IR 05000295/1982007
| ML20054A974 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/30/1982 |
| From: | Greger L, Miller D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20054A968 | List: |
| References | |
| 50-295-82-07, 50-295-82-7, 50-304-82-07, 50-304-82-7, NUDOCS 8204160250 | |
| Download: ML20054A974 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
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Reports No. 50-295/82-07(DETP); 50-304/82-07(DETP)
l Docket Nos. 50-295; 50-304 Licenses No. DPR-39; DPR-48
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Licensee: Commonwealth Edison Company
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Post Office Box 767 Chicago, IL 60690
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Facility Name: Zion Nuclear Power Station, Units 1 and 2 i
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Inspection At: Zion Site, Zion, IL
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Inspection Conducted: March 16-19, 1982 Inspector:
D. E. Miller Me'
_7/.29/f5'A
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Date
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i f ] h'xg&L Approved By:
L. R. Greger, Chief J Eo M A Facilities Radiation Date I
Protection Section
Inspection Summary Inspection on March 16-19, 1982 (Reports No.50-295/82-07(DETP);
50-304/82-07DETP))
Areas Inspected: Routine, unannounced inspection of operational radiaticn
protection program during refueling outage, including: staffing, advanced l
planning and preparation, training, exposure control, posting and control, material control, and surveys. Also reviewed were past items of noncom-pliance, unresolved items, and open items. The inspection involved 36 inspector-hours onsite by one NRC inspector.
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Results: No items of noncompliance were identified.
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r 8204160250 820331 PDH ADOCK 05000295 G
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DETAILS 1.
Persons Contacted
- K. Graesser, Superintendent
- E. Fuerst, Assistant Superintendent, Operations
- G. Plim1, Assistant Superintendent, Administrative and Support Services D. Howard, Rad / Chem Supervisor
- T. Lukens, Quality Control Supervisor
- G. Trzyna, ALARA Coordinator
- F.
Ost, Lead Health Physicist
- J. Ramage, ALARA Engineering Assistant
- K. Depperschmidt, Radwaste Group Leader
- F. Reseck, Health Physicist, CECO The inspector also contacted several other licensee employees including, Rad / Chem Technicians, Rad / Chem Engineering Assistants, and members of the technical and engineering staffs.
- Denotes those present at the exit meeting.
2.
General This inspection, which began at 9:00 a.m. on March 16, 1982, was conducted to examine radiological aspects of the Unit 1 refueling and maintenance outage. Also reviewed were past items of noncompliance, unresolved items, and open items. The inspector performed independent surveys and reviewed radiation controls and postings during tours of the licensee's radiologically controlled plant areas. Housekeeping and cleanliness were good considering the extent of the maintenance outage.
Radiological conditions appeared satisfactory.
The inspector observed radiological work being performed, including; turbine generator repair, auxiliary building and equipment decontamina-tion, spent resin packaging, and contaminated laundry operation.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance Item (295/82-02-01; 304/82-02-01): Concerning two shipments of byproduct material made by the licensee, to an Agree-
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ment State licensee, without verifying if the receiver's license authorized receipt. The corrective actions described in the licensee's response dated March 5, 1982, were reviewed and appear to be adequate.
No. additional problems were noted.
(Closed) Unresolved Item (295/81-02-01): Concerning whether the Rad /
Chem Supervisor met the requirements of Technical Specification 6.1.D.
The technical specification has been changed to permit either the Rad / Chem Supervisor or Lead Health Physicist to meet the requirements.
No further problems were noted.
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(Closed) Unresolved Item (295/79-04-01; 304/79-05-01): Concerning radiation exposure records not being convenient for review. The licensee has added coding to aid in identification of worker's employer, employee's work function, and CECO employee's duty station.
This coding makes the records more convenient for review. No further problems were noted.
(Closed) Unresolved Item (295/81-26-05; 304/81-23-05): Concerning the release of contents of a gas decay tank without the required 45-day holdup. This item was left unresolved because of differing interpretations of Technical Specification 3.12.2.A.
During this review, the inspector learned that the licensee's Onsite Review Committee had reviewed the proposed release before giving permission to release the contents; and an NRC representative had concurred with the Committee's review. The licensee has applied for a change to the technical specification to clarify intent. This matter is considered resolved. No further problems were noted.
(Closed) Unresolved Item (295/81-06-04; 304/81-23-04): Concerning possible inadvertent release of about 5700 cubic feet of waste gas.
The licensee's review of the incident showed that no effluent
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monitoring system detected the release, nor did area gaseous or direct radiation monitors detect gases in the buildings. During this period, temporary liquid piping existed in Unit 1 to permit installation of the High Range Sampling System. The possibility exists that the gases were vented into containment where they were contained. The temporary piping has been removed and no further significant loss of volume in the waste gas system has been experienced. This event constituted no danger to the health and safety of the public. This matter is considered resolved. No further problems were noted.
(Closed) Open Item (295/81-21-02; 304/81-17-02): Concerning possible leakage from the waste gas system and consequences of such leakage during an accident. The actions describec' in the licensee's response dated September 21, 1981, and Region III's acknowledgement dated December 2, 1981, were reviewed. The licensee's ongoing testing program has identified several leaking components which have been repaired. Recently installed flow measurement instrumentation has improved leak identification capabilities. Review of recent daily gas balance calculations and trending indicates that system integrity has been greatly improved.
The inspector will continue to
review waste gas system integrity during future inspections.
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(Closed) Open Item (295/81-21-03; 304/81-17-03): Concerning nonlinear response found during checking the licensee's Eberline PRM-4 friskers.
The licensee has ordered Eberline PRM-6 friskers to replace the PRM-4s.
The licensee stated that after replacement, the PRM-4 response problems will be investigated. The licensee stated that the nonlinear response at the high end of the scale was found to be conservative, permitting their continued use until replacement.
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4.
Rad / Chem Department Staffing Since previously reported in Inspection Reports No. 50-295/81-21; 50-304/81-17, several organizational changes have been made, including:
a.
F. Ost, former Health Physicist, has been promoted to Lead Health Physicist replacing F. Rescek who was assigned to the CECO corporate office.
b.
J. Ramage, former Rad / Chem Technician (RCT) has been assigned ALARA Engineering Assistant and reports to the ALARA Coordinator.
c.
Liga Minejevs, former Lead Rad / Chem Foreman has been reassigned to a supervisory administrative position reporting to the Assistant Superintendent, Administrative and Support Services.
d.
Former Rad / Chem Foreman W. Cramer and J. Firoved have been reassigned to the training department.
L. Gesiakowski has been promoted to Rad / Chem Foreman from RCT, D. Shamlin was transferred from the quality control department to a Rad / Chem Foreman position, and B. Westerman was transferred from the training department to a Rad / Chem Foreman position.
Currently, there are four Rad / Chem Foremen with no one designated as Lead Rad / Chem Foreman, c.
RCT staffing has been increased to 28, seven of whom are in training.
4.
ALARA Since previously reported in Inspection Report No. 50-295/81-02, the following ALARA activities have occurred, a.
G. Trzyna, formerly a Trainer in the Training Department and a Health Physicist in the Rad / Chem Department, has been assigned to a newly created ALARA Coordinator position. He reports to the Assistant Superintendent, Administrative and Support Services.
b.
J. Ramage, former Rad / Chem Technician, has been assigned to a new ALARA Engineering Assistant position reporting to Mr. Trzyna.
c.
The ALARA Committee continues to meet at least bimonthly.
Members are routinely assigned specific ALARA related projects to study, scope, or perform.
Several projects have been and are being performed.
d.
With apparent plant management backing, support, and participa-tion, the ALARA Coordinator and his assistant have completed several ALARA reviews of high dose outage work, installed temporary shielding, and developed procedures to be used during future outages. A package is assembled for each task.
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e.
Assigned to the ALARA Coordinator and his assistant are twelve contractors and four stationmen to support ALARA related work such as erecting and removing shielding and various decontamination projects.
f.
The ALARA Coordinator and/or his assistant have addressed meetings with contractor and plant personnel to describe ALARA programs, goals, and the responsibility of individuals.
The licensee plans to expand this program.
Although significant progress has been made, additional effort is needed concerning formalization of the ALARA program.
5.
Contamination Control Under the direction of the ALARA Coordinator and his assistant, the licensee is performing a complete cleanup of the auxiliary building.
This includes reduction in contamination levels in all accessible rooms.
The licensee is putting curbing around potential leak areas and placing splatter shields around pump shafts to reduce contamination spread from leakage.
Leak repair is being expedited. Overall appearance and contamination controls appear greatly improved.
The inspector verified that the corrective actions for a previous item of noncompliance concerning control of contaminated tools, have been implemented. No additional problems were noted.
(295/81-15-01; 304/81-11-01). The licensee has initiated a modification to construct
a central tool crib near the spent fuel pool.
6.
Exposure Control a.
External The licensee's film badge and pocket dosimeter records from October 1981 to date were reviewed.
No exposures exceeding 10 CFR 20.101 limits were noted.
A selective review of records for individuals who received greater than 1250 mrems during a quarter indicated that the licensee had completed NRC-4 forms for these individuals.
The licensee is now using self-reading dosimeters for all individuals entering the controlled area.
Plant employees have permanently assigned dosimeters which are exchanged when cali-bration is due; plant employees record their own doses daily when entries are made.
Long-term contractors pick up and return dosimeters daily at the contractor trailer; dose is recorded at that location. Short term contractors and visitors pick up and return dosimeters at the rad / chem office where the dose is recorded.
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i The dosimeter sheets are delivered to a rad / chem representative at the end of each shift. The dosimeter doses are keypunched into the computer to obtain a daily update. The licensee has found the system inadequate for individuals, such as steam generator jumpers, who receive elevated doses over a short period of time; for these individuals the licensee is performing a hand tally.
No items of noncompliance were identified.
b.
External Whole body counting data for October 1981 to date were reviewed.
No body burdens indicative of an exposure greater than the 40 MPC-hour control measure were noted.
Several repeat counts on individuals were necessary to show that the control measure was not exceeded.
Station personnel who work in controlled areas are routinely whole body counted.
Contract employees who are expected to use respirators are normally whole body counted both when they begin work at the site and upon termination. Rad / Chem Technicians who conduct the whole body counts are instructed to contact a Health Physicist whenever a preliminary indication exceeds three percent of MPBB for a single isotope, or five percent additive MPBB for all isotopes.
No items of noncompliance were identified.
7.
Training The inspector attended an NGET retraining class. The training con-sisted of videotape presentations with little elaboration or oral presentation. One presentation was a recently obtained commercially produced videotape which presents basic radiation physics, radiation detection, shielding, and some comments on the nuclear controversy.
Another videotape described the proper use of protective clothing.
The retraining is acceptable.
However, oral presentation of common mistakes and recent radiological occurrences would enhance the program.
The licensee is extensively using a mockup to train persons who will I
perform work in steam generators.
Persons being trained wear protec-tive clothing and equipment that will be worn when entering the generators.
No items of noncompliance were noted.
8.
Exit Meeting The inspector met with licensee representatives (denoted in Section 1)
at the conclusion of the inspection on March 19, 1982. The inspector summariacd the scope and findings of the inspection.
In response to i
certain matters discussed by the inspector, the licensee:
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a.
Stated that formalization of the ALARA program would be considered in the near future when the program was more clearly formulated.
(Section 4)
b.
Stated that plans to establish the central tool crib are progressing, but no installation date has been set.
(Section 5)
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