ML19338F838

IE Insp Rept 70-0754/80-04 on 800707-10.No Noncompliance Noted.Major Areas Inspected:Organization Mods to Facilities & Sys,Internal Review & Audit,Employee Training & Environ Programs

ML19338F838
Person / Time
Site:	07000754
Issue date:	08/25/1980
From:	Book H, Cooley W, Thomas R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML19338F836	List: ML19338F835 ML19338F838
References
70-0754-80-04, 70-754-80-4, NUDOCS 8010270373
Download: ML19338F838 (10)

Text

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U. S. NUCLEAR REGdATORY CotetISSION -

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MOFFICE OF INSPECTION AND ENFORCEMENT i

1 REGION. V -.

j Report'No.

70-754/80-042 3;x Docket Nob

'70-754 License No..

SNM-960-o Safeguards Group

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Licenseet

-Genaral Electric Comoany

'Va11ecitos Nuclear Center-P.:0.. Box 460.-

Pleasanton; California 94566-Facility Name:'

Vallecitos Nuclear' Center-

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. Inspection at:-

Pleasanton. Califosnia Inspection conducted:

' July 7-10. 1980

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Inspectors:

W. J. Cooley',' Fuel F$ilities Inspector Data Signed Date igned h

. Approved by:

R. - 0. -

omas,

_. Approved By:

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f. Materpls Radiological Protection Date S @ ed

'.72f/fe; H.- E. Book, Chief Fuel Facility and Material Safety.

Date Signed -

Branch-Suspary:-

Inspection on July 7-10,n1980 (Report No. 70'-754/80-04)~

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Areas Inspected:1 Organization;' modifications.:and changes to facilities;and systems; internal review and audit;? safety committee activities; employee training; operations.

review; criticality safety; environmental 1 programs; and confinnatory measurements.

m The inspection involved 26-inspector-hours'onsite. by one inspector.

Results: No' item of. noncompliance or deviations were identified in.the subject areas inspected.:

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Persons Contacted

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l R.D W. ' Darmitzel, Manager. Radiation Processing. Operation s

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- W.: H. King, Manager. Nuclear Safety..

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• G. E. Cunningham, Senior-Licensing' Engineer-4 D. C.~Bowden, Nuclear Safety Compliance Engineer Nuclear Safety

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W.:R.. Lloyd, Senior: Engineer,' Nuclear Safety P..S. Webb, Manager,. Radiological:and Environmental Protection a

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C.'. A. Hooker, Specialist, Radiological and Environmental Protection D

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.R. E. Butler, Manager, Radioactive Products 1and Services P

D. ' L. - Zimmerman, Radioactive Products and Services Analyst.

u L. 'A. Hanson, Manager,7 sotope' Product Fuel Recovery and Irradiation I

J. : I. Tenorio, Manager. - Remote. Handling Operations -

M. L. Thompson, Manager, Advanced Fuels Laboratory L

Tc E. Ludlow, Advanced Fuels Laboratory Superintendent R. D. Reager, Chemist"

• Denotes those attending the. exit interview.

2.

Oroanization E. F. Kurtz, former Manager,' Advanced Fuels Laboratory has left that

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position.

M. L. Thomoson.is presently Acting Manager, Advanced Fuels a

r Laboratory.

R. C. Gebhart is Manager of Laboratory Operations and

.T. E. Ludlow, is th.e Advanced Fuels Laboratory Superintendent.

R.' E. Broz, Training and Emergency Coordinator, Radiological and Environmental Protection has terminated. : At the time of his termination his responsibilities incladed anduct of the employee training program. Emergency Coordinator, and Environmental Protection Specialist.

E. J. Strain, Engineer, Nuclear Safety Technology has been named Emergency Coordinator for the Vallecitos Nuclear Center Site.

The empioyee; training function is-pesently being shared by i

-Messrs..P. SJ Webb, R.-L..Morgin, and D. C. Bowden. The~ environmental.

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program is being conducted by Mr.-Webb and H. C. Mohr, former Environmental Specialist..

A new environmental specialist has been selected from site personnel.

That individua11has 25 years experience in the nuclear field,15 years 2i s

of which is onsite experience including work in environmental chemistry.

- A requisition has.been submitted for an individual to conduct the employee J

training program.

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"A requisition has been' submitted for three additional Health Physics L

. Monitor positions. Two of those positions have been approved and'

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filled while the management decision is awaited on the third request.

With the two approvals a compliment of-seven Health Physic Monitors is s

?available to MrL Webb.-

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13.,lModificstions~ and' Changes to Facilities and Systems / Change Authorization 3. =."

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Procedure,,

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R' iThe licensee is decomissioning3the; Advanced FuelsTLaboretory. The

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decomissioning is scheduled:for completion'by about December -1981..

f Glove boxesland:other equipment had-been' decontaminated and removed -

u from the(wet chemistry portion.of the laboratory.' u At-the time of this inspection. equipment had been decontaminated and removed from glove boxes in the ceramicoline. Those boxes had been decontaminated to various

.deg'ees and were being prepared for packaging and shipment to a waste r

- burial' site.

' The Advanced Fuels Laboratory decommis'si.oning program is being controlled

'by Change Authorization. Because' of the complexity.of the decomissioning, that authorization:was being changed progressively by amendments and.

additions.iAn authorization began with a? plan:for test decontamination of the glove box. The plan included a requirement for the development-of acceptable' decontamination procedures; presented the format of records of surveys to be kept; presented the deco'ntamination limits; and presented-

'the required instrument calibrations'and proposed decontamination methods. -

An addition to the Change ~ Authorization file presented a method for' handling large metal parts of equipment to be removed from the glove boxes;' a recalculation of: the-pePissible' remaining plutonium in a box with respect of the use of a DOT type 7A container; and calculations to determine if the i.

- ' total remaining' transuranic activity.would meet:the 10 nanocurie per. gram requirement:in land burial licenses. An extended decommissionir.g plan'.

for the Advanced Fuels Laboratory along with the offical test results on decontamination of glove box number 35 were included in the Change Authorization file.

The mixed-oxide chemical line and the. scrap recovery line remained intact l

in the wet chemistry portion of the ' Advanced Fuels Laboratory.

d Inventcry of fissile material had been reduced considerably in that i

. laboratory.

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The licensee had removed all fissile material from the Building 105 vault and from the building 105 Critical Experiment Facility. ~ The Critical Experiment Facility was being used by the Advanced Fuels Laboratory for.

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-the installation of a metal frame and chemica1' train to study the 1

de:struction of various chemical wastes associated with processes -

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. which have been developed 'at the Advanced Fuels Laboratory.~ The work 4

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-planned in the Critical Experiment Facility is with nonradioactive j

F material.. At some future date the eouipment installed in the Critical Experiment Facility will-be relocated to Advanced FuelsLlaboratory at.

hich time the ex'perimentation.would continue using. naturally occurring w

eradioactive materialiand perhaps depl. eted uranium.

a The. licensee has completed the decomissioning of the Development Shop q

-located in building <106 at the Vallecitos Nuclear Center. That 1

' decomissioning was accomplished 'using the licensee's Change Authorization S

M Procedure. 7This inspection included review of that Change Authorization ~

and of the direct reading and' smear type survey that was made of the p

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'buildi 106 shop.' ~Pemissions and conditions concerning the decomissioning lng were fi ed in the Change' Authorization-file. They included deactivation -

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.of. criticalityclimit' areas;* deactivation of the criticality detector; hJ

- removal:of: signs.and postings;. deactivation of. air sample monitors; a

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[permissionito remove.the HEPA filters; requirement that the buil' ding!106 '

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exhaust fans remain' activated;'and the. requirement of quarterly surveys -

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'to determine if radioactive materials are introduced into building 106.

The Change' Authorization inc~uded a direct and -smear type survey for alpha t

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.and: beta-activity in the-building 106.and a certification of the accuracy r-of:that survey?as well;as certification-of "0" contamination of special-nuclear.

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- materia 1 Din that bui.1 ding.. A special requirement was retained in that e

t the' critical alarm system sas required Lto remain active for use with J

P lSpecial Nuclear. Material in association with the x-ray equipment located in buildfng 106 shop. A-limit of.approximately 235 grams contained U-235 was placed on-the x-ray room location.

i The decommissioning was treated as a temporary deactivation and conditions

~ d were placed upon reactivation of the Development Shop with the use of radioactive materials. The conditions.were that a new Change Authorization

.was-required; fair samplers-were to be restarted,-' posting was to be accomplished as required; routine surveys were to be reinstituted; and a

ng the HEPA filters were to be restored and tested.

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4.

Internal Review'and Audit Criticality safety audits are perfomed by the Senior Engineer, Nuclear' Safety. The frequency of~those audits varies from crea to area dependent U

upon:the hazard potential. This inspection includt.d 'a review of the

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records of criticality safety audits conducted frra approximately a

December 1978 thru March.31,1980. Over that period of time 16 audits y

were made. 'On tnree occasions deficiencies in' posting criticality limits

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-were discovered and: corrected.

A second type of criticality safety audit is conducted by the Health a

Physic Monitors _in the Radiological and Environmental Protection' Unit.

D Those audits are conducted. monthly.and are~ addressed to SNM inventory control, housekeeping, posting,'and criticality alarm operability. This f

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. inspection included a -review of the records-of. audits of that type. -The~

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audits -had been conducted in buildings '102 103,105,-as well as the Advanced Fuels. Laboratory, Plutonium Analytical Laboratory and various b

storage facilities onsite. 'During an audit of certain plutonium facilities d

on October 29,1979, a critical alarm check was-found to be missing for 21

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October 3, 1979.

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1 the month of-September 1979. That check had been accomplished on' q

n 1This. inspection.also included a review of ~ records of radiation' safety 9

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audits which have been conducted by a Nuclear Safety Compliance Engineer.

Those audits.were conducted during the period of approximately December 1978 it through-Junet1980. :Those audits addressed use of radiation producing ~

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machinesiand radioactive materials which were of. interest to the. State of;

California and the NRC. The' fo110 wing ;11st includes most of. the-subjects

audited followed by the-number of times the subject was addressed.

of criticality limit areas and associated posting (3)y machines-(2);: audits

'(in parenth' eses) over the review period.' --Useiof x-ra

visual inspection of HEPA filters.(4);. audit of Vallecitos Nuclear Center Em

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,andWtraining Program (4); Area radiation safety audits (ployee Training 2);.Fol c

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srecommendations(forlisprovement'_(2); Status'of 1978 critica11ty drill-z u ~

DrecommendationsTforfimprovement (1); Status of 007 tests (1); Status of 5

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' change: authorizations ~ (1); Status;of 1979 investigations E(1); status of a 1 Y*J fealibration' of Vallecitos: Nuclear Center Dosimetry instruments and hand 7

A and foot backgrounds:(2); Audit of respiratory protection program (1);_

'and site posting review (1).

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.The most recent problems encountered were lhe development of a backlog

of_ employees for_whom requests for training.and retraining has been received.

A backlog of. instruments to be calibrated and repaired was also developing.

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~In September 1979:a more formalized approach to the radiation safety Jaudit program was' instituted.. As a-minimum audit program the following

' subjects were to be addressed on a annual; basis: employee training.

respiratory protection program; change authorization followups; investigation followups; isotope use: authorizations; emergency: plans-

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1and procedures;. waste handling; and calibration of instruments.

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~ Additional subjects to be addressed on a biennial basis were ventilation;

._high radiation alarm systems; posting and labeling; criticality limit

. area posting;; verification of licenses; radiation and environmental A

protection procedures and practices;.' standard operating procedures; exposure and bioassay records;'and coding of_ piping and lines..

The review of radiation safety audits indicated that well written and <

clear reports on the audits are produced. Problem areas are recognized 1d and-correction is accomplished.

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- 5.

Safety Comittee Activities s

This inspection, included a' review of minutes of meetings of the Vallecitos Technical. Safety Council dating from September 1979 thru. March 1980. The-meetings were announced by letter to council members which included a

. meeting addenda..- The meetings were held at quarterly intervals. Attendance

' 1 at the meetings was recorded and included participation by nonmembers. of i

~the council.;

.Over. the period of_ review the subjects discussed included the ALARA concept ead goals;' waste handling-problems; fire prevention'and emergency planning; 3

' che California Water Quality Control Board Water Discharge Pennit; respiratory 1

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protection employee retraining; and the'decomissioning plans for the Advanced W

Fuels l Laboratory..

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The individual employee whole body dose ALARA goal for the year 1980 was 1

set at 3 rom. The present exposure rate at the Vallecitos Nuclear Site :

L s approximately;73 man-rem / year.

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6. - TEmployee Tra'ining:

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The following courses of instruction 'are available in the Vallecitos.

" Nucle'ar. Center Employee Training Program.-

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lNew hire orientation course.- Four hours of class-lecture followed by:a Ltestc A117 page textual handout is' furnished to.the' employee

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ifor reading'.and: includes 16 references'of the subject of radiation.

The 'testiconsists of six._ questions.

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- x b2 7 ThA most intensive. course in radiation. of nuclear s'afety at the ~.

d Vallecitos Nuclear Center is titled Radiation ~ Safety;at Vallecitos -

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! Nuclear. Center. iThe course-is required within 1 year of hire of

any individual: working routinely with radioactive materials.

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? Twenty-four hours'of classroom lecture time is devoted.-.1A fifty i page training manual assembled by R.4L. Morgin is used;as a text.

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. A' test:and. passing grade is required. eThe test is~ closed book and _

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consists of 45 questions including essay, multiple choice, and word.

matching types.-

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A short course in'Ra' iation Protecticn Fundamentals consisting.of-d

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four hours-of class-lectures'and a test is available touemployees -

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outline is similarato a. above and includes' the same references

' i for-the study of radiation. 'The test consist of 25 questions:

including true or false, word match. and fill blank. types.

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'A course specific to criticality safety is available and consists ~ of-about four' hours of class 11ecture time. The course

d-outline consistsTof approximately. 25 pages including criticality g

accident.h.istoriest a bibliography; and discussions of the various parameters which must be controlled to preclude.a criticality. The.

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test consists of 25 questions which are again an admixture of multiple' choice, true.and false, essay, and blank; fill.

et Respiratory protection training is a course given on an as needed

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basis. Classroom lecture time and' demonstration is about eight

f hours. The course outline addresses the preventic 3 internal.

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. deposition, metabolism, critical organs, chronic exposure, single

' incident. and detection methods for-internal exposure. -The test F.

consists of six= true/ false;ffour multiple choice, six essay /discussioni and eight: additional questions.

f.' ~ A course on radiation detection instruments'is available on an -

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and~ Advanced Fuels Laboratory. A test 1s given.

T as-needed or as-requested basis by personnel working at GETR,.RML' g.

Reactor Operations) Health Physics is available on an as-requested-b

= basis requested by employees;at GETR and is accompaned by a. test.

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~- A course entitled High Dose Rate Training has ~been devised for -

special wo'rk-such as ' decontamination involving?high ~ dose ~ rates.

It consists of eight hours lof. class ".acture followed by a test.

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0ther s'pecia11 classes approved as' retraining courses may be devised

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)at the request of_ management.

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,iRetrainingLisfscheduledonceeachtwoyearsforthoseworkers-4 exchanging personnel dosimeters'at monthly frequency.

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jp i f iThi$inspedioniincludediisitsito Building 103, ChemistiryLand Metallurgy;:

Building;102CHo_t Cell. Operations and Advanced Fuels" Laboratory; M*

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Building >105r formerly Vault 1 Storage Facility;1 Building 400, Natural;.

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f c uranium Waste. Recovery Studies;'and the waste treatment facility atLthe

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G southern most border of the Vallecitos Nuclear Center Site. -

<q mThe Bdilding;103 vault was:beingJused?for the storage of uranium.of.

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Tvarious enrichments.1 Appearance 1of variouselaboratories in/that! building

%s (wa's generallyJgood with th' " exception 1of laboratories 1209fand 210 which e

hadfa cluttered appearance.

:The fuel storage facilitiesEin: Bui.1 ding :105 -

l:(plutonium clad vault and Critical Experiment Facility):were no longer 1 g

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.beingiused forithe storage of fuel.' 1he Criticalt AssemblyiFacility was-being used-forfca-tin ~ Advanced: Fuels Laboratory chemistry studies.

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plutonium wasistored in the Advanced Fuels Laboratory vault. uThe'.

3 AdvancedLFuels Laboratory was being-decommissioned and several ceramic' t

line glove boxes:had been decontaminated.

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1,.2:and 5-in the hot cellicomplex of Building' 102 were in use in ;

the studyLof spent fuel elements..; Cells 3-and 4 (medical-~ isotope and b

alpha. emitter cells) were'not being used. ;The waste treatment: plant at the

~~p southern ~ border of the' Vallecitos" Nuclear Center: Site was-visited. 'Only i,

one of.four,--60,000 gallons: retention basins' were in use at the time.

1 Basin A-2.was filled to about;30,000 gallons.- Opportunity was7taken to p-obtain two liquid waste samples. E General Electric Company. personnel obtained an_ additional two samples from thelsame basin and' intends to.

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-have' theminalyzed for radioactive constituents. - The results of the -NRC o

analytical work will be presented'as.a; addendum to this report when those-L results have been received.1 1

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? rit1cality Safety

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.Theolicense'e has b'egun a: program of restudying all nuclear safety analyses

. pertaining Lto operationsTat w Vallecitos:: Nuclear Center. The plan is

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~-to show 'that the use off this material:in 'any area will not< result in a 6

criticality accident even if all fuel in that area.is rearranged in-its,

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most rea'ctive. configuration. : At least two analyses;of. that type have' been Q

' accomplished;an(this inspection 11ncluded a review of,the reports of:that j

W analytical ^ work.

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R The two contingency criteria for:the rwnalysis of,the Building 103 fissile, q

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material vault postulates;aiseismic event in'which all that fissile material y1 is: brought together: simultaneously. ' Additionally, as the material is~ brought

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together i.tTis ! configured -1.nrits most reactive geometry.. In one model three?

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-2Rl pip'estare assumed to come together tin triae. gular pitch and then' fissile material: external to:those; pipes -1sf allowed to rap itself.around the p1 Des m

?in 11ayers: accordin~ ;to the~~ enrichment:of the fuel. L Varying amounts of 4

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moderator is(then introduced ;to1thisfsyr, tem to determine the maximum' m*

., keff for optimum moduation and full wa'.er reflection.) "In a:second model'

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[ fuel externalfto the threet2R pipes i',:a_110wedito comeLtogether in layersL P

p' l accordingito enrichment in a cylindr'ca12 geometry and the:three. 2R pipes

$Jr' 3are assumed to assemble themselvesfaround that fuel in close-packed array.

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?Again,Lmoderatorfis introduced to determine the. maximum keff for, optimum.

2 W- ' ' 'xz ~ -n moderation'and. full water reflection.)

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@M VW $ Thy three; 2Rf pipest areithe4 central ;contain:rs: of-mod 21 6M : shipping: c:ntain a

3:P 5.1TheirL contents are limited!by'massiand' enrichment and'allistructural material J

yg f ' ~ 'Tofithe.6M shippingicontainer is: assumed to be-lostnin order to bring the pipes.

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together.dModeratorlis iintroduced 'into, the pipes' in increments to determine N

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lthe;most; reactive pipe loadingland the corresponding height:o.f fuel.in' the.

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LlayersTof various enrichmentsfofifuel are placed around the pipes with. -

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' waterfreflection of the.modeliis used in each case. tThe; analysis.of the

- fuel: enrichment: decreasing as'the radius of the assembly increases'.

Full.

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IV criticality; code.-

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a IFoNenr'ichmentsjlessi tha'n five' percent a correction was introduced in the W

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.calculationito a'ccountiforLclumping of'the.losenriched material'in. the j

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-Under the above: postulated conditions the entire: vault loading was found-

.N to betsubcritical.-

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-The. analysis. included an-interaction calculation _ for the normal vault.

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loading.,TheLreport included la: Plan viw of the building 103. vault loading limits and a print out of:the interaction calculation. The date of completion

'of the analysis:wasifebruary 28, 1980.-

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C Radioactive: Materials Laboratory cells number 1 ar;d 2..

In this case ranspherical mode 1Tof, fissile ~ material layered by enrichment wasL used.

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- As--in' thCcase 'of the building'103 vault, a correction was made. for the e

greater raactivity of heterogeneous.: moderated systems cf enrichmentDiess J

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'than five percent.' 3The H/U-235 ratio was varied and the rcost reactive, reflected,.and: moderated; system wasLshown to be' less than -individual cell fissil_e material < inventory limits. ~

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All permitted fissile units in cells l 'and-2 were considered in an inter:ctionJealculation and were shown to be.subcritical. - The report.

iir.cluded a statement of cel1~1_imitslalong with a. plan view of the cells J

- and details:of the-. interaction calculations..

9 9.L Envi ronmental ' Surve111 ance Program :

Since the lastLinspection, the licensee has considered a reduction in the

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numbr.. 'af: samples acquired as/part of.the' environmental program.

A'_ summary-by

~ f i N study-along~with a proposed revised program was. presented by o

Radiation'and Environmenta11rotection to Nuclear Safety Technology on March 28,_1980.. A licenseeis Change Authorization procedure was used

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to review?the proposals and finaljapproval for the changes _was-granted 1by; management lon June ~ E.1980..

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' The study. included a revieE of enEironmental data as published in annual-susenary reports <for the years;1971 through 1979 for samples in the-' categories

' of vegetation,; stream bottom, soll,l aquatic vegetation, and cloud gamma :

dosimetry.1 'That,dataLindicated no accumulation or rcconcentration.over W

Ethe period of the review and taken.along with a reduced activity as' the

+-

Va11ccitos Nuclear Center!resulted in the approved reduction in the program.

/

ENo reduction in the number'or types of samples required by California i@

Regional Weter. Quality Control. Board Discharge Pemit was pemitted.. The s

following-TABLE.I presents the environmental. prograsi prior to the changes

+

and indicatesithe' changes instituted..

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+ TAB'LE Il i^

$9 W. nb 3, f 1

E % -jEnvironmental ProgramfPrior;to '

ChangesLin the Basic.

Og fpW ' sJu'ne 2.t1980-Environmental Program kNuid effluents? discharged frams No. change.

a.

$.M ' ',

rthe!siteLanalyzedforfPu-239, 4

i VN? 4 MSR-69/SR-90,tTritium, Cobalt 60, fg 2

clodi.ne :131. ;

V W,'

L e, LL No. change.

/

S&W b.- !Airbornt particulate and. gaseous:

K>m-Stack effluents analyzed for alpha,

^

?, ' r-

~

N beta-gama,' noble gas,-Iodine-131. '

n.

1. T

.c.-

1 Water' analysis froml streams crossing No change.

Ar

thelfallecitos' Nuclear Center Site, W-

?Vallacitos' Creek, Arroyo de:la Laguna,

'x y

a and Alameda; Creek, analysis for

' 'A

'M,

4 alpha',1 eta-gamma..and tritium.

~

[sw.

b

~~~

~

7 d.

Various we11' water from wells both No change.-

f4 V onsite and'offsite, analyzed for alpha

.' activity and beta-gama activity.

j

.. =

nE

, e.. Stream sediment samples analyzed for-Retain onsite -sample. basin outfall:

~

Cobalt 60, Cesium 137,1 Strontium 90, sample, Vallecitos Creek offsite'

'~,

plutonium-239,!and-potassium 40; sample, and Alameda Creek offsite-sample-Eliminate site lake bottom

(-

1The sediment" samples analyzed for:

sample.

Reduce ~freqcencyTof two3 additional offsite stream bottom;

p Alpha,1 beta-gama," strontium-90 --

samples from monthly / annually to cesium' 137, cobalt 60.. and. potassium 40.

annually.

f.

Soillsamp1es analyzed for. alpha,.

Eliminate all soil-samples from the.

min

beta-gammas strontium

90, cesium 137, program.

u

~ cobalt' 60; and potassium _a0.

^

m

g..

Cloud-gama TLD ' measurements.

' Reduce all cloud.gama-analyses from.

('

b

' measurement f(cloud-gamma. radiation monthly / quarterly to' annually with.

1st 31 statio(ons on the.Vallecitos the exception'of. station number l' W

. Nuclearf Center. Site.

'(water tankrabove hillside storage).

u

+

9

h.x -Perimeter airzsample stations analyzed No change.

R g: %

fob alpha. beta-gamma. and' Iodine 131.

a

~.

L Vegetationis~amples = analyzed for ~ alpha',.

Of' the total of 20 vegetation samples, F k

~

1.

beta-gamac strontium 90,-Iodinec131,..

eliminate.all three marine flora v

/ cesium 137,1 cobalt 60 and' potassium 40. :

fsamples (aquatic flora); eliminate

.l x.

.a total. six additional onsite and a

offsite' vegetation samples; reduce.

q Y

,the-frequency of an additional nine 4

w aJ.

=

~1 offsite and onsite vegetation samplesD o

4

from monthly / annual to annual sample e

x only;-

pg=w t

y..

a 7

i $

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~%

1' 79, tu

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y%

u 1

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ny:

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- (The'above# changes' in-the~ envirottnental program are primarily a reduction -

~

in the; number. and~ frequency of each sample type except~ forl soil sampling.:

Soil-samples have been climinated from-:the program...

t x

IThe ChangeIAuthorization review of;the program changes recommended not only--

'y further reductions in the environmental program as might be justified by

~

Lfurther reduction in; activity at-the: Vallecitos Nuclear: Center but also.

recommended increases iin-the environmental monitoring program if any increase

~

in site' activities from those currently being conducted might occur.

.-10.' Management Inverview~

~

j The scope and results of this inspection where discussed with Mr. G. E. Cunningham on' July 10,.1980. The licensee was: informed that no items'of. noncompliance and no deviations were-observed within une scope'of the inspection.-

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