ML19282D185
| ML19282D185 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 03/21/1979 |
| From: | Axelson W, Essig T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282D184 | List: |
| References | |
| 70-1308-79-02, 70-1308-79-2, NUDOCS 7905230442 | |
| Download: ML19282D185 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III Report No. 70-1308/79-02 Docket No. 70-1308 License No. SNM-1265 Licensee: General Electric Company 175 Curtner Avenue San Jose, CA 95125 Facility Name: Morris Operation Inspection At: Morris Site, Morris, IL Inspection Conducted: Feb,ruary 28, March 1, 2 and 7, 1979 b
L. Axelson Inspector: {f.-W.
A' 3 u 71 d
Approved By:
T. H. Essig, ief Environmental and Special Projects Section Inspection Summary Inspection on February 28, March 1, 2 and 7, 1979 (Recort No. 70-1308/79-02)
Areas Insoccted: Routine, unannounced emergency planning and fire protec-tion inspection, including an examination of the licensee's Emergency Plan and Procedures; coordination with offsite agencies; emergency equipment,
supplies, and communications; training; tests and drills; fire prevention and protection; licensee internal audits of the above subject material; and discussion of results of the confirmatory measurements samples collected in October 1978.
The inspection involved 26 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were identified during this inspection.
790528988 W7-
DETAILS 1.
Persons Contacted Licensee Personnel
- E.
Voiland, Plant Manager
- K. Eger, Ph.D., Senior Engineer, Licensing and Radiological Health
- T.
Ingels, QA and Safeguards Manager
- J. McGrath, Plant Safety Supervisor Offsite Agency Personnel B.
Coleman, Chief, Morris Fire Department E. Livsey, Assistant Chief, Coal City Fire Department R. Schinderle, Administrator, Saint Joseph Hospital C. Richards, Chief of Security, Saint Joseph Hospital J. Temple, Director, Grundy County Emergency Services and Disaster Agency J. Shelly, Sheriff, Will County
- Denotes those present at the exit interview.
2.
Previous Inspection Findings (Closed) Significant Inspection Finding (70-1308/78-03): Better understanding of assigned responsibility of support agencies.
During this inspection the inspector determined that the licensee visited with the Coal City Fire Department in October 1978 and Saint Joseph Hospital in September 1978. These visits were made to ensure that the agency is prepared to make the appropriate emergency response. During this inspection, the inspector visited these agencies and determined that adequate agreements exist.
The inspector has no further questions regarding this matter.
3.
Coordination with Offsite Support Agencies The inspector reviewed records, procedures, and written letters of agreement relating to licensee coordination of emergency planning with offsite support agencies. During that review, the inspector determined that letters of agreement and procedures were current as required by the Emergency Plan.
The inspector also reviewed lict7see records of telephone listings of support agencies.
These i v. ;rt s indicated that telephone listings were current.
s During this inspection, the inspector visited with the represen-tatives of offsite support agencies identified in Paragraph 1.
During those visits, existing agreements between the licensee and the agencies were verified and coordination was noted to be adequate for the agencies to maintain an effective response capability.
No formal training has been offered to these agencies by Morris Operation. However, agencies requiring training are also listed in the Dresden Emergency Plan and are currently being trained by Radiation Management Corporation (RMC) pursuant to their agreement with the Dresden Nuclear Station.
No items of noncompliance or deviations were identified.
4.
Facilities, Equipment, and Supplies The inspector toured the f acility and examined emergency equipment lockers located in the administration and process buildings.
All emergency supplies were present as rbquired by the Emergency Plan.
During this inspection, operational checks of this equipment were conducted and found to be satisfactory.
The inspector reviewed records of monthly inventories conducted during 1978 of these supplies. These records indicated that missing items were replaced in a timely manner.
Completed check-lists were reviewed by the plant's Safety Supervisor.
During this inspection, the inspector examined the first aid facility located in the South Plug Callery.
The inspector determined that required supplies were present and appeared adequate for the licen-see's needs.
No items of noncompliance or deviations were identified.
5.
Emergency Plan and Procedures The inspector discussed review and updating of the Emergency Plan and associated procedures and the licensee's responsibility to maintain required emergency procedures which reflect current plant activities. The licensee is required to conduct this review annually.
During this inspection, it was deteruined that the latest revision of the licensee's Emergency Plan (NEDE-21894) had not been fully implemented. This Emergency Plan has been reviewed by the NRC's Accident Analysis Branch and has been found to be satisfactory.
Results of this review were sent to the licensee in a letter dated February 5,1979 from the Division of Fuel Cycle and Material Saf ety.
The inspector expressed some concern regarding the licensee's schedule for implementing the plan. The licensee stated that it will be fully implemented on or before April 15, 1979.
This matter will be reviewed during a future inspection.
No items of noncompliance or deviations were identified.
6.
E=ergency Plan Training The inspector reviewed records covering scheduling and content of training provided to licensee personnel in first aid, emergency planning, and emergency procedures. Various aspects of the Emer-gency Plan were discussed in monthly safety meetings which were attended by all technical personnel.
The inspector examined the Emergency Brigade Training Manual and minutes of monthly safety meetings conducted in 1978.
Several safety technicians and plant supervisors are Emergency Medical Technicians.
In addition, multi-media Red Cross training was offered to plant personnel and retraining was scheduled to main-tain current first aid capability. The inspector determined that all required emergency plan training was conducted for CY 78.
No items of noncompliance or deviations were identified.
7 Emergency Drills The inspector examined the licensee's records (for CY 1978) covering conduct of emergency plan drills or exercises.
Drills have been conducted on the required quarterly frequency and drill critiques have been held. Recommendations for improvement derived from the drills appear to have been implemented.
e No items of noncompliance or deviations were identified.
8.
Licensee Internal Audits Licensee internal audits consist primar / of e.; amination of emer-gency equipment. Monthly inventories a a functional checks were conducted of emergency lighting, emergency eq susant lockers, and fire protection equipment.
The inspector revie ed t acords of these audits (for CY 1978) and determined that all equipstat and supplies were examined or tested as prescribed by au?ft procedures.
During this inspection the inspector examined several fire inspection audits conducted by the Factory Mutual Ccmpany (Arkvright-Boston Insurance Company).
Currently, these audits are conducted semi-annually. Audit Report 77-7-1 identified a deficiency relating to fire protection in Warehouse A.
Specifically, the audit reccenended the need for providing automatic fire suppression (sprinklers) pro-tection in Warehouse A or removal of significant combustible materials from this building.
The licensee corrective action in regard to this finding was to remove some combustible material from Warehouse A.
Followup fire inspections by Factory Mutual Ccmpany indicated this ae. ion was insufficient and continued to recommend automatic fire suppression.
During a plant tour of Warehouse A, the inspector noted that radio-active waste was stored in this building.
At the time of the inspection, approximately twenty 55-gallon drums of low-level radio-active wastes were stored. The inspector expressed concern about this vaste being stored in a warehouse with a large loading of combustible material.
Also, the inspector noted that automatic fire suppression systems were not installed in this warehouse. Accord-ingly, the inspector requested that the licensee resolve this matter.
This was discussed at the exit interview.
9.
Fire Prevention and Protection a.
Firefighting Procedures Firefighting procedures were developed and included in the Emergency Brigade Training Manual. Procedures indicated proper techniques for firefighting.
No problems were iden-tified while reviewing these procedures, b.
Training The licensee has a well equipped and trained fire brigade to fight common fires at this facility.
The brigade received classroom training in firefighting and conducted several field exercises. Field exercises involved extinguishing controlled fires by portable extinguishers.
Actual use of equipment from both fire hose houses was also conducted as part of this training.
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f c.
Firefighting Equipment The inspector examined selected firefighting and detection equipment in areas where radioactive material was present.
Fire extinguishers were located as stipulated in the Emer-gency Plan.
Both fire hose houses were examined and found to be satisfactory. Fire suppression equipment located in some buildings was examined and found to be satisfactory.
With the exception noted in Paragraph 8, the inspector observed that the licensee has adequate firefighting suppression and detection equipment to extinguish small fires or control large fires until local fire departments arrive.
No ite=s of noncompliance or deviations were identified.
10.
Results of Comparison of Confirmatorv Measurements Results of comparative analyses performed on ef fluent samples were reviewed with the licensee.
The results are shown in Table I.
The criteria for comparing measurement results are given in Attachment 1.
Of six sample comparisons, the licensee's results yielded five agree-ments and one possible agreement.
During this inspection, samples were collected for future comparative analyses. Samples collected included a six month composite of air particulate and a liquia effluent from the vaste lagoons.
No items of noncompliance or deviations were identified.
10.
Exit Interview The inspector met with the licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on March 2, 1979.
The inspector summarized the scope and findings of the inspection. The licensee stated the following in response to certain items discussed:
a.
Agreed to fully implement the new Emergency Plan and its procedures on or before April 15, 1979.
b.
Indicated reluctance to concur with the inspector's findings identified in Paragraph 8.
The inspector requested that the licensee respond in vriting to this office indicating their intended actions to resolve the matter s
a-identified in Paragraph 8.
Specifically, the inspector stated that he concurred with the fire insurance audit findings and that cor-rective action was necessary because radioactive waste material was stored in that building.
/.
Attachments:
- 1., Criteria for Comparing Analytical Measurements
- 2., Confirmatory Measurements Program 4
0 t
ATTAC1t!C:7 I e
CRITERIA FOR COMPARING ANALYTICAL MEASURC:ENTS This attachment provides criteria for comparing results of capability testo and verification measurements.
The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.
In these criteria, the judgment limits are variable in relation to the comparison of the NRC Refetence Laboratory's value to its associated one sigma uncertainty. As that ratio, referred to in this program as
." Resolution", increases, the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement should be con-sidered accepteble as the resolution decreases. The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported by the NRC Reference Laboratory, unless such rounding will result in a narrowed category of acceptance.
The acceptance category reported will
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be the narrowest into which the ratio fits for the resolution being used.
RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE 7ALUE Possible Possible Agreement Agreement "A" Agreeable "B"
<3 No Comparison No Comparison No Comparison
>3 and <4 0.4 3.0 No Comparison 2.5 0.3 2.5 0.3
- 3.0 2.0 0.4 T4 and <8 0.5 2.5 2.0 0.4 T8 and <16 0.6 1.67 0.5 T16 and <51 0.75 - 1.33 0.6
- 1.67 0.5
- 2.0 1.67 751 and <200 0.80 - 1.25 0.75 - 1.33 0.6 1.25 0.75 - 1.33 I200 0.85 - 1.18 0.80 "A" criteria are applied to the following analyses:
Camma spectromatry, where principal gacma energy used for identifi-cation is greater than 250 kev.
Tritium analyses of liquid sampics.
"B" criteria are applied to the following analyses:
Camma spectrometry, where principal ga=ma energy used for identifi-cation is less than 250 kev.
Sr.-89 and Sr-90 determinations.
Cross beta, where samples are counted on the same date using the same reference nuclide.
4 m.
m.
TABLE I U S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPE C TIO N A NO E NF O RC E M E N T CONF IR M A TOR Y ME A SUREMENT S PROGR A M F AC ILITY : MORRIS OP FOR THE 4 QUARTER OF 1978
--NRC-------
---NR C : L IC EN S E E----
SAMPLE ISOTOPE RESULT ERROR REF, ULT ERROR
' RA TIO RE S T
P FILTER CS 137 3 0 E -0 5 4 4E-06 1 3 E -0 5 00 4 3E-01 6 8E +00 P
CO 60 6 3 E -0 5 7 4E-06 5 7 E -0 5
'0.0 9 0E -01 8.5E + 00 A
F SPIKED CO 57 9 2E-03 3 0E-04 8 2E-03 00 8 9E-01 3 1 E +01 A
CS 1 34 1 3 E -0 2 5 0E-04 1 2 E -0 2 0.0 9 2 E -01 2.6E + 01 A
CS 137 6 7E-03 3 0E-04 5 7E -0 3 00 8 5 E -01 2 2E +01 A
CO 60 8.8E-03 4 0E-0 4 7 9 E -0 3 00 9 0E -01 2 2E +01 A
T TEST RE S U L T S:
A = A G R E E ME N T 0 =D I S AG RE E ME N T P=PO S S IBLE AGREE *ENT N=NO CO MP A R ISON e
OS