ML20137H045

From kanterella
Revision as of 23:51, 30 June 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Informs of Personnel Changes in Reactor Operations Committee.H Gill Replaced by J Macki as Committee Chairman, Norwood Replaced by T Prasons as Health Physicist & P North Replaced by J Simpson as Senior Reactor Operator
ML20137H045
Person / Time
Site: Dow Chemical Company, 05000000
Issue date: 02/22/1980
From: Langner R
DOW CHEMICAL CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20136D183 List: ... further results
References
FOIA-85-256, FOIA-85-258, FOIA-85-259, FOIA-85-261 NUDOCS 8508280099
Download: ML20137H045 (1)
v • d • e


Text

.

DOW CHEMICAL U.S.A. ,

February 22, 1980 2DuND. WCHIGAN 6 US Nuclear Regulatory Comission Operating Reactors Branch #4 .

Division of Operating Reactors Washington, DC 20555

Dear Sirs:

DOCKET No 50-264, LICENSE R-108 This letter is to inform you of recent personnel changes regarding the operation of the Dow TRIGA research reactor, license R-108. Several members of the Reactor Operations Comittee (ROC) have moved to dif-ferent positions and were replaced. Harold Gill has been replaced by Jim Macki as Chairman of the Reactor Operations Comittee. Samuel Norwood has been replaced by Tracy Parsons as Health Physicist and Phil North has been replaced by Joan Simpson as a Senior Reactor Operator.

Sincerely, j'

'th" W Ralph R. Langner, Chairman

,bh Radiation Safety Comittee 1603 Building 517/636 4344 bjd ,

[\

i

. Mx6 5

//O

_ J- W

- 8508200099 850712 PDR FOIA I

  • KOHN05-256 PDR T AN OFtMATING UNIT OF THE DOW CHEMICAL COMPANY 3003080

YILLOP!F2 COPY k

MAY 7 980 Docket No. 50-264 Dow Chemical U.S.A. .

ATTN: Dr. R. R. Langner, Chairman Radiation Safety Committee Building 1603 Midland, Michigan 48640 Gentlemen:

Enclosed is IE Information Notice No. 80-19, "NIOSH Recall of Recirculat-ing-Mode Closed-Circuit) Self-Contained Breathing Apparatus (Rebreather),"

which addresses the NIOSH "stop-sales-and-recall" order to the manufac-turers of the BioPak 60P rebreather respirator. Should you have any questions related to the enclosed authorization or guidance, please con-tact this office.

Sincerely, James G. Keppler s Director

Enclosure:

IE Information Notice No. 80-19 cc w/ enc 1:

Central Files Director, NRR/DPM s Director, NRR/ DOR PDR NSIC TIf RII RIII haan/jp M

Keppler

-5/6/80

~ $$0N So D YQ- ,

SSINS: 6870 Accession No.:

UNITED STATES 9000999999 %k ,

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 -

May 6, 1980 IE Information No. 80-19 NIOSH RECALL OF RECIRCULATING-MODE (CLOSED CIRCUIT) SELF-CONTAINED BREATHING APPARA1U5 (REBREATHER)

The NRC has been informed by the National Institute for Occupational Safety and Health (NIOSH), the agency that tests and certifies respirators, that some of the NIOSH-certified respiratory protective equipment that NRC licensees use might have been modified by the manufacturer without approval by NIOSH. NIOSH considers such modified equipment not to be certified, even though it might bear their test and certifification label.

The equipment in question is the BioPak 30P and 60P, NIOSH test-and-certifica-tion numbers TC-13f-84 and TC-13F-85, respectively. The BioPak 30P and 60P are respectively 30-minute and 60-minute, closed-circuit, recirculating-mode, self-contained breathing apparatuses (rebreathers), manufactured by BioMarine Industries, Inc. Our information leads us to believe that NRC licensees have purchased only the 60P equipment.

NIOSH has issued a "stop-sales-and-recall" order to the manufacturer for this equipment. Licensees who have such equipment should che.ck with the manufacturer to determine what action to take to assure that their equipment is in certified status.

The manufacturer's address and telephone number are:

BioMarine Industries Inc.

45 Great Valley Corporate Center Malvern, PA 19355 Tel: (215) 647-7200

-fes248g7f-227 g

N IE Information Notice No. 80-19 Enclosure May 6, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No. Issued 80-18 Possible Weapons Smuggling 5/5/80 All power reactor Pouch facilities with an OL, fuel fabrication and processing facilities and Materials Priority I licensees (processors and distributors) 80-17 Potential Hazards Associated 5/5/80 All radiography With Interchangable Parts Licenses On Radiographic Equipment 80-16 Shaft Seal Packing 4/29/80 All power reactor Causes Binding In Main facilities in your Steam Swing Check And Region with an OL or CP Isolation Valves 80-15 Axial (Longitudinal) 4/21/80 All Light Water Reactor Oriented Cracking In Facilities holding power Piping reactor OLs or cps 80-14 Safety Suggestions From 4/2/80 All power reactor Employees facilities with an OL or CP 80-13 General Electric Type SBM 4/2/80 All light water reactor Control Switches - Defective facilities holding power Cam Followers reactor OLs or cps 80-12 Instrument Failure Causes 3/31/80 All holders of power Opening of PORV and Block reactor OLs and cps Valve 80-11 General Problems with ASCO 3/14/80 All holders of Reactor Valves in Nuclear Application OL, CP, fuel fabrica-Including Fire Protection tion and processing Systems facilities 80-10 Partial Loss of Non-Nuclear 3/7/80 All power reactor Instrument System Power facilities holding Supply During Operation OLs and cps 80-09 Possible Occupational 3/7/80 All holders of Health Hazard Associated power reactor OLs with Closed Cooling Systems and near term cps

.8. Pe"w We FJUN 2 4 $80 Docket Nc.59-264 Dow Chemical U.S.A.

ATTN: Dr. R. R. Langner Radiation Safety Committee 1603 Building Midland, MI 48640 Gentlemen:

The enclosed IE Circular No. 80-14 is forwarded to you for information.

If there are any questions related to your understanding of the suggested actions, please contact this office.

Sincerely, James G. Keppler Director

Enclosure:

IE Circular No. 80-14 cc w/ encl:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR NSIC.

TIC

~

RIII pNRII hman/np 6/24/80 spier sAs4>% rd

,vw u s tvw 1 ff.

SSINS.: 6830

" UNITED STATES Accession No.:

SGEESM&Me NUCLEAR REGULATORY COMMISSION @ns OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 June 24, 1980 IE Circular No. 80-14 RADI0 ACTIVE CONTAMINATION OF PLANT DEMINERALIZED WATER SYSTEM AND RESULTANT INTERNAL CONTAMINATION OF PERSONNEL This circular describes an event which occurred at a nuclear power facility; however, the generic implications may be applicable to research reactors, and fuel cycle facilities.

On March 17, 1980, a licensee informed the NRC resident inspector that portions of the plant demineralized water (DW) system were found to be radioactively contaminated. A temporary hose used to add demineralized water to the spent fuel pool was the pathway for the cross-contamination. After this fuel pool makeup was completed on March 14, the temporary DW line (still connected to the DW header) was inadvertently left submerged in the fuel pool. Since the DW header pressure at the point of supply was relatively low (a DW booster pump had been secured), a siphoning action occurred, resulting in radioactive contamination of portions of the DW header.

On March 17, 1980, while performing routine secondary system chemical analyses, thelicenseediscoveredthatthedcaineralizedwatertapin_ghechemistrylab contained high levels of boron and had activity of 1.5 x 10 uCi/ml (mainly Cs-134, Cs-137, Co-58, Co-60 and Mn-54). It was subsequently discovered that demineralized water from the chemistry laboratory supply tap had been used to make five (5) pots of coffee. The remaining coffee was confiscated and the twenty-three (23) individuals who had consumed this coffee were whole-body counted. All involved individuals showed no intake greater than an equivalent 0.01 MPC-HRS. Analysis performed by the licensee's radiation consultant, based on the maximum concentration of radioactivity found in the coffee, indicated that the resultant 50 year dose commitment to an individual drinking eight ounces of this coffee would be less than 1 millirem.

Further licensee investigation revealed that the non-radiological chemistry DW l

f supply tap was the only DW supply point outside the Auxiliary Building l controlled area. This DW supply tap was tagged prohibiting human consumption j to prevent a similar event in the future.

It is recommended that you review your facilities use of demineralized water (DW) via temporary connections and give attention to the following:

1. Provisions should be made to assure that radioactive materials are not i inadvertently introduced into your facility's DW system via the improper use of temporary connections. A temporary cross connection between contaminated systems and the DW system without adequate physical controls to prevent cross-contamination should be prohibited.

l ObhN 3 .-

IE Circular No. 80-14 June 24, 1980 Page 2 of 2

2. In addition to some physical means of prever, ting backflow into the DW system, appropriate administrative controls should be established to ensure that the DW supply valve is secured and temporary hosing is disconnected from the DW supply header after use.
3. Use of plant-supplied DW for human consumption should be prohibited.

The potable water system should be the only authorized source of water for human consumption.

4. Examine potable and demineralized water systems to determine if pathways exist allowing or having the potential to allow contamination of these systems including temporary connections whereby siphons could cause situations described above.

No written response to this Circular is required. Your review of this matter to determine its applicability to your facility and any corrective and preven-tive actions taken or planned, as appropriate, will be reviewed during a subsequent NRC inspection. If you desire additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.

IE Circular No. 80-14 Enclosure June 24, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date of Issued to No. Issue 80-13 Grid Strap Damage in 5/18/80 All holders of Reactor Westinghouse Fuel Assemblies OLs and cps 80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of Reactor May Fall Out of Place When OLs and cps Mounted Below Horizontal Axis 80-11 Emergency Diesel Generator 5/13/80 All holders of a power Lube Oil Cooler Failures reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of Reactor Environmental Qualification OLs and cps of Equipment 80-09 Problems With Plant Internal 4/28/80 All holders of a power Communications Systems reactor OL or CP 80-08 BWR Technical Specification 4/18/80 All General Electric Inconsistency - RPS Response BWR's holding a power Time reactor OL 80-07 Problems with HPCI Turbine 4/3/80 All holders of a power Oil System reactor OL or CP 80-06 Control and Accountability 4/14/80 Medical licensees in Systems for Implant Therapy Categories G and G1 Sources 80-05 Emergency Diesel-Generator 4/1/80 All holders of a power Lubricating Oil Addition and reactor OL or CP Onsite Supply 80-04 Securing of Threaded Locking 3/14/80 All holders of a power Devices on Safety-Related reactor OL or CP Equipment 80-03 Protection from Toxic Gas 3/6/80 All holders of a Hazards power reactor OL 80-02 Nuclear Power Plant Staff 2/1/80 All holders of Reactor Work Hours OLs, including research and test reactors, and cps

E f 'o,,

o UNITED STATES NUCLEAR REGULATORY COMMISSION l

i y .E REGION lli 1 0 # 799 ROOSEVELT ROAD o GLEN ELLYN, ILLINOIS 60137 February 9, 1981 Gentlemen:

The enclosed IE Circular No. 81-02 is forwarded for your information.

A copy of this circular is also being mailed directly to each licensed reactor operator and senior reactor operator. No written response is required. If there are any questions related to your understanding of the recommended actions, please contact this office.

Sincerely,

  • SY James G. Keppler Director

Enclosure:

IE Circular No. 81-02

.) fo .

MLo z2800N ' '

W' - - - - -

e 1

Docket No. 50-264 hI-C@

Dow Chemical U.S.A. , .

ATTN: Dr. L. W. Rampy, Chairman ,

Radiation Safety Committee 1803 Building Midland, MI 48640 cc w/ encl: -

Dr. 0. V. Anders Reactor Supervisor Mr. J. M. Macki, Chairman TRIGA Reactor Operations Committee Central Files AD/ Licensing AD/ Operating Reactors PDR ,

NSIC TIC 4

7

SSINS No.: 6830 Accession No.:

IEC 81-02 8809ff9f9F" h{

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT i WASHINGTON, D.C. 20555 February 9, 1981 IE Circular No. 81-02: PERFORMANCE OF NRC-LICENSED INDIVIDUALS WHILE ON DUTY Description of Circumstances:

Recently, an NRC inspector observed two licensed reactor operators who I

appeared to be asleep while on duty in the control room. A subsequent NRC l investigation into the matter concluded that the operators were not fully

! attentive to their licensed duties of monitoring reactor conditions, which is a serious matter of safety significance. Furthermore, the investigation l concluded _that management controls were inadequate to assure the alertness of licensed operators while on duty. Enforcement action was taken after it was determined that attentive operators were not present at the controls as required by 10 CFR 50.54(k).

l Discussion:

NRC believes that a relationship exists between the professional attitude of a nuclear plant's operating and management personnel and the degree to which the health and safety of the public is protected. NRC believes that professional attitude is reflected in high standards of performance including pride in the facility as demonstrated by the nuclear power plant staff.

Factors making up this professional attitude include knowledge of all aspects of plant status by licensed control room operators, maintaining an orderly and clean working environment, aggressiveness of the operating staff to prevent operational problems, and correcting observed deficiencies. NRC believes that clarification of its position on this subject is necessary because several recent events involving licensed operators indicate a lack of a professional attitude at some nuclear power plants.

The following conditions and practices are among those the NRC believes to be necessary for the maintenance of a professional atmosphere in the control room and throughout the facility.

1. All on-duty NRC-licensed operators and operating supervisors must be aware of and responsible for the plant status at all times. This includes supervisors being responsible for the performance of all personnel assigned to their shift who could affect plant safety, regardless of specialty affiliation. Knowledge of the plant's status must be assured during shift changes by a formal watch turnover and relief.

Attachment:

< Racantiv issued IE circulars r'p"' b ,

IEC 81-02 February 9, 1981 Page 2 of 3

2. All on-duty NRC-licensed operators must be alert, remain within their immediate areas of responsibility until properly relieved, and be particularly attentive to the instrumentation and controls located within these areas at all times.
3. Potentially distracting activities in the control room and other watch stations must be prohibited (for example: radios, TV, alcohol use or drug abuse, games, horseplay, hobbies, and reading that is not directly job related).
4. Control room access must be limited to those persons on official business only and loitering in this area must be prohibited.
5. All necessary plant-related technical / administrative control room business must be conducted at a location and in such a manner that neither licensed control room operator attentiveness nor the professional atmosphere will be compromised. This includes activities associated with the use of special eating and training facilities for on-shift personnel.

Additional Information:

NRC inspectors will be particularly mindful of those conditions and practices described above during future inspections of licensed nuclear facilities.

l For more specific information, you are referred to the following NRC documents:

1. 10 CFR 50, " Domestic Licensing of Production and Utilization Facilities,"

Paragraph 50.54

2. 10 CFR 55, " Operators' Licenses," Paragraph 55.31 and 55.40
3. Regulatory Guide 1.114, " Guidance on Being Operator at the Controls of a Nuclear Power Plant"
4. IE Information Notice 79-20, Revision 1, "NRC Enforcement Policy -

NRC-Licensed Individuals"

5. Letter from D. G. Eisenhut, NRC, to All Licensees and Applicants, dated July 31, 1980,

Subject:

Interim Criteria for Shift Staffing The following excerpts are taken from some of these documents and are provided for your information:

1. Only licensed operators are permitted to manipulate the controls that directly affect the reactivity or power level of a reactor

[10 CFR 50.54(i)].

2. Licensed operators are required to be present at the controls at all times during the operation of the facility [10 CFR 50.54(k)].
3. Operation of mechanisms and apparatus other than controls that may indirectly affect the power level or reactivity of a reactor shall only be accomplished with the knowledge and consent of an operator licensed in accordance with Part 55 [10 CFR 50.54(j)].

l

IEC 81-02 February 9, 1981 Page 3 of 3

4. The NRC-licensed individual shall observe all applicable rules, regulations and orders of the Commission, whether or not stated in the license [10 CFR 55.31(d)].
5. The operating test, to the extent applicable to the facility, requires the applicant to demonstrate an understanding of:

The necessity for a careful approach to the responsibility associated with the safe operation of the facility

[10 CFR 55.23(1)].

6. In order for the operator at the controls of a nuclear power plant to be able to carry out these and other responsibilities in a timely fashion, he must give his attention to the condition of the plant at all times. He must be alert to ensure that the plant is operating safely and must be capable of taking action to prevent any progress toward a condition that might be unsafe (Regulatory Guide 1.114.B).

NRC policy regarding responsibility for safe operation of NRC-licensed facilities as stated in IE Information Notice 79-20, Revision 1, continues to be as follows:

1. "The facility licensee is responsible for assuring that the facility is operated safely and within the requirements of the license, technical specifications, rules, regulations, and Orders of the NRC, and for the actions of their on-duty employees while on site."
2. "NRC-licensed individuals are responsible for taking timely and proper actions that will not create or cause a hazard to ' safe operation of the facility' (i.e., actions or activities, including failure to take action, related to the facility that could have an adverse effect on the health and safety of the public, plant workers, or the individuals)."

Recommended Action for Licensee's Consideration:

Each power reactor licensee should review and revise, as necessary, their administrative controls regarding operator performance to ensure the guidance contained or referenced herein is incorporated. These administrative controls should prescribe performance requirements for licensed personnel and specify types of activities that are prohibited while licensed personnel are on duty.

These' administrative controls should be considered for applicability to other plant personnel whose actions, while on duty, may affect plant safety or the orderly conduct of facility operation. Licensees should assure dissemination of these administrative requirements to affected personnel.* It is also requested that licensees have their licensed personnel review this Circular and IE Information Notice 79-20, Revision 1, as well as Regulatory Guide 1.114.

No written response to this Circular is required. If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.

"A copy of this Circular was mailed directly to each licensed reactor operator and senior reactor operator.

Attachment IEC 81-02 I February 9, 1981 RECENTLY ISSUED IE CIRCULARS Circular Date of No. Subject Issue Issued to 81-01 Design Problems Involving 1/23/81 All power reactor Indicating Pushbutton facilities with Switches Manufactured by an OL or CP Honeywell Incorporated 80-25 Case Histories of 12/5/80 All radiography Radiography Events licensees 80-24 AECL Teletherapy Unit 12/2/80 All teletherapy Malfunction licensees 80-23 Potential Defects in Beloit 10/31/80 All power reactor Power Systems Emergency facilities with Generators OL or a CP 80-22 Confirmation of Employee 10/2/80 All holders of a Qualifications power reactor OL or CP architect-engineering companies and nuclear steam system suppliers

' 80-21 Regulation of Refueling 9/10/80 All holders of a ,

Crews power reactor OL or CP 80-20 Changes in Safe-Slab Tank 8/21/80 All Part 50 and Part Dimensions 70 fuel facility licensees 80-19 Noncompliance with 8/26/80 All medical licensees License Requirements for Medical Licensees 80-18 10 CFR 50.59 Safety 8/22/80 All power reactor Evaluations for Changes to facilities with an Radioactive Waste Treatment OL or CP Systems 80-17 Fuel Pin Damage Due to Water 7/23/80 All holders of PWR Jet from Baffle Plate Corner OLs and PWR cps OL = Operating Licenses CP = Construction Permit I

--. . _

Retrieved from "https://kanterella.com/w/index.php?title=ML20137H045&oldid=2869863"