IR 05000320/1981021
| ML20039E426 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/21/1981 |
| From: | Conte R, Fasano A, Oneill B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20039E424 | List: |
| References | |
| 50-320-81-21, NUDOCS 8201070281 | |
| Download: ML20039E426 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-320/81-21
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Docket No.
50-320
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License No.
0PR-73 Priority
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Category C
Licensee :
Metropolitan Edison Company P.O. Bo_x 480 Middletown, Pennsylvania 17057 Facility Name: Three Mile Island Nuclear Station, Unit 2 Inspection at: Middletown, Pennsylvania
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Inspection conducted: November 15 - December 12, 1981 Inspectors :
bdV lh L) $/
R. Conte, Senior Resident Inspector (TMI-2)
date signed Jb)
l B.' 0' f ' ill,/had 'ation Specialist date signed Approved by:
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A. Fasano, Chief, Three Mile Island Section, date signed Projects Branch No. 2 Inspection Suarnary:
Inspection on November 15 - December 12,1981 (Inspection Report No. 50-320/81-21)
Areas Inspected: Routine safety inspection by onsite inspectors of plant operations; radiological and environmental protection; reactor building (RB)
entries; radioactive material shipments; and emergency drills.
The inspection involved 111 inspector-hours.
Resul ts : No items of noncompliance were identified.
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I DETAXLS 1.
Persons ' Co_n_tacted Genera? Public Utilities Nuclear Group
- S. Chaplin, Licesning Engineer
- J. Chwastyk, Nuclear Plant Operations Manager
- G. Giangi, Emergency Planning
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L. King,' Acting Director Site Operations TMI-2
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A. Miller, Technical Analyst
- denotes those present at'the exit interview
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Routine Plant Operations Reviews
_ The inspector, on a periodic basis, obtained information on plant conditions, reviewed selected plant parameters for abnormal trends, ascertained plant status from a maintenance / modification viewpoint, and verified logkeeping practices were in accordance with administrative
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control s.
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The inspector made random inspections of the control room during the regular and back-shift hours, discussed operations with control room personnel, reviewed selected control room logs and records, and observed selected licensee plan-of-the-day meetings.
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No items of noncompliance were identified.
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Routine Health Physics and Envirc ' ental Review i
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Plant Tours The onsite radiation specialists completed routine plant inspection tours.
These inspections included all control l
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points and selected radiologically controlled areas.
Obser-
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- Access control to radiologically controlled areas;
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Adherence to Radiation Work Permit (RWP) requirements;
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Proper use of respiratory protection equipment;
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Adherence to radiation protection procedures;
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Use of survey meters including personnel frisking techniques; Cleanliness and housekeeping conditions; and,
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Fire protection measures.
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Measurement Verifications tieasurements were independently obtained by the inspector to verify the quality of licensee performance in the following selected areas:
Radioactive material shipping;
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Radiological control, radiation and contamination surveys;
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Onsite environmental air and water samples and analysis.
No items of noncompliance were identified.
4.
feactor Building Entries a.
The onsite staff monitored reactor building (RB) entries conducted during the inspection period to verify the following on a sampling basis:
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The RB entry was properly planned and coordinated for effective task implementation including adequate as low as is reasbnably achievable (ALARA) review, personnel training, and equipment testing; Proper radiological precautions were planned and implemented
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including the use of a RWP; and, Specific procedures were developed for unique tasks and
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properly implemented.
b.
The onsite staff attended RB entry status meetings, reviewed selected documents, applicable procedura, and RWP's concerning these entries.
Several discussions occ ed with licensee representatives concerning plans for the seactor building decontamination experiment.
Entry Nos. 21, 22, 23 and 24 were conducted on November 17, 20, December 3 and 9,1981, respectively.
Licensee continued assessment of polar crane damage, and visual / radiological surveys and equipment installation to support the gross decontamination experiment (tentatively scheduled for mid January 1982).
No items of noncompliance were identified.
Radioactive Material Shipments a.
The onsite radiation specialists inspected all radioactive material shipments during the inspection period to verify the below items:
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-4-Licensee had complied with approved packaging and shipping
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procedures; Licensee had prepared shipping papers, which certified
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that the radioactive materials were properly classified, described, packaged, and marked for transport;
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Licensee had applied warning labels to all packages and placarded vehicles; and, Licensee controlled the radioactive contamination and
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dose rates below the regulatory limits.
b.
Inspector review in this area consisted of: examination of shipping papers, procedures, packages, and vehicles; and performance of radiation and contamination surveys for each shi pment.
During this period, 26 radioactive material shipments were made by the licensee.
No items of noncompliance were identified.
6.
Emergency Drills a.
The NRC onsite staff participated in two TMI-2 emergency drills conducted during this period to verify the below listed items on a sampling basis:
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Licensee organizational response was coordinated, orderly, and timely; Immediate and supplemental actions of the applicable
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emergency procedures were properly implemented; Health physics practices, radiological dose assessment,
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and utilization of emergency response kits for radiological emergencies were adequate;
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Internal communication systems and techniques were adequate;
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Licensee use of " drill observers" to evaluate " drill participant" response and drill observer connents were adequate; and,
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Corrective actions were initiated by the licensee to correct identified deficiencies.
Also, the NRC onsite staff tested the implementation of the NRC Onsite Event Response Plan.
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Selected sections of the following documents were reviewed, in preparation, for and during the observation of these drills:
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Emergency Plan Implementing Procedure (EPIP) 1054.1, Revision 1, November 25, 1981, Unusual Event; EPIP 1054.2, Revision 1, December 3,1981, Alert;
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EPIP 1054.3, Revision 1, December 3,1981, Site Emergency;
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EPIP 1054.4, Revision 1, December 3,1981, General Emergency; EPIP 1054.6, Revision 1, December 1,1981, Additional
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Assistance and Notification; and, EPIP 1054.7, Revision 1, December 9,1981, Offsite Dose
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Projections.
The scenario for the drill on December 1,1981 was a simulated general emergency involving high reactor coolant system (RCS)
leakage and a dropped EPICOR II resin liner with subsequent'
offsite radiological releases.
The scenario for the drill on December 10, 1981, was a simulated site emergency involving high RCS leakage and a fire at a radwaste storage area with subsequent offsite radiological releases.
Observations of emergency activities were made at the Emergency Offsite Facility (TMI Observation Center), Emergency Control Center (Control Room), Radiological Assessment Center (Control Room), Technical Support Center (Control Building - room adjacent to Control Room), Operations Support Center (TMI-2 Health Physics Office - Service Building), Scene (Radwaste Storage Area at South End of the Owner Controlled area).
For the December 10, 1981 drill, two staff members of the NRC TMI Program Office (Bethesda office) made observations at the Emergency Offsite Facility and on the island with the Onsite Monitoring Team.
c.
The inspectors attended a post-drill critique, during which licensee observers and participants discussed the drill and highlighted areas where improvement may be necessary or desi rable.
The inspector noted that the licensee's observer staff adequately audited the emergency organization's performance and highlighted significant items.
The inspector also noted that the observer and participant comments were being documented for followup.
Based on an evaluation of the findings of the licensee observers, licensee participants, and the NRC observers, the inspector
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concluded that although there were items identified which
f e e O-6-exhibited a potential for a degraded response, the licensee demonstrated the ability to adequately implement the existing Emergency Plan.
The inspector had no further comments in this area.
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7.
Exit Interview On December 15, 1981, a meeting was held with licensee representatives (denoted in paragraph 1) to discuss the inspection scope and findings.
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