IR 05000313/1975010
| ML19326B600 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/26/1975 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326B587 | List: |
| References | |
| 50-313-75-10, NUDOCS 8004160381 | |
| Download: ML19326B600 (17) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
, REGION IV IE Inspection Report No. 50-313/75-10 Docket No. 50-333 Licensee: Arkansas Power and Light Company (AP&L)
License No. DPR No. 51 Sixth and Pine Streets Pine Bluff, Arkansas 71601 Category B Facility: Arkansas Nuclear One (ANO-1)
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Location: Russellville, Arkansas Type of License: PWR Power Reactor, 2568 Mwt Type of Inspection: Routine, Unannounced Emergency Planning, Analytical Measurenents, and Radiation Protection
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k Date of Inspection: August 12-14, 1975 Date of Previous Radiological and Environmental Protection Inspection: June 11-13, 1975 Inspector:
.fAAf]'k/?!L(/fV Shf):5
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BlaineMurray,RadigerSpecialist
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/Date/
Accompanying Personnel: None
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16( Phl e1 [-
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Reviewed By:
L i,i Glen D. Brown, Chief
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Radiological and Environmental Protection Branch
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SUMXtRY OF FINDINGS I.
Enforcement Action Contrary to Section 5.3 of the Emergepay Plan, training sessions were not conducted semi-annually to insure that personnel are familiar with their duties and responsibilities. (See DETAILS, paragraph E.4)
This item is a deficiency.
II.
Licensee Action on Previously Identified Enforcement Matters 1/
Control of Portable Radiation Survey Instruments
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The individual responsible for initiating corrective action was on vacation. As a result, it was not determined if the necessary corrective action has been completed.
(.See DETAILS, paragraph D.1) This item remains open, r-s III. New Unresolved Items
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75/10-1 Calibration Procedures for Emergency Survey Eauipment Present procedures do not include proper calibration of emergency survey counting equipment.
(See DETAILS, paragraph Z.2.b)
IV.
Status of Previously Identified Unresolved Items 2/
75/03-1 Sample Losses in Delivery Lines
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e Tests have not been conducted to determine the amount of scmple loss occurring in the gaseous sample delivery lines. This item remains open.
(See DETAILS, paragraph D.2.g)
75/01-1 Effluent Monitoring System Testa Comparisons'between laboratory analyses and waste effluent monitors have not been completed. This item remains open.
(See DETAILS, paragraph D.2.h)
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(continued)
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.IE Inspection Report 50-313/75-03
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IE Inspection Report 50-313/75-05
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74/14-03-Radiation Levels Inside Reactor Containment i
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Corrective action related to radiation levels in cantafnment which y
exceed the design basis have not been completed. This item remains open.
(See DETAILS, paragraph D.2.1)
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75/05-1 Radiation Levels at Restricted Area Fence Procedures have not been completed to include radiation measurements
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at the restricted area fence. This item remains open.
(See DETAILS,
j paragraph D.2.a)
i 75/05-2 Air Sampler Flow Rates
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Flow rates for ANO air samplers have not been determined. This item remains open.
(See DETAILS, paragraph D.2.b)
75/05-3 Whole Body Counter Calibration Procedures l
Calibration procedures have not been completed for the whole body
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counting system. This item remains open.
(See DETAILS, paragraph D.2.c)
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75/05-4 TLD Calibration and Quality Control Procedures I
Calibration and Quality Control procedures have been completed for the TLD read-out system. This item is considered closed.
(See DETAILS, paragraph D.2.d)
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t 75/05-5 Laboratory Counting Eouipment Calibration Procedures
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l Calibration procedures have not been completed for the laboratory
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counting equipment'. 'This lie'm GenifiETppEn.
(See DETAILS, paragraph D.2.e)
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75/05-6 Training Radiological training has not been completed. This item remains open.
(See DETAILS, paragraph D.2.f.)
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Unusual Occurrences
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None VI.
Other Signigicant Findings
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None
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VII. Management Interview-At the conclusion of the inspection on August 14, 1975, a management interview was held to discuss the inspection findings. The following AP&L personnel were in attendance.
l-C. H. Halbert, Technical Support Engineer J. W. Anderson, Plant Superintendent
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R. G. Carrol, Health Physics Supervisor l
L. Alexander, QC Engineer l
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The items discussed and the licensee's position with respect to these
items, as applicable, follow.
1.
Scope of Inspection The inspector outlined the areas covered during the inspection.
2.
Items of Noncompliance The inspector identified the apparent item of noncompliance.
(See DETAILS, paragraph E.4)
3.
Status of Previously Report Unresolved Items The licensee provided expected completion dates for outstanding e
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unresolved items.
(See DETAILS, paragraph D.2)
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4.
Calibration of Survey Team Counting Equipment A licensee representative stated that calibration procedures for instrumentation used to analyze Emergency Team air samples will
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be revised.
(See DETAILS, paragraph E.2.b)
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i 5.
Scope of Emergency Drills I
A licensee representative stated that the scope of future e=ergency
drills (e.g., involving off-site support agencies such as Arkansas i
Health Department, Arkansas Highway Patrol, etc.) will be reviewed.
(See DETAILS, paragraph E.6)
6.
Notification of Emergency Drills A licensee representative stated that IE Region IV will be given prior notice for all future emergency drills.
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(continued)
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DETAILS A.
Persons Contacted i
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Arkansas Power and Light Compan3 _(AP&L)
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J. W. Anderson, Jr., Plant Superintendent C. H. Halbert, Technical Support Eagineer R. G. Carrol, Health Physics Supervisor D. C. Trimble, Training Coordinator L. Alexander, QC Engineer
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2.
Russellville Fire Department D. Sacrey, Fire Chief
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3.
Energy Research and Development Administration
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W. Sc: alley, Assistant for Emergency Preparedness, RAP-Region II.
St. Marv's Hospftal, Russellville D. C. Rains, Administrator
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5.
Arkansas Health Department E. L. McGuire, Health Physicist
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Pope County Sheriff Department i
W. N. Abernathy, Sheriff e'
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Arkansas Highway Patrol
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~ A. D. Kendall, Dispatcher, Clarksville Station B.
Health Physics and Chemistry Organization No changes have occurred in the Health Physics and Chemistry staff since that reported in IE Inspection Report No. 50-313/75-03.
J C.
Scope of Inspection The purpose of this inspection was to review the E=ergency Planning program and to complete the Radiation Protection inspection which was partially reported in IE Report 50-313/75-05.
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Licensee Action on Previously Reported Items 1.
Items of Noncompliance Control of Portable Radiation Survey Insturments This item was reported in IE Inspection Report No's 50-313/75-03 and 50-313/75-05 and involved the development of a procedure which will establish calibration frequencies for survey instrurents.
The AP&L employee responsible for developing the procedure was on vacation. As a result, the status of the procedure was not determined. This item remains open.
2.
Unresolved Items a.
75/05-1 Radiation Levels at Rer.tricted Area Fence This item was reported in IE Inspection Report No.
50-313/75-05 and involved obtaining radiation levels at the restricted area fence as part of routina radiation survey procedures. A licensee representative stated thst survey s,
procedures are being revised to include measuraments along
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the restricted area fence.
It uas estimated that these procedures should be completed and approved by early Octcher,
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1975.
b.
75/05-2 Air Samole Flow Rates This it.im was reported in IE Inspection Report No. 50-313/75-05 and involved the determination air sampler flow rates. A licensee representative stated that a NES type rotometer has been ordered.
It was estimated that flow rate determinations
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will be completed by mid-September, 1975.
c.
75/05-3 Whole Body Counter Calibration Procedures This item was reported in IE Inspection Report No. 50-313/
75-05 and involved the development of written procedures for calibrating the whole body cou. ting' system. A licensee representative stated that this procedure will be co=pleted by early October, 1975.
d.
75/05-4 TLP Calibration and Ouality control Precedures e
This item was reported in IE Inspection Report No. 50-313/
75-05 and involved the development of written procedures for O
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calibrating the TLD system.. Procedure No. 1303.85 has
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been developed which contains calibration and quality control requirements for the TLD system. The inspector reviewed the TLD calibration and quality control procedures. No discrepan-cies were noted. This item is considered closed.
I e.
75/05-5 Calibration Procedures for Laboratory Countine j
Equipment j
This item was discussed in IE Inspection Report No. 50-313/
75-05 and involved the development of written procedurec for calibrating laboratory counting equipment used to analyze health physics surveys. A licensee representativo teated
that the calibration procedure ie presently being vcitten.
It was estimated that the procedure will be completed by-early October, 1975.
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75/05-5 Training This item was discussed in IE Inspection Report No. 50-313/
75-05 and involved providing radiological training to employees whose job description requires that they receive such training.
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iO It was noted that since the previous inspection, radiological training sessions were held on June 20, 1975 and July 25, 1975.
However, the licensee's training records indicated that tha reccin-ing individuals still have not received the necessary training.
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Name Employment Date 4-G. Fiser 5/74 l-P. Jacob 8/74 J. Orlicek 5/74
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C. Shively S/74
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B. Baker 5/74 B. West 5/74 A licensee representative stated that the next radiological
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training session is set for September 3-5, 1975.
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g.
75/03-1 Sample Losses in Gaseous Sample Delivery Lines This' item was discussed in IE Inspection Report No. 50-313 75-03 and involved the determination of sample loss in the gaseous sample delivery system. A licensee representative
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stated that nothing has been accomplished in regard to de-
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termining the amount of sample lost. An estimated completion date for this study was not set.
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75.01-1 Effluent Monitoring System Tests
.This item was discussed in IE Inspection Report J. 50-313/
75-01 and involved the comparison of laboratory ana'yses versus process monitor indication for similar effluent
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releases. A licensee representiative stated that these comparisons should be completed by mid-October, 1975.
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74/14-3 Radiation Levels Inside Reactor Containment This item was discussed in RO Inspection Report No. 50-313/
74-14 and involved radiation level in containment which exceeds design bases. A licensee representative stated that the status of this item is unchanged from the previous inspection.
No completion date has been established.
E.
Emergency Planning 1.
Facilities and Equipment a.
Emergency Kits The inspector examined the emergency kits maintained at the Control Room, E=ergency Assembly Area, Emergency Control
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Center, Emergency Control Office, and Site Ambulance. The inventory of supplies and equipment to be maintained in each of the kits appears in Appendix J of the Emergency Plan. No inventory discrepancies were noted. The licensee's records
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indicated that an emergency kit inventory is perfor=ed each month. The results are recorded on forms H.P.,
7.2, 7.3, and 7.4.
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Emergency Control Centers 4.
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The inspector visited each of the emergency control centers
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listed in the Emergency Plan to verify that the specified equipment was available and operable. No discrepancies were noted,
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c.
Emergency Communication Equipment i
The specified emergency communication equipment was examined
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and found to be operable.
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d.
Changes in Emergency Equipment and Facilities Several changes to the Emergency Plan have occurred since the previous Emergency Planning Inspection.
It was noted N
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that changes were reviewed and approved by the Plant Safety Committee. The licensee's records indicated that copies of
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the changes were sent to the NRC and designated off-site support agencies.
2.
Monitoring Instruments a.
Inventory The instrumentation used to monitor radioactive releases was examined. Monitoring instrumentation consists of survey team equipment contained in the emergency kits and the plant stack monitor (RE 7400)
Survey team equipment is located at the Emergency Control Center and Emergency Assembly Area. Each kit includes a GM type detector, a count rate meter, and a sample counting chamber.
The stack monitor (RE 7400) includes two NaI detectors and
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l associated display meters and strip chart recorders. The i
stack monitor read-out systems are located in the centrol
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The inspector examined the specified monitoring equipment and verified that the equipment was available and operable.
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b.
Calibration
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Survey Team Equipment'
...Z~_~.' ~ ' ~T W % t"able sonitors maintained in the emergency kits
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are calibrated each quarter.
In reviewing calibration i
procedure No. 1602.19, it was noted that the conitors designated to analyze air samples were not calibrated in the same configuration as would the case under emergency counting conditions. Under the present pro-
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cedures, the survey team meters are calibrated in the same manner as other meters used for routine plant surveys.
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A licensee representative stated that emergency survey meter calibration procedure will be modified to include calibration of the sampler holder, deteccor, and count rate meter as one unit.
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-10-j (2) Stack Monitor
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Environmental Technical Specification 2.4.2.2 (Monitoring Requirements) requires that gas conitors be c911brated at least quarterly. The licensee's records indicated that RE 7400 was calibrated on the folicwing dates:
June 6, 1974 September 7, 1974 j
December 10, 1974 March 17, 1975 June 30, 1975
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Gas monitors are calibrated as per Procedure No. 1304.27
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titled:
" Process Radiation Monitoring System" 3.
Medical a.
Treatment Facilities - Off-Site The license has an agreement with St. Mary's Hospital, Russell-ville, to provide emergency cedical treatment. The inspector visited St. Mary's hospital and verified that the agreement, dated May 15, 1972, between AP&L and the hospital remains in effect. The inventory of emergency supplies to equipment maintained at St. Mary's specified in Appendix E of the Emergency Plan was examined. No discrepancies were noted.
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b.
Treatment Facilities - On-Site i
A first aid room is maintained near ANO-2.
A list of first aid supplies and equipment appear in Appendix J-6.
No dis-l crepancies were noted.
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I c.
.Oualified Physicians A St. Mary's hospital representative stated that the following
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physicians have received formal emergency radiological
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training.
J. M. Carter, M.D.
K. O. New, M.D.
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R. M. Franklin, M.D.
S. D. Teeter, M.D.
According to a hospital representative, all of the above
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physicians are presently on the St. Mary's staff.
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(Continued)
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d.
Ambulance Service The licensee maintains an ambulance at the site. An inventory of supplies and equipment to be maintianed in the Ambulance Emergency Kit is listed in Appendix J-5 of the Emergency-Plan.
No discrepancies were noted.
4.
Training a.
On-Site Personnel Section 5 of the Fnereercy Plan outlines the training program.
Section 5.3 states, in part:
Training sessions are conducted
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semi-annually to insure that personnel are faciliar with j
their duties and responsibilities assigned by the E=ercancy Plan and procedures..."
The licensee's training records indicated that training was conducted on the fo11 cuing dates:
Team Date Trainine Conducted gs Emergency Radiation Team 10/9/73 (
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11/15/73 U
4/26/74 Medical and Decontamination Team 4/29/74 12/3/74
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Emergency Fire Team 4/23/75 5/12/75 5/27/75
Emergency, Security and Evacuation Team 4/25/7!,
Duty Emergency Coordinators 4/29/74 As the above dates indicate, training was not conducted at the required frequency.
b.
Off-Site Support Acencies l
Section 5.4 of the Emereency Plan. states, in part:
"... Periodic reviews with local groups are held annually and as soon as l
possible following assigncent of new key personnel to these
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local outside group."
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The licensee's records indicated that training was conducted on the following dates:
Organization Date Training Conducted
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Russellville Fire Department 9/16/74 7/7/75 Yell County Sheriff 7/29/75 Pope County Emergency Services 6/10/75 St. Mary's Hospital 12/3/74 11/19/74 Pope County Ambulance Service 2/3/75 5.
Drills a.
Frequency The licensees records indicated that emergency drills were conducted on the following dates.
(1) December 3, 1974 - Medical Drill Included transporting accident victim to St. Mary's
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Hospital for treatment.
(2) February 11, 1975 - Plant Evacuation Included accountability procedures for AP&L and construc-tion personnel.
(3) May 27, 1975 - Fire Emergency b.
Records l
Records of the emergency drills' vere maintained by the license.
These records included comments by AP&L personnel assigned to observer and evaluate the drills.
l 6.
Contact with Off-Site Support Agencies
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The following off-site support agencies were contacted by the inspector to determine if the licensee has maintained contact and coordination with the various agencies.
- NRC Region II and IV
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RAP Region II (continued)
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. reviewing the Emergency Plan.
The Arkansas Etate Department of Health, NRC, RAP, and Arkansas Highway Patrol representatives stated that they have not been contacted during the past year.
7.
Licensee QC Audits The licensee's records indicated that an audit of AMO-l's Emergency Plan was conducted May 8-16, 1975.
Some of the discrep-ancies noted were lack of a proper training program and copies of the Emergency Plan were not available at all designated locations.
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F.
Radiation Protection V
The following is a continuation of the Radiatien Protection items that were not covered during IE Inspection Report 50-313/75'-05.
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1.
Material Inventory and Records a.
Sealed Sources The following is a list of sealed sources that exceed 10 times the values listed in 10 CFR 20, Appendix C.
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Date Nuclide Activity Model Received Use 137CS 50 Ci Tech. Ops. 682 4/6/73 Calibration Sot.rce 137CS 39 mci Trapelo Ax-4 2/73
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137CS 100 mci ICP-371 5/7/73
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CO 20UCi Trapelo Ax-4 2/73
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23go 500 mci MRC-Co-144 1/30/74
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Pu-Be 4.71Ci MRC-Pu-Be 1/16/75
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238 Pu-Ee 1Ci Boroftometer 1/14/74
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Records The licensee's records indicated that receipt and accountability records are maintained on all radoactive materials.
This included sealed and unsealed sources. Acccuntability informa-
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tion is recorded on Form H.P.
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The license records
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indicate that approximately 131 individual sources are presently on site. Radioactive accountability procedures appear in Procedure No. 1002.29.
c.
Leak Tests Technical Specification 4.14 contains leak test requirements.
Leak test records for the sources listed in the above item 1.a.
were reviewed. The licensce's records indicated that leak tests were performed on August 26, 1974, November 19, 1974, and February 27, 1975. Tests results indicated that for any one source, the leakage was less than 0.005 microcuries.
Leak test procedures are container in Procecure No. 1602.34 titled:
" Leak Test of Scaled Sources".
2.
Instrument Calibration The calibration records for Health Physics instruments such as j
portable meter, friskers, portal monitors, and hand and foot counters were examined.
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The licensee's records indicated that Health Physics instruments are calibrated quarterly. A separate calibration procedure has been written for each type of instrument. These procedures appear in procedure No.s 1303.69 through.105.
It was noted that except for a few high rangt gamma survey meters, each instrument is calibrated at two points on each' range scale. Calibration results were recorded on Form H.P. 6.5.
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3.
Radioactive Shipments Radioactive shipping records for the period July 1, 1974 through August 14, 1975 were examined. The licensee's records indicated that three solid waste shippments, consisting of filter resin and concrete contain in 55 gallon drums, were shipped on the following
. dates:
Dates Total Activity / Shipment 7/7/75 336 mci 7/9/75 337 mci 7/11/75 520 mC1 kA) ^
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-h In addition to the above shippments, it was noted that several miscellaneous. shipments (e.g., contaminated clothing, low activity waste, etc.) have also been made. Shipping procedure are contained in Procedure No. 1602.13 titled:
" Shipment of Radioactive Materials".
The following shipping forms are also part of the shipping procedures.
a.
" Chronological Log of Radioactive Materials Released" b.
" Transmittal of Special/Non Routine Materials"
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The licensee's shipping records and procedures were reviewed to determine compliance with 10 CFR 71 and D.O.T. regulations. No discrepancies were noted.
G.
Analytical Measurements Verification measurements were performed on the following types of samples:
1.
Liquid Waste - Hold-up Tank T-16A 2.
Gaseous Waste - Decay Tank T.18A p
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Charcoal Filter - From Stack Vent System
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4.
Particulate Filter - From Stack Vent System The licensees measurements are compared with measurements made by NRC's reference laboratory, Idaho Health and Safety Laboratory (IHSL).
IHSL's measuremsce are referenced to the National Bureau of Standards by laboratory intercomparisons. Verification comparisons are only =ade Z; 7 E JZ.f82 those nuclides identified by IHSL as being present inconcentrations
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greater than 10% of the respective MPC's for liquid and gas samples and total activity per sample for stack particulate and charcoal filters.
- Attachment No. 1 contains the acceptance criteria.
The following table shows the comparison results.
1.
Liquid (Waste held-up tank T16 A - Collected June 12, 1975)
Nuclide NRC Measurement ANO Measurement Decision
Gross geta 2.7 + 0.1 x 10-5 uCi/ml 5.42 x 10-4 uCi/mi disagreement-2 H
6 + 0.01 x 10-2 uCi/ml 9.85 x 10 uC1/mi disagreement 110 mag 9.3+ 0.4 x 10-6 uCi/ml 1.02 x 10-5 uCi/mi agreement 137Cs 5.7 + 0.2 x 10-6 uC1/ml 5.5 x 10-6 uCi/ml agreement
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131 5.1 + 0.2 x 10-5 uCi/mi Co
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6.34x10juC1/mi I
4.98 x 10-agreement
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5.4 + 0.3 x 10-6 uCi/ml uCi/ml agreement O
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-16-2.
Gascons (Gas Decay Tank T18A - Collected June 12, 1975)
Nuclide NRC Measurement.
ANO-1 Measurement Decision 133-1 4.9+0.2uci/mg 7.69 x 10 uci/mi disagreecent Xe 133m 7.3 + 0.5 x 10~ uci/mi 2.99 x 10~3 uci/ml disagreement Xe 85Kr 9t i x 10-4 uci/mi 4.33 x 10-3 uci/mi disagreenent 3.
Particulate Filter Stack Vent - Co112cted June 11, 1975)
Nuclide concentrations identified by IHSL were less than statistical I
reliability limits.
4.
Charcoal Cartridge (Stack Vent - Collected June 11, 1975)
Nuclide concentrations identified by IHSL vere less than statistical reliability limits.
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ATTAC1 BENT NO.1
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' Criteria for Comparing Analytical Measurements The following is the criteria used in comparing the results of capability tests and verification measurements. The criteria are based on an ecpirical relationship established through prior experience and this program's analytical requirements.
In these criteria, the judgement limits vary in relation to the comparison of the resolution.
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Resolution = NRC Value NRC Uncertainty Ratio = Licensee Value NRC Value Comparisons are made by first determining the resolution and then reading across on the same line to the corresponding ratio. The following table shows the acceptance values.
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RESOLUTION RATIO O)
Possible Possible
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Agreement Agreement A Agreenent B
0.4 - 2.5 0.3 - 3.0 No comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
>200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
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"A" criteria are applied to the following analyses:
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Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
Tritium analyses of liquid samples.
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Iodine on adsorbers.
"B" criteria are applied to the followir, analyses:
Gamma Spectrometry where principal gamma energy used for identification is less'than 250 Kev.
'89Sr and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same
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(v, reference nuclide.
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