ML20217C149

Insp Repts 50-070/98-201,50-073/98-201 & 50-183/98-201 on 980209-13.Violations Noted.Major Areas Inspected:Review of Safeguards Programs,Security Program,Procedures,Radiation Protection & Matl Control

ML20217C149
Person / Time
Site:	Vallecitos Nuclear Center, Vallecitos  File:GEH Hitachi icon.png
Issue date:	03/18/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217C121	List: ML20217C117 ML20217C128 ML20217C149
References
50-070-98-201, 50-073-98-201, 50-183-98-201, 50-70-98-201, 50-73-98-201, NUDOCS 9803260333
Download: ML20217C149 (18)

See also: IR 05000070/1998201

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ENCLOSURE 2

U. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

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' Docket Nos: 50-73, 50 70,'50-183

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- License Nos: R-33, TR 1, DR-10

Report Nos: 50 73/98 201, 50-70/98-201, 50-183/98-201

' consee: . General Electric Company

Facility: Nuclear Test Reactor (NTR)  !

Location: Vallecitos, CA

- Dates: February 9-13,1998

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~ Inspector: ' Craig Bassett, Senior Non-Power Reactor Inspector

Approved by: Seymour H. Weiss, Director

Non-Power Reactors and Decommissioning

Project Directorate

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Division of Reactor Program Management

Office of Nuclear Reactor Regulation

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EXECUTIVE SUMMARY

General Electric Company Nuclear Test Reactor

Report Nos: 50-73/98-201, 50-70/98-201, 50-183/98 201

The primary focus of this routine, announced inspection was the on-site review of selected

aspects of the licensee's Class ll non-power reactor operation including: organization and

- staffing; review and audit functions; procedures; radiation protection and ALARA programs;

effluent and environmental monitoring; the shipment of radioactive material; the safeguards

and security program; and the material control and accounting program. Oversight

programs for two of the licensee's deactivated facilities, the ESADA Vallecitos Experimental

Superheat Reactor (EV6SR) and the General Electric Test Reactor (GETR), were also

reviewed.

Chances. Oraanization. and Staffino

e The licensee's organization and staffing remain in compliance with the requirements

specified in the Technical Specifications.

Review and Audit Functions

e . Audits were being conducted by the Regulatory Compliance group and th,e Vallecitos

Technological Safety Council reviewed change authorizations and facility changes

according to the requirements specified in the Technical Specifications.

Procedures

e Procedures were being reviewed and approved as required and changes to procedures

were acceptably reviewed and approved.

Radiation Protection Prooram

o One appbrent violation was noted for failure to comply with TS Section 6.3 involving

f ailure to complete monthly surveys within the six week time frame prescribed by TS.

e Postings met regulatory requirements except for one instance of failure to post a

radiation area (as noted below).

• Personnel dosimetry was being worn as required and doses were within the licensee's

procedural action levels, and NRC's regulatory limits.

• Radiation monitoring equipment was being maintained and calibrated as required.

e The Radiation Protection and ALARA Programs satisfied regulatory requirements.

• One apparent violation was noted for failure to post a radiation area.

e Another example.of an apparent violation was noted for failure comply with

L TS Section 6.3 involving failure to provida whole body counts four times per year as

l required by procedure for individuals assigned to work in radioactive material areas.

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Effluent and Environmental Monitorino '

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Les Effluent monitoring satisfied license and regulatory requirements and releases were

within the specified regulatory and TS limits.

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Transportation of Radioactiva Materials

. e. Radioactive material was transferred from the Nuclear Test Reactor to the 102

Radioactive Materials Laboratory (from the reactor license to the materials license) for-

~s hipment and/or disposal according to procedure.

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t Safeguards and Security

e ! One~ apparent violation.with three examples of failure to comply with the Physical

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- Security. Plan was noted.

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3 e Other aspects of the NRC-approved security program at the facility were being _

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acceptably carried out.

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s Material Control and Accountability

• No deficiencies were identified in the licensee's Material Control and Accounting .

• program.-

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G= Status of Other Reactor Facilities 1

er The General Electric Test Reactor and ESADA Vallecitos Experimental Superheat Reactor

' facilities are being maintained in accordance with the applicable TS requirements and in-

a safe shutdown condition.

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' Summary of Plant Status .

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The licensee's one hundred kilowatt (100 kW) Nuclear Tes't Reactor continues to be

operated in support of neutron radiography. During the inspection, the reactor was being

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started up and operated several hours a day to complete various radiographic work projects.

1. Changes,LOrganization, and Staffing (69001)

a a. Insoection Scone

' The inspector reviewed the following regarding the licensee's organization and -

staffing to ensure that the requirements of TS Section 6.1 were being met:

4 , . ~ ~ the organizational structure,

. management responsibilities, and

f; * ' staffing requirements for safe operation of the reactor facility,

b. Observations and Findings

Through discussions.with licensee representatives the inspector determined that

management responsibilities and the organization at the facility had not changed

since the previous NRC inspection in June 1997 (Inspection Report No. 50-73/97-

1. . 201). The inspector determined that the Manager of the Vallecitos and Morris -

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Operations (V&MO) was responsible for the NTR facility license. The Manager of

Facilities Maintenance was responsible for the overall safe operation and:

' maintenance of the facility as specified in the TS.. The Manager, NTR, was

responsible for the. routine safe operation and maintenance of the facility.

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Through review of records and logs and through discussions with licensee personnel. j

- the inspector determined that the staffing at the facility was acceptable to support' i

the work and ongoing activities.l The staffing met the requirements of the TS.

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c. Conclusions

The licensee's organization and staffing remain in compliance with the requirements l

'specified in'the TS.- 1

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2.' Review and Audit Functions (69001) l

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La. Insnection Scone  !

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The inspector reviewed the following to ensure that the audits and reviews l

. stipulated in the requirements of TS Section 6.2 were being completed: i

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... Vallecitos Technological Safety Council (VTSC) meeting minutes,

e ~ Vallecitos Nuclear Center (VNC) RegJiatory Compliance audits, . ,

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. - VNC Nuclear Safety Procedures, )

. - VNC Safety Standards, and. .

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TS duties specified for the cognizant Nuclear Safety Review Groups responsible

to the Manager, V&MO. J

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- b. . Ohnarvations and Fin'dinas

Section 6.2 of the TS requires that the independent review function be performed -

under a written charter. VNC Safety Standard No.1.1, " Charter - Vallecitos

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s Technological Safety Council," Revision (Rev) 7 stipulates that the VTSC is

' respontNo for reviewing Change Authorizations (CAs), reportable incidents, and

facility changes. VNC Safety Standard No.1.2, "VNC Regulatory Compliance

i Function Charter," Rev.~ 7, requires that the VNC Regulatory Compliance group

reivew plant operations, changes to procedures, CAs, and retain exposure records.

. The VTSC was required to meet quarterly.

The inspector reviewed the VTSC meeting minutes from September 1996 to the

present. These meeting minutes showed that the committee met as required by the

TS with a quorum being present. The inspector also noted that the VTSC had

considered the types of topics outlined by the TS.

It was noted that the Regulatory Compliance group completed audits of plant

operations and reviewed changes to procedures and CAs. Audits were varied so

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that all aspects of the licensee's safety program were reviewed every two years.

The inspector noted that the audits and the resulting findings were detailed and that

the licensse's responses and corrective actions were acceptable. ,

c. Conclusions

Audits were being conducted by the ' Regulatory Compliance group and the VTSC j

reviewed change authorizations and facility changes according to the requirements i

specified in the Technical Specifications.

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3. Procedures (69001) ' j

a. Insoection Scone

The inspector reviewed the following to ensure that the requirements of TS Section 6.3 were being met concerning written procedures:  ;

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• selected operations procedures, l

.c selected safety procedures, and  ;

the process used by the licensee to revise, review, and approve all facility

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procedures.

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b. Observations and Findinos -

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l The inspector verified that selected procedures and associated changes had been

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reviewed and approved in accordance with the TS, applicable administrative

L procedures, and the VNC Regulatory Compliance Function Charter. ~ Changes were

l' properly reflected in the copies of procedures'in use in the NTR control room.

) c. Conclusions

. Procedures were being reviewed and approved as required and changes to

procedures were acceptably reviewed and approved.  ;

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g f 4. Radiation Protection Program (69001)

a. Insnaction Scone ,

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The inspector reviewed the following to _ verify compliance with 10 CFR Part 20 and

tho' applicable licensee TS requirements and procedures:

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r; .: RadiStion Monitoring (RM) survey records,

-e' = radiological signs and posting,.

- . dosimetry records,

.. calibration records and periodic check records for radiation monitoring

instruments,'.

f. the Radiation Protection Program,

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. the ALARA Program, and

1 ;the Bioassay program.

E The inspector also toured the licensee's facility and observed the use of dosimetry

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~b. : Observations and Findinos

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( Surveys

TS 6.3 requires that the licensee have procedures for various activities

including radiation protection,

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Standard Operating Procedure'(SOP) 7.3, " Radiation and Contamination

. Surveys," Section 5.2 requires that routine surveys be conducted by radiation

control personnelin accordance with Nuclear Safety Procedure 3550, " Building -

'105/NTR Work Routines."

Nuclear Safety Procedure 3550, " Building 105/NTR Work Routines," Rev. 7;

dated October 1995, Sections V.A, B, and D require monthly surveys in the

Machine Shop, NTR Setup Room, NTR Darkroom, and the Hand and Shoe

Counter.Section V.E requires monthly surveys in the North Room and the

. South Cell.

. TS 4.6 defines monthly to be an interval not to exceed six weeks.

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az .The inspector reviewed the results of daily, weekly, monthly, and other periodic

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contamination and radiation surveys. It was noted that, in most instances, the

, L required surveys were completed by RM technicians as required by TS and

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licensee procedures.'- Results were evaluated and corrective actions taken as

required.

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However, in 1997, the inspector noted that the Machine Shop, NTR Setup

Room, NTR Dark Room, and the Hand and Shoe Counter were surveyed on -

7 September 10 but not again until October 28. This represented a period of ,

time exceeding six weeks. Also, the North Room and the South Cell were 1

surveyed on December.10 but not surveyed again until January 27,1998. This '

was also a period of time exceeding six weeks. In both instances no

contamination was detected on the follow-up survey.

' The licensee was informed that failure to complete a survey of the

aforementioned areas was an apparent violation of TS 6.3 (VIO 50-73/98-201-

01).

(2) Postings and Notices

Copies of current notices to workers required by 10 CFR Part 19 were posted

in appropriate areas in the facility. The copies of NRC Form-3 that were posted

were the latest issue.

(3) Dosimetry -

The licensee used a National Voluntary Laboratory Accreditation Program

(NVLAP) accredited vendor to process personnel thermoluminescent dosimetry.

An examination of the records for the past two years through the date of the

inspection showed that all exposures were within NRC limits and licensee

action levels. Dosimetry was acceptably used by facility personnel.

(4) Radiation Monitoring Equipment

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Examination of selected radiation monitoring equipment demonstrated that the

instruments had the acceptable up-to-date calibration sticker attached. The

calibration of portable survey meters was typically completed by on-site

personnel. Calibration frequency met procedural requirements and records

were maintained as required.

(5) Radiation Protection Program

The licensee's Radiation Protection Program was established and described in I

various VNC Safety Standards and Regulatory Compliance Nuclear Safety

procedures. The program was further outlined in SOP 7.1, " Radiation

Protection Program," Rev. 820, dated September 27,1996. The program ,

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included a requirement that a review of the program be completed annually.

The annual reviews were being completed as required.' The program also

outlined the requirements for training in radiation protection, as well as the

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policies and procedures to be used when working with radioactive materials )

and in facilities where radiological work was performed. The program appeared j

to be acceptable.

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. The licensee no . longer routinely used respirators for radiological work.

However, the capability was being maintained on site by emergency response

personnel. The licensee's Respiratory Protection Program was being carried out

as outlined in the procedure and associated instructions. Training was being

conducted, bionssays were being completed, annual personnel physicals were

being conducted, and the equipment was being checked and maintained as

required.

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The inspector reviewed the Radiation Work Permits (RWPs) that had been

written and used during the past two years. It was noted that the controls

specified in the RWPs were acceptable and applicable for the work being done.  :

The RWPs had been reviewed and approved as required. i

(6) ALARA Program

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The ALARA Program was outlined and established in procedure SOP 7.5, )

" Radiation Exposure and Control," Rev. 823, with an effective date of April 29,  !

1994. The ALARA program provided guidance for keeping doses as low as  ;)

reasonably achievable and was consistent with the guidance in 10 CFR Part 20. j

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(7) Facility Tours i

10 CFR 20.1902 requires that radiation areas be posted with a sign reading ,

" Caution, Radiation Area." 10 CFR 20.1003 defines a radiation area as an i

aree, a::cessible to individuals, in which radiation levels could result in an

individual receiving a dose equivalent in excess of 5 millirem in one hour at

30 centimeters from the radiation source or from any surface that the radiation

penetrates.

The inspector toured the control room, selected support laboratories, and other

areas with a licensee representative on various ocassions. The inspector noted

that the facility's radioactive material st' orage areas were properly posted. No

unmarked radioactive material was noted.

During one tour, when the reactor was operating at power level of 100 kW,.

both the inspector and the licensee representative conducted a radiation survey

of some of the areas surrounding the reactor. Postings at the entrances to the

controlled areas,' including the reactor control room, were acceptable for the.

hazards present. Radiation areas were posted as required with one exception.

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The inspector found that an area on the east side of the South Cell, outside the

cell wall, had a radiation level of 6 8 millirem per hour (mr/hr) as measured at a

distance of at least 30 ' centimeters'from the wall. The licensee measured levels

~ from 5.5 to 6 mr/hr. The area was not posted 'with a sign indicating that it

was a radiation area..

The licensee was informed that failure to post an area in which radiation levels

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could result in an individual receiving 5 millirem in one hour was an apparent

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violation of 10 CFR 20.1902 (VIO 50-73/98-20102).

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-(8)- Bioassays 1

. TS 6.3 requires that the licensee have procedures for various activities

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, VNC Safety Standard No. 5.3.0, ~ Bioassay Program," Rev. 6, dated November

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' 1996, Section 3.7 stipulates that an employee's supervisor or manager is

responsible for initiating the action to begin bioassay sampling and for notifying

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Regulatory Compliance of all radionuclides with which their employees will be

>+ working. A written notification from supervision can be made using forms

VNC-335 and -336. Form VNC-335 has a Frequency-Of-Exposure Table which

states that personnel who are regularly assigned to work in " Radioactive ,

Material Areas". on a daily basis should be counted four times per year.

The inspector reviewed the bioassay records for the three individuals who

routinely work at the' NTR and enter a radioactive material area almost daily,

e The form of bioassay routinely used by the licensee for personnel working at

Ethe NTR is a whole body count (WBC). It was noted that,in 1996, two of

these individuals only received one WBC each, in 1997, all three individuals

only received two WBC each.

The licensee' was informed that failure to perform a whole body count four

times per year for individuals who are regulary assigned to work in radioactive

material areas on a daily basis was another example of an apparent violation of

. - TS 6.3 (VIO 50-73/98-201-01).

c. Conclusions .

One apparent violation was noted for failure to complete monthly surveys within the

six week time frame prescribed by TS. Postings met regulatory requirements except

for one instance of failure to post a radiation area. Personnel dosimetry was being

worn as required and doses were within the licensee's procedural action levels and

the NRC's regulatory limits.- Radiation monitoring equipment was being maintained

and calibrated as required. The Radiation Protection Program and the ALARA

Pr'ogram' satisfied regulatory requi ements. One apparent violation was noted for

failure to post a radiation' area. Another apparent violation was noted for f ailure to

provide whole body counts for individuals assigned to work in radioactive material

areas four times per year as required by procedure.

' 5. Effluent and Environmental Monitoring (69001)

a. 'Insnection Scone

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The inspector reviewed the following to verify compliance with the requirements of

10 CFR Part 20 and TS Sections 4.4 and 6.5.1.e:

• the licensee's environmental monitoring program,

-. annual VNC effluent monitoring and environmental surveillance program

reports, and

+ counting and analysis records.

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'; b Observation and Findinos

The inspector determined that gaseous releases continued to be monitored as

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, w required, were adequately documented, and were well within the annual dose

constraint of 10 CFR 20.1101 (d),' Appendix B concentrations, and TS limits. There

x 2 were no liquid releases of radioactivity in water or to the ground water greater than

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those limits specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

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' Effluent monitoring satisfied license and regulatory requirements and releases were

_ - within the specified regulatory and TS limits.

8. Transportation (86740)~ ,

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l3. ' InsDection Scone -

, ;The inspector interviewed licensee personnel and reviewed.various records to verify l

. compliance with procedural requirements for transferring licensed material. y

b. . Observations and Findinas -

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iThrough records reviews and discussions with licensee personnel, the inspector

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' determined that the licensee continued to transfer solid waste to the 102

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. Radioactive Materials Laboratory (RML) for shipment and/or disposal. The transfers

were documented on Nuclear Energy Operation (NEO) Form 706 and appeared to be

in compliance with procedure.

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c.. Conclusions

' Radioactive meterial was transferred from the NTR to the 102 Radioactive Materials I

Laboratory (from'the reactor license to the materials license) for shipment and/or - I

disposal according to procedure, j

7.1 Physical Security (81401i81402, 81431) :

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Insnection Scone

To verify compliance with the licensee's NRC-approved Physical Security Plan (PSP) {

and to' assure that changes, if any, to the plan had not reduced its overall  !

effectiveness, the inspector reviewed: j

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. logs, records, and reports,-

.. = the security' organization,

• - key control, . . .

<r . intruder detection and physical barriers,

• access controls, and

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• procedures,

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ic ~ "b2 f0hmarvatinns and Findinas'.

[(1) Emergency Generator Testing:

. The licensee's' Physical Security Plan (PSP), Section 11.2 requires that the

e . emergency generator be tested semi annually to demonstrate that, upon loss of

site power, it starts automatically and the Closed Circuit Television (CCTV) and

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1 The inspector checloed the records documenting the testing of the emergency

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generator. :lt was noted that, prior to 1998, the test was only performed

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annually. The last time the emergency generator had been tested was on.

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. November '4,1997. LThe' licensee stated that the procedure for conducting the

- test was being revised to require a semi-annual test.

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The licensee was informed that failure to conduct semi-annual operability tests

'of the emergency generator was an apparent violation of the Physical Security

Plan (VIO 50-73/98 201-03). ,

'(2): Test of the High Level Conference Circuit (HICON)

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Section 12.3 of the PSP requires that the HICON be tested on the first

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Wednesday of each month.

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The inspector reviewed the records documenting the testing of the HICON. It

was noted that, during 1997, there was no documentation of a test being

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completed in October, and the test in December was not completed on the first

Wednesday of the month. in'1998, testing of the HICON was not completed

on the first Wednesday of the month in either January or February.

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The licensee was informed that failure to conduct a test of the High Level '

Conference Circuit on the first Wednesday of the month was another example

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of an apparent violation of the Physical Security Plan (VIO 50-73/98 201-03).

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(3); Off Site Emergency Agencies Call List Quarterly Calls

' Section.12.4 of the PSP requires that a quarterly call be made from en Off Site

Emergency Agencies Call List on the first Thursday of March, June, September,

and December using the site or automatic dial telephone.

The inspector reviewed the records documenting the quarterly calls made from

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an Off-Site Emergency Agencies Call List. It was noted that the calls had been

made in 1997 but had not been made on the first Thursday of March, June,

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September,'_and December as required.

The licensee was informed that failure to complete a call from the Off-Site

g Emergency Agencies Call List on the first Thursday of the month of March,.

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June, September, and December was another example of an apparent violation

of the Phys'ical Security Plan (VIO 50-73/98-201-03).

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2 The inspector' determined that the other ' aspects of the licensee's physical protection

. program conformed to NRC requirements and to the licensee's implementing

procedures.

c. Conclusion

Three examples of failure to comply with the Physical Security Plan were noted.

Other aspects of the NRC-approved security program at the facility were being

acceptably carried out.

8. M'aterial Control and Accounting (85102)

a. Insoection Scone

To verify compliance with 10 CFR 70, the inspector reviewed:

. storage areas,

e procedures for tracking the quantity, identity, and location of Special Nuclear I

Material (SNM),

e assignment of responsibilities -

. annual inventory results, and

. associated records and reports.

b.' Observations and Findinos

' The design of item control areas ensured that physical and administrative control of

.SNM would be maintained. Licensee procedures for tracking SNM were acceptably

carried out. Records showed that physicalinventories were conducted at least

1 annually as required by 10 CFR 70.51(d).

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Nuclear Material Transaction Reports (DOE /NRC Form 741) and Material Status

Reports (DOE /NRC Form 742) had besa submitted by the licensee as required by

10 CFR 74.13(1).-

Exhibit I (attached to this report) summarizes the licensee's uranium materia' i

balances from October 1,1995, through September 30,1997.

'c.' Conclusion'

. No deficiencies were identified in the licensee's Material Control and Accounting

program.

l. , 9. Follow-up on Previous Open items (92701)

a. 21nsoection Scone

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The inspector reviewed the actions taken by the licensee following identification of

i" previously noted Inspector Follow-up Items (IFI).

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b.- ~ Observations and Findinas '

(1) - IFl - 50-73/93-02-01 - Automated Key Control Reccrds

In June 1993, it was noted that there were some inconsistencies in the records

with regard to the combination changes for the lock controlling access to the

NTR controlled area. During that inspection, the licensee indicated that they

were anticipating placing their issue and change records for keys, locks, and

combinations into an automated data processing system.

During an inspection in March 1996 and again during this inspection, the

licensee's system for tracking keys, locks, and combinations was reviewed it

was determined that the licensee had installed the ~BEST Key / Core Control

System" on the security computer. Security personnel were trained and

proficient in its use. The database for the entire site lock system had been

entered into the security computer and was up-to-date. This IFl is considered

closed.

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(2) IFl - 50-73/96-01-01 - Evaluate Neutron Survey instrument Calibration l

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While reviewing the calibration of instruments in March 1996, an NRC. l

inspector noted that the licensee was using a pulse generator to calibrate their

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neutron survey instruments. The inspector questioned the use of a pulse

generator instead of a certified radioactive neutron source with neutron

energies typical of those measured during the radiation surveys conducted -

during power operation of the NTR facility as recommended in ANSI N323- )

1978.

During this inspection, the inspector reviewed this issue and verified that the

licensee now sends the neutron survey instrument used at the NTR off site to

be calibrated. The vendor uses a certified Californium-252 source to calibrate i

the instrument. The instrument was last calibrated on July 8,1997. The

procedure appeared to be acceptable and this IFl is considered closed.  ;

(3) IFl - 50-183/93-01-01 - Revi.'w of Licensee's Evaluation of Flooding in the

Containment Building

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In 1993, approximately 50,000 gallons of water were discovered in the lower

level of the EVESR containment building. The NRC initiated a specialinspection

to review the circumstances of the event and the licensee's actions in response

to the problem. An IFl was established to follow-up on the licensee's final

review of the event and review the corrective actions taken to prevent

. recurrence.

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During an inspection in March 1996 and again during this inspection, it was

noted that the water was apparently ground water that had entered the

containment building via a deteriorated piping sleeve expansion bellows located

in a valve pit adjacent to the building. The slightly contaminated water was

pumped out of the containment building and processed through the site liquid

waste evaporator. Repairs and preventive corrective actions were scheduled

' for 1994.' The inspector reviewed the 1994 through 1997 annual reports for

L the facility and noted that repairs and corrective actions had been taken in

1994. The licenses currently enters the containment building annually to

perform a radiation survey, take air samples, and conduct a general check of

the conditions throughout the facility, The results reported in the annual

reports indicate that the conditions have remained unchanged to the present.

This item is considered closed.

c.' Conclusions 1

Acceptable actions were taken by the licensee regarding the three IFis noted above

and these issues are considered closed.

10. Review of the Status of Other Reactors at VNC (40755)

a. Insoection Scone

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The inspector reviewed the following to ensure that the requirements of the '

applicable TS were being met for the GETR and EVESR facilities:

. annual reports,

. Regulatory Compliance Reviews of the facilities, and

. Annualinspection Checklists for each facility.

b. Observations and Findinos

The inspector verified that the GETR and EVESR are being maintained in a

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deactivated status in accordance with the appropriate licenses. No major preventive

or corrective maintenance activities having safety significance were performed.

Annual entries have been made into the buildings to perform routine radiation

i. surveys and to check the areas to ensure that the conditions remain unchanged in

the f acilities. All reactor fuel has been removed from the reactors and shipped off

site. The GETR and EVESR facilities are be!ng maintained in a safe shutdown

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condition.

c. Conclusions

The GETR and EVESR facilities are being maintained in accordance with the

applicable TS requirements and in a safe shutdown condition.

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11. Exit interview .

The inspection scope and results were summarized on February 13,1998, with

members of licensee management. The inspector described the areas inspected and

discussed in detail the inspection findings.

No dissenting comments were received from the licensee. The licensee did not identify

as proprietary any of the material provided to or reviewed by the inspector.

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PARTIAL LIST OF PERSONS CONTACTED ,

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Licensee

C. Bassett, Manager, Regulatory Compliance

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W. Kreutel, Senior Reactor Operator

B. Murray, Senior Licensing Engineer

M. Rogers, Specialist, Radiation Mor.itoring i

D. Smith, Manager, NTR i

R. Snyder, Senior Reactor Operator l

G. Stimmell, Manager, V&MO

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H. Stuart, Specialist, Radiological Engineering

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INSPECTION PROCEDURES USED

IP 69001 Class 11 Non Power Reactors

IP 81401: Plans, Procedures, and Reviews

IP 81402: Reports of Safeguards Events l

IF' 81431: Fixed Site Physical Protection of Special Nuclear Material of Low Strategic j

Significance ]

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IP 85102: Matarial Control and Accounting - Reactors i

IP_86740: Inspection of Transportation Activities )

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ITEMS OPENED. CLOSED. AND DISCUSSED i

Onened )

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50 73/98 201-01 VIO Failure to comply with TS 6.3 by: 1) failure to complete j

monthly radiological surveys within a period of time not

exceeding six weeks as required and 2) failure to perform a

whole body count four times per year as required by j

procedure for individuals who are regulary assigned to work '

in radioactive material areas around the NTR on a daily  :

basis. I

50-73/98-201-02 VIO Failure to post an area outside the South Cell of the NTR in

which radiation levels could result in an individual receiving

5 mr in one hour with a Caution, Radiation Area" sign.

50-73/98-201-03 VIO Failure to comply with requirements of the PSP for:

1) conducting semi annual operability tests of the ,

emergency generator prior to 1998,2) conducting calls  !

from the Off Site Emergency Agencies Call List on the first i

Thursday of the month of March, June, Septebmer, and i

December of 1997, and 3) conducting a test of the High-

Level Conference Circuit on the first Wednesday of the

l' month in October of 1997 and in January and February of

l- 1998.

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50-73/93-02-01- ;IFl Automated Key Control Records

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'50-73/96-01-01 IFl Evaluate Neutron Survey instrument Calibration

.50 183/93-01-01. IFl- Review of Licensee's Evaluation of Flooding in the

Containment Building

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LIST OF ACRONYMS USED

' ALARA'.

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. As low as reasonably achievable -

CA Change Authorization

.: CCTV : Closed circe:t television -

tCFR: . Code of Federal Regulations

,EVESR~ = ESADA Vallecitos Experimental Superheat Reactor.

GETR. General Electric Test Reactor-

HICON High Level Conference Circuit

HP. Health physics .

'iP . Inspection Procedure

J kW- Kilowatt =

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NEOL . Nuclear Energy Operation-

LNCV. - Non-Cited Violation

.NRC . Nuclear Regulatory Commission

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NRP - Nuclear Reactor Program

. NSIC Nuclear Safety.information Center

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.NVLAP. . National Voluntary Laboratory Accreditation Program

(PC: - Frocedure change

'PDR Public Document Room

. PSP. Physical Security Plan

RHP. Reactor Health Physicist

RM . ' Radiation Monitoring.

. RML; Radioactive Materials Laborrtory

RPC- ' Radiation Protection Committee

Radiation Protection Office

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RPO1

RSAC. ' Reactor Safety and Auditing Committee

RWP- Radiation Work Permit -

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SNM -Special Nuclear Material ..

ESOP . Standard Operating Procedure

SRO; Senior Reactor Operator .

tTS. Technical Specification ,

V&MO~ Vallecitos and Morris Operations

b . _ :VNC Vallecitos Nuclear Center .

VTSC. .Vallecitos Technological Safety Council

'A WBC . . - Whole Body Count

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EXHlBIT I

GENERAL ELECTRIC COMPANY

VALLECITOS NUCLEAR CENTER

NUCLEAR TEST REACTOR '

Docket No. 50-73 License No. R-33

Material Balance for Period: October 1.1995 - Santamber 30.1997

Reporting Identification Symlhol: YJB Report Units: Grams

Hioh Enriched Uranium

Element Isotone

- Beginning inventory: 3,878' 3,577

(October 1,1995)

Receipts: +1- +1

(Received from Lockheed '

Martin Oakridge (FZG])

Total Receipts: +1 +1'

Material to Account for: 3.879 3.578

Removals:

Shipments: -1 -1

(Shipped to KKM in

. Switzerland [RZAU-1])

Fission / transmutation: -4 -5

Total Removals: -5 -6

Ending Inventory: -

(September 30,1997) 1824 3.572

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