IR 05000264/1977002

Insp Rept 50-264/77-02 on 770719-22,26 & 27.No Noncompliance Noted.Major Areas Inspected:Reactor Startup & Routine Operation

ML20137G933
Person / Time
Site:	Dow Chemical Company, 05000000
Issue date:	08/17/1977
From:	Charles Brown, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20136D183	List: IA-85-256, Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies IA-85-258, Amend 3 Renewing License R-108 & Incorporating Security Plan as License Condition IA-85-261, Documents That Appropriate Corrective Actions Taken by Dow Chemical Co in Response to 780113 Immediate Action Ltr,Per 780207 Enforcement Conference at Facility IR 05000264/1973001 IR 05000264/1975001 IR 05000264/1977002 IR 05000264/1979003 ML20137G383 ML20137G390 ML20137G402 ML20137G410 ML20137G417 ML20137G432 ML20137G437 ML20137G446 ML20137G450 ML20137G460 ML20137G467 ML20137G472 ML20137G478 ML20137G487 ML20137G507 ML20137G524 ML20137G586 ML20137G600 ML20137G614 ML20137G637 ML20137G653 ML20137G750 ML20137G793 ML20137G816 ML20137G854 ML20137G875 ML20137G888 ML20137G896 ML20137G903 ML20137G908 ML20137G916 ML20137G921 ML20137G926 ML20137G931 ML20137G940 ML20137G951 ML20137G972 ML20137G976 ML20137G983 ML20137G990 ML20137G997 ML20137H003 ML20137H022 ... further results
References
FOIA-85-256, FOIA-85-258, FOIA-85-259, FOIA-85-261 50-264-77-02, 50-264-77-2, NUDOCS 8508280026
Download: ML20137G933 (3)

Text

{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ ,

,o ,

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-264/77-02-Docket No.' 50-264 License No. R-108 Licensee: Dow Chemical U. Building Midland, MI 48640 Facility Name: TRIGA Reactor Inspection At: TRIGA Site, Midland, MI Inspection Conducted: July 19-22, 26, and 27, 1977

   /   '
   / /

sW C Inspector: . rown ,3 / Y f-

   ,g Approved by: W. S. dittle, Chief
    /
     '
     [/7/ [[
     '

Nuclear Support Section Inspection Summary Inspection on July 19-22, 26, and 27,1977 (Report No. 50-264/77-02) Areas Inspected: Routine, unannounced inspection to review records, surveillance, procedures, operations, maintenance. Reactor startup and routine operation were observed. The inspection involved 24 inspector-hours onsite by one NRC inspecto Results: No items of noncompliance were found in the areas inspecte " 8508280026 850712 PDR FOIA KOHN85-256 PDR f

,
*

.. DETAILS 1. Persons Contacted

* V.~Anders, Reactor Supervisor
*G. L. Kochanny, Lab Director A. J. Kamp, Assistant Reactor Supervisor
*T. J. Quinn, Reactor Operator
* denotes persons attending management intervie . Procedures The inspector's review of the facility's procedures revealed that the requirements of the Technical Specifications for written pro-cedures were being met.. Two procedures, Administrative Control and Reactor Startup, were reviewed by the inspector without commen All the procedures had been reviewed and approved by the Reactor Operations Committe No items of noncompliance or deviations were identifie . Requalification Training The performance of the requalification training program and the results of each operator's test and evaluation was reviewe The program documentation indicates that the program has satisfactorily been maintained up-to-date. The operators completed written and orals satisfactorily. The licensee presently performed the program of the requalification training in January and February each yea No items of noncompliance or deviations were identifie . Surveillance The records of surveillance performed at the facility were reviewed. No discrepancies were noted as compared to proce-dural requirements. The post-maintenance surveillance (no major maintenance) was the normal pre-startup surveillance which verifies that the Technical Specifications for minimum instrumentation and functional interlocks are me The inspector commented on the 5 to 10 cent variations in core reactivity that shows up when the fuel elements are inspecte The licensee stated that maintaining the core approximately 50 cent less than maximum allowable excess reactivity and with the variation remaining consistantly small, no further review was being considered at this tim No items of noncompliance or deviations were identifie . -2-

.-
,
.' *

5. Experiments and Irradiations The irradiation forms completed during the past two years were reviewed on a random selection basis. Only one type was performed during this period - a small sample activation was noted. No discrepancies were indicated with record comparison to the proce-dural requirement. The number of irradiations performed remained approximately the same as noted in previous inspection period The pneumatic " rabbit" remained on a once-a-month or less frequency of us No items of noncompliance or deviations were identifie . Logs and Records The licensee's logs and records were found to meet the license and Technical Specification requirements. Only minor errors in log keeping practices were noted and pointed out to the license No items of noncompliance or deviations were identifie . Internal Review The inspector's review of the minutes of the Reactor Operations Committee indicated that the meetings were held as required and with a quorum. The internal audits appeared to be performing their control functions. The Committee reviewed these report The Committee also reviewed the event of the key in the unattended reactor consol No items of noncompliance or deviations were identifie . Reactor Operating Personnel The licensee had five new operators qualify during this inspection period. At 'the time of the inspection, eight persons had completed the requalification program.

t-9. Management Interview The inspector met with the licensee representatives (denoted in t paragraph 1) at the conclusion of the inspection on July 27, 197 The licensee acknowledged the inspectors' comments on record keeping. The licensee confirmed that the present opinion is that no further review and evaluation is needed at this time on the 5 to 10 cent variations in reactivity that are noted from random fuel rotatio . . -_ - ._ - . . -- -- _ .- -. . -- - _ . _ >

 >

 .

I

 - .

j . . , i

       -

i AUG 2 51977' , ,

.

'

 ~

Docket No. 50-264 - 7 ~ '- ! Dow Chemical U. I, , ATIN: Dr. L 1. Langner

'

Radiation Safety Committee 1803 Building

'

Midland, MI 48640

     ..

' Gentismen: This refers to the inspection conducted by Mr. W. h. Grant of this office on August 9-11, 1977,,.of activities at the Dow Nuclear ' Research Reactor authorised by NRC License No. 1-108 and to tha discussion of our findings with you and Mr. O. Anders at the con- , elusion of the inspectio The enclosed copy of our inspection report identifies areas i essained during the inspection. Within these areas, the inspection consisted of a selective avamination of procedures ,\ and rapresentative records, observations, and interviews with N i personne \s k

     '

No items of acacoupliance with NRC requiremsats were identified during the course of this inspectio In accordarsee with section 2.790 of the NRC's " Rules of Practice,"

'

Part 2, Title 10, Code of Federal Regulations, a copy of this

letter sad the enclosed inspection report will be placed in the NRC's Public Document Room, except as follows. If this report contains information that you or your contractors believe to be proprietary, you must apply in writing to this office, within twenty days of your receipt of this letter, to withhold such information from public disclosure. The application must include a full statement of the reasons for which the information is con-

! ,

sidered proprietary, and should be prepared so that proprietary information identified in the application is contained in an emelosure to the applicatio ;

     ,.

i

    ~

W.?UV200 % '/

 !

orric s > eunma ass > oats > _ NRC FORM 318 (9 76) NRCM 0240 W u. s. sovannusNT rninvine omes een -eas.ea4

- - - - _  -
  . . _ _ . _

       - . . -

0 l l

.

now Chemical U. .- AUG 2 51977 We will gladly discuss any questions you have conceraias this inspectio ,

     ~

Sincerely . l .

      -

i . t

     .

,

     - James M. Allan, Chief

' Fuel Facility and Materials Safety Branch

     *

, Enclosure: IE Inspection Report No. 50-264/77-03 ~ '

     . .
     *

ec w/ encl: Central Files ~ Reproduction Unit NEC 20b , FDR , , MSIC ,. TIC , 9*

     ..   \

, t

;
!

i

,
!

Orrsc= > . _EI . .Inb RIIL RILL . . . .

      ...RIII._g su==aus k . Gr t _bh, Enni ,

All ... m

     
! O..., ... 8./.. 2.. 4..../.. 7.._ ..[ . _ . _

L

'

NRC PORM 310 (9 76) NRCM 0240 * u. e. oovsmausut eneurine orrica. to,e - eae.es4

f; i

.
.
.

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-264/77-03 Docket No. 50-264 License No. R-108 Licensee: Dow Chemical U. Building Midland, MI 48640 Facility Name: TRIGA Inspection at: TRIGA Site, Midland, MI

' Inspection conducted: August 9-11, 1977 Q0, <M Y 77 Inspector: W. B. Grant ,

Approved by: T. H E f ff Ek

    '

Environmental and Special Projects Section Inspection Summary Inspection on August 9-11, 1977 (Report No. 50-264/77-03) Areas Inspected: Emergency Planning, including a review of the Emer-gency Plan and implementing procedures; interviews with licensee personnel; visits to emergency support groups; reviewed training of support groups and results of quarterly evacuation drills. The inspection involved 15 inspector-hours on site by one NRC inspecto Results: No items of noncompliance or deviations were identifie .

. ','
,

DETAILS Persons Contacted

 *0. Anders, Reactor Supervisor
 *R. Langner, Chairman, Radiation Safety Committee T. Quinn,-Reactor Operator K.~ Kelly, Reactor Operator Olson, Senior Radiation Safety Officer Barsten, Industrial Hygienist Heitzig, Fire Chief, Dow Chemical Ducommun, M.D.,. Medical Department, Dow Graham, k.N., Medical Department Westjohn, Chief, Plant Security N.-Olney, Day Captain, Plant Security J. Weed, Plant Protection, Communications
 * denotes.those present at the exit intervie . Emergency Plan and Implementing Procedures     *

The emergency plan adopted by Dow Chemical was updated on April 15, 1977. The plan was submitted to NRR on that date and according to a licensee representative, Dow has been notified by the NRC that-the plan is acceptable. The inspector reviewed the licensee's emergency plan and.it appears to contain the major elements of emergency preparedness discussed in the proposed American National Standard " Emergency Planning for Research Reactors" (draf t No. 4)

 (ANS-15.16, N17.2, dated April 1976). The licensee also has pro-cedures for implementing the emergency plan which are included in the plant's overall emergency plan and the medical department's
 "First Aid for Radiation Victims".

No items of noncompliance were note . Coordination with Support Agencies , r The inspector visited the licensee's Health Physics, plant pro-tection fire and medical departments and discussed the arrange-ments made to provide assistance in the event of an emergenc Discussions with representatives of those departments showed that there was close coordination between them and the reactor staf No items of noncompliance or deviations were noted.

      -2-i
, . -, ., _ - , , , , . . . - . , _ . . - _ . , _ . . , . , , _ . _ , _ - . .. . _ _ _ . _ _ _ . . - - . .~.

-

%
.
. . Facilities and Equipment First aid supplies, radiation survey monitoring equipment, and supplied air respiratory protection equipment were examined for maintenance and operability. All equipment appeared to be main-tained in a ready stat The inspector found that the radiation survey meters in the reactor control room were_ operable and had been calibrated. The reactor room is equipped with a_ continuous air particulate monitor that has audible and visual alarms which are monitored by the reactor operators and also at the Plant Protection Communications Cente No items of noncompliance were note . Medical Arrangements In case of injury, personnel would be transported to the medical department which is approximately half a mile from the reactor facility. According to licensee representatives, transportation to the medical department would be provided by a fire department ambulance.. The inspector visited the medical department and found it contained facilities for decontamination of injured personnel and procedures for retainirg contaminated liquid According to licensee personnel, the medical staff would provide medical assistance to an' injured contaminated person and the health physics staff would provide decontamination assistanc No items of noncompliance or deviations were identifie . Drills and Training The inspector discussed with licensee personnel the quarterly evacuation drill which is conducted in accordance with emergency plan. Records were reviewed and it was noted that the last drill took place on July 1, 1977.- Records indicated that any weaknesses recognized during the drills are followed up and correcte The inspector reviewed documentation procedures and interviewed'

ten employees to verify that training in the emergency plan had been conducted. According to licensee representatives, training sessions are held at least annually and include lectures and l ! r f '.

  -3-

-.
'-
.
,
', ..

discussions in radiation safety, evacuation procedures and the use of self contained respiratory protection equipment. According to licensee representatives, training has been provided for approxi-mately 80 plant protection personnel, 40 firemen, and 20 medical department personne No items of noncompliance or deviations were identifie . Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on August 11, 197 The inspector summarized the purpose and the scope of the inspection and the finding __ }}