ML20054C765

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IE Insp Rept 50-047/76-02 on 760826-27.No Noncompliance Noted.Major Areas Inspected:Licensee Action on Previously Identified Items of Noncompliance,Cathodic Protection Sys & Logs & Records
ML20054C765
Person / Time
Site: 05000047
Issue date: 09/10/1976
From: Norrholm L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17298A033 List: ... further results
References
FOIA-81-311, FOIA-Z81-311 50-047-76-02, 50-47-76-2, NUDOCS 8204210619
Download: ML20054C765 (7)


See also: IR 05000047/1976002

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IE:I Form 12

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(Jan 75) (Rev)

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U. S. NUCLEAR REGUL\\ TORY CC:CIISSION

OFFICE OF INS?ECTION AND ENFORCDIENT

REGION I

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IE Inspection Report No:

50-47/76-02

Docket No:

50-47

Lic ensee:

U. S. Army Materials and Mechanics Research Center

License No:

R-65

Watertown Arsenal

Priority:

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Watertown, Massachusetts 02172

Category:

G

Safeguards

Group:

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Loca tion:

Watertown, Massachusetts

Research Reactor (?ossess Only)

Type of Licensee:

,

Routine, Unannounced

Type of Inspection:

Dates of Inspection:

August 26-27, 1976

Nofember 25,1975 (Operations)

Dates of Previous Inspection:

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Reporting Inspector:

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DAT"r

L./Norrhol=, Reactor Inspector

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Acco panying Inspectors:

emre

DATE

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DATE

DATE

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Other Accompanying Personnel:

NONE

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Reviewed By:

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D. L. Caphtoit, Chief, Reactor Projects Section No. 2,

'DATE

Reactor Operations and Nuclear Support Branch

8204210619 911005

PDR FOIA

KADAT-Z81-311

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SUMMARY OF FINDLNGS

Enforcement Action

None.

Licensee Action on Previousiv Identified Items of Noncompliance

The following Itens of Nonconpliance were identified in NRC:I Inspection

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Report 50-47/75-01 dated December 12, 1975. By response letter dated

January 22, 1976, the licensee outlined corrective action for these

items.

A.

Infraction relating to failure of Reactor Safeguards Cennittee to

conduct periodic audits.

The inspector had no further questions on

this ites.

(Detail, 2b)

B.

Deficiency relating to failure to conduct visual surveillance

inspections. The inspector had no further questions on this item.

(Detail, Sa)

C.

Deficiency _ relating to failure to post docunents required by 10 CFR 19.11.

The inspector had no further questions on this item.

(Detail, 6c).

Desien Changes

None.

Unusual Occurrences

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None.

Other Significant Findings

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A.

Current Findings

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Acceptable Items

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(These are matters not involving an item of noncompliance or

an unresolved ites.)

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a.

Administration and Organization (Detail, 2)

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b.

Operations (Detail, 3)

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c.

Containment (Detail, 4)

d.

Surveillance Tests-General (Details, Sa, b, c)

Radiation Protection (Detail, 6)

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2.

Unresolved Items

(An unresolved item is a matter about which more information

is required in order to ascertain whether it is an acceptable

item or an item of noncompliance.)

Records to demonstrate that semi-annual checks of the fire

alarm system had been satisfactorily performed were not

available.

(Detail, 5d)

B.

Status of Previous Unresolved Items

None.

Management Interview

An exit interview was conducted on August 27, 1976, at Watertown Arsenal

with the following persons in attendance:

Mr. J. J. O'Connor, Reactor Facility Supervisor

Mr. L. J. Norrhcim, Reactor Inspector, USNRC

Items Discussed

A.

Purpose of Inspection

The inspector outlined the scope of the routine unannounced in-

spection as a review of activities under the " possess only" license,

including inspections, surveillance and health physics practices.

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B.

Other Items

The following specific items were discussed:

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1.

Previous Items of Noncompliance.

(Details, 2b, Sa, 6c)

2.

Unresolved item relative to periodic testing of fire alarms.

(Detail, 5d)

3.

Cathodic protection system surveillance.

(Detail, 4)

4.

Record Keeping.

(Detail, 4b)

5.

Independent survey results.

(Detail, 6a)

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DETAILS

1.

Persons Contacted

Mr. J. J. O'Connor, Chief, Technology Planning and Exploitation

Division and Reactor Facility Supervisor

Mr. S. Levin, Chief, Radiation and Occupational Safety 3 ranch

Mr. A. J. Colacey, Chief, Facilities Engineering 3 ranch

Mr. A. Kalinaukas, Captain, Security Section

Mr. G. Flanders, Electrical Engineering Technician

2.

Administration and Orzanization

a.

No change in the facility organi:ation has been =ade in either

structure or personnel since the previous inspection.

b.

The Reactor Safeguards Committee =e=bership is as described in

the previous inspection report.

The same report * identified,

as an item of noncompliance, the failure of the Coc=1ttee to

conduct periodic audits as required by Technical Specifications.

The inspector reviewed the minutes of a Reactor Safeguards

Committee =eeting held on April 1,1976, which included all

members.

During this =eeting, a tour of the facilic'; was

conducted which precipitated several recommendations relative

to safety and integrity of the facility.

In addition, a

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schedule was established to hold meetings semi-annually,

following periodic radiation surveys.

The inspector had no further questions in this area at this

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time.

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  • NRC:I Inspection Report 50-47/75-01 dated Dece=ber 12, 1975.

3.

Operations

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Logs and Records

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To review the conduct of operations since the previous in-

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spection, the inspector examined, on a sa=pling basis, the

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following licensee records covering the periods indicated:

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(1) Record of Access to Reactor Facility

11/25/75

-8/26/76

(2) Cathodic Protection Surveillance Record 10/23/75 - 6/4/76

(3) Reactor Safeguards Ccamittee Minutes

- 4/1/76

(4) Fire Prevention Inspection Reports

1/1/75 - 7/31/76

(5) Weekly Reactor ?. M. Inspection Reports 1/15/76 - 7/28/76

(6) Reactor Facility Radiation and

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Contamination Surveys

1976 - (Selected)

(7) Liquid Release Records

- 6/28/76

b.

The facility remains in a shutdown " standby" status.

Contain-

cent entries are =ade only for periodic surveillance and

inspections. No other use has been sade of the facility.

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No changes to this status are anticipated.

4.

Containment

Technical Specification 4.b requires that voltage and current

a.

readings of the cathodic protection system be obtained quarter-

ly and that the effectiveness of the system be checked semi- '

annually using a half-cell.

The above checks are made by the Arsenal Facility Engineering

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3 ranch.

The inspector reviewed the results of checks made on the

following dates:

10/23/75

SATISFACTORY

12/22/75

SATISFACTORY

2/10/76

GROUND FROZEN

4/6/76

SATISFACTORY

6/4/76

SATISFACTORY

The inspector had no further questions in this area at this

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time.

b.

Records of the above tests are retained by the Facility Engineer-

ing Branch.

A licensee representative acknowledged the inspector's

suggestion that a report or duplicate record be provided to

the Reactor Supervisor to assure a check of compliance with

Technical Specifications.

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5.

Surveillance Tests

Technical Specification 4.a. (1) requires a weekly visual

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inspection of the heating and ventilation systems. The

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inspector reviewed the Intelligence and Security Branch (ISB)

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records of access to the reactor facility in order to verify

that individuals with responsibility in this area made entries

to the facility at least weekly.

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A previous inspection * identified failures to perform the

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above weekly inspections. No subsequent failures were identi-

fied.

The inspector had no further questions in this area,

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b.

Technical Specification 4.a. (2) requires a monthly check of

all heating and ventilation equipment in accordance with a

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written checklist.

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The inspector's review of checklists identified no problems in

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this area.

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Technical Specification 4.c requires a check of fire fighting

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equipment be performed at least monthly.

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These checks are conducted by the Post Fire F.arshal who

completes a Fire Prevention Inspection Report.

The inspector reviewed the reports and conducted a tour of the

facility to verify fire protection / prevention adequacy.

The inspector had no questions in this area at this time.

d.

Technical Specification 4.d requires that the fire alarm

system be operability checked semi-annually.

These checks are performed by a sub-contractor. Due to the

absence of the Post Fire Marshal at the time of this inspection,

records of fire alarm checks were not available for review.

The inspector's review of the IS3 access records indicated

that entries to the facility to check fire alarm operability

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had been made.

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  • NRC:I Inspection Report 50-47/75-01 dated Dece=ber 12, 1975.

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This item is unresolved (76-02-01) pending review of licensee

records of fire alarm checks.

6.

Radiation Protection

a.

Technical Specification 3.a requires that a facility radiation

survey, including smears, be performed at least quarterly.

The inspector reviewed records of surveys conducted on Feb-

ruary 21, April 3, and July 24, 1976.

Licensee results of the July 24, 1976 survey indicated the

following:

Airborne. activity

Less than MDA

Removable Contamination

Less than 21 pei/100 cm,'

General Area

.01 .02 mrem /hr

Pool Top

2 mrem /hr

Core level, in pool

3.8 Rem /hr

The inspector conducted an independent survey using a cali-

brat ~ed NRC instrument (Eber11ne E-120, serial 3173), which

corroborated the licensee's results (Contamination, general

area and pool top values were verified).

The inspector had no further questions in this area at this

time.

b.

The licensee has made one recent liquid release from the

facility hold tank.

The fluid is attributable to condensation

collected inside the containment.

The release was made on June 28, 1976, and consisted of

8645.2 gallons of water with the following activity:

Beta

3.92 X 10-7 sci /mi

Total release:

12.8 mei

Alpha

3.6 X 10-8mei/mi

Total release:

1.13 mei

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The inspector had no further questions in this area at this

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time.

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The previous inspection * identified a failure to post docu-

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ments required by 10 CFR 19.11.

The inspector's review of corrective action identified no

further questions in this area.

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To preclude physical loss of these items or loss of appli-

cability by revision, the licensee indicated that a notice

would be posted directing interested individuals to the

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location of current copies of the documents.

  • NRC:I Inspection Report 50-47/75-01 dated December 12, 1975.

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