IR 05000320/1983011
| ML20024F538 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/18/1983 |
| From: | Barr K, Bell J, Fasano A, Kalman G, Moslak T, Oneill B, Thonus L, Joel Wiebe NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20024F530 | List: |
| References | |
| 50-320-83-11, NUDOCS 8309090460 | |
| Download: ML20024F538 (6) | |
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O U. S. NUCLEAR REGULATORY COMMISSION 50320-830420 50320-830527 Region I 50320-830603 50320-830216 50320-830610 Report No.
50-320/83-11 50320-830616 50329-830609 Docket No.
50-320 50320-83-526 50320-830628 License No. DPR-73 Priority Category C
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Licensee:
GPU Nuclear Corporation P.O. Box 480 Middletown, Pennsylvania 17057 Facility Name: Three Mile Island Nuclear Station, Unit 2 Inspection At: Middletown, Pennsylvania Inspection Conducted: July 9 - August 8, 1983 Inspectors:
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J iebe, Senior Resident Inspector (TMI-2)
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K.1)hrr, Ragiation Spe ialist date signed Al
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Al i rt Thonus, Resident Inspector (TMI-2)
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'G. Kalman, Nuclear Engineer date signed Approved by:
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/T[////5 asano, Chief, Three Mile Island-2 Projects dhte signed
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Section, Projects Branch No. 2 Inspection Summary:
Inspection conducted on July 9 - August 8,1983 (Inspection Report Number 50-320/83-11)
Areas Inspected: Routine safety inspection conducted by site inspectors of routine plant operations; licensee event reports; qualifications of plant staff; health physics and environmental review; reactor building entries; radioactive material shipments; and reactor building inspection. The inspection involved 197 inspector-hours.
Results: No violations or deviations were identified.
8309090460 030825 PDR ADOCK 05000320 G
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6-O DETAILS 1.
Persons Contacted General Public Utilities (GPU) Nuclear Corporation B. Ballard, Manager, TMI Quality Assurance (QA) Modification / Operations J. Fornicola, Manager Quality Assurance Systems Engineering
- W. Heysek, Supervisor Audits A. Knoche, Instrumentation and Controls (I&C) Foreman-S. Levin, Director, Site Operations TMI-2
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I A. Miller, Acting Manager, Plant Operations
- R. Swartzwelder, Licensing Engineer Bechtel
- D. Lake, Manager, Recovery Operations
- denotes those present at the exit interview.
2.
Routine Plant Operations Inspections of the facility were conducted to assess compliance with general operating requirements of Technical Specification (TS) 6.8.1 in the following areas:
licensee review of selected plant parameters for abnormal trends; plant status from a maintenance / modification viewpoint including plant cleanliness and fire protection; lis.enace control of ongoing and special evolutions including control room personnel awareness of these evolutions; control of documents including log keeping practices; area radiological controls; and security plan implementation.
Random inspections of the control room during regular and back shift hours were conducted at least three times per week. The shift foreman's log and selected portions of the control room operator's log were reviewed for the period July 9 - August 8, 1983. Other logs reviewed during the inspection period included procedure in-use log and auxiliary operators daily log sheets.
Operability of components in systems required by TS or plant procedures to be available for response to emergencies was reviewed to verify that they could perform their intended functions.
Selected licensee planning meetings and shift staffing for licensed operators, non-licensed personnel, and fire brigade members were observed. The above areas were satisfactory.
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Licensee Event Reports The inspector reviewed nine Licensee Event Reports (LERs) required to be submitted in accordance with Technical Specifications (TSs) 6.9.1.8 and 6.9.1.9 (and NUREG 0161) to verify the following:. Event and cause description clearly reported event information; the required LER form was 2.
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properly completed; and adequate corrective action was specified. LERs 83-15/03L-0, 83-17/03L-0, 83-18/03L-0, 83-19/0ll-0, 83-20/03L-0, 83-21/03L-0, 83-22/03L-0, 83-25/03L-0, and 83-30/03L-0 were reviewed.
Initial screening of these events was completed to determine generic applicability, need for additional site verification, and the necessity for additional NRC management review. LERs 83-17/03L-0, 83-18/03L-0, 83-19/OlL-0, and 83-22/03L-0 have been selected for additional onsite followup.
4.
Qualifications of Plant Staff The inspector reviewed the qualifications of the principal (supervisory)
staff members of the Director, Site Operations.
TMI-2 Technical Specification (TS) 6.3.1 requires that these individuals meet the educational training and experience levels required by American National Standards Institute (ANSI) standard N18.1-1971 " Selection and Training of Personnel for Nuclear Power Plants." The TS also requires that the Director, Site Operations delegate in writing the succession to the responsibility for overall unit operations during his absence.
The principal members of the plant staff exceeded the requirements of ANSI N18.1-1971. The Director, Site Operations delegated two qualified alternates to meet the TS requirements during his absence.
5.
Routine Health Physics and Environmental Review a.
Plant Tours The NRC site radiation specialists completed routine plant inspection tours. These inspections included all radiation protection control points and selected radiologically controlled areas.
Items inspected included:
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 Use of survey meters including personnel frisking techniques
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Cleanliness and housekeeping conditions Fire protection measures.
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Licensee performance was satisfactory.
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b.
Measurement Verification
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Measurements were independently made by the inspector to verify the quality of licensee performance in the areas of radioactive material shipping, radiation and contamination surveys, and onsite environ-l mental air and water sampling and analyses. Licensee data were
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consistent with the NRC measurements.
6.
Reactor Building Entries The site staff monitored reactor building (RB) entries conducted during the inspection period. The inspection activities included review of selected documents and direct observations of reactor building entries.
The following items were verified on a sampling basis.
The RB entry was properly planned and coordinated to assure that
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task implementation, including adequate as low as is reasonably had been con (ductec;. review, personnel training, and equipment testing achievable ALARA
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Radiological precautions were planned and implemented including the
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use of a Radiation Work Permit (RWP)
Specific procedures were developed for non-routine tasks and were
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properly implemented.
Entries 231 through 267 were conducted during this inspection period.
All the areas observed were acceptable.
7.
Reactor Building Inspection The following documents were reviewed:
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General Reactor Building Entry Training G-1, Revision 10, dated March 31, 1983 AP1008,Goodyousekeeping, Revision 5,datedJuly 19, 1982
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Unit Work Instruction, 4370-3100-83-G-0001, NRC Safety and
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Cleanliness Inspection.
Two members of the NRC TMIP0 staff conducted a special followup inspection inside the reactor building on Thursday, July 14, 1983. The purpose of the inspection was to verify the progress of corrective actions addressing the violation identified during the May 5,1983 reactor building inspection by the NRC (320/83-06-08). The scope of the inspection included:
Evaluation of the effectiveness of general cleanup (housekeeping)
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and industrial safety hazard removal on the 305 ft., 347 ft., and polar crane elevations Evaluation of audibility of reactor building evacuation alarms
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Inspection of fuel canal to assess damage caused by the dropped
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source shield cover plate (320/83-07-03)
Performance of a test of the Gaitronics phone intercom systems
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Performance of independent radiation measurements
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Performance of a photo survey of selected areas and equipment
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Entry training and briefings.
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The inspector verified significant improvements in the cleanliness and general housekeeping conditions inside the reactor building.
Industrial safety conditions were enhanced by removal of trash, hoses, and cables which had previously obstructed walkways. Additionally, ropes had been installed to limit access in fall hazard areas.
Although present efforts represent a good beginning, completing the cleanup'and maintaining housekeeping and safety conditions at an acceptable level, will require a sustained effort. NRC will continue to follow licensee efforts in this area.
During the entry, the inspector observed that the reactor building evacuation alarms functioned but were difficult to hear and that one gray Gaitronics intercom phone was operational. However, he was unable to verify operability of the red Gaitronics intercom system due to radiation levels in the vicinity of that phone. Communications were evaluated as
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satisfactory. The inspector was unable to complete the assessment of damage to the fuel canal due to poor area lighting and limits of the Radiation Work Permit (RWP). The inspector took photographs and performed independent radiation measurements. The radiation measurements were in agreement with licensee readings. The NRC inspection / entry lasted one hour and eleven minutes.
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The NRC participated in and reviewed the following licensee's personnel radiation monitoring program which resulted in the following data:
Reactor Building Entry 256 (July 14, 1983)
Breathing Zone Urine Analysis Digital TLD Air Sample Individual (mrem)
(mrem)
uCi/ml(By)
H pCi/ml NRC-1 101
1.4 E-8 25.0 NRC-2
79 3.6 E-9 18.0 Further, NRC Individual #1 participated in a licensee program designed to determine the validity of determining "whole body" dose on the basis of the results of TLDs worn on a worker's thigh and to determine the correlation between the self-reading digital dosimeter results and the whole body dose as determined from the thigh dosimeters. The digital dosimeters are worn at waist height. The program is condacted on a
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bi-weekly basis by randomly selected individuals wearing supplementary personnel dosimetry. The additional TLD data from this program is listed below.
Location TLD (mrem)
Chest
Right Thigh
Left Thigh
Forehead
Back
No abnormal exposure data was identified.
8.
Radioactive Materiai Shipments The NRC site radiation specialists inspected TMI-2 radioactive material shipments during the inspection period to verify the items listed below.
The licensee had ccmplied with approved packaging and shipping
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procedures The licensee had prepared shipping papers, which certified that the
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radioactive materials were properly classified, described, packaged, and marked for transport The licensee had applied warning labels to all packages and had
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placarded vehicles The licensee had controlled the radioactive contamination and dose
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rates below the regulatory limits.
Inspector review of this arca consisted of (1) examination of shipping papers, procedures, packages, end vehicles, and (2) performance of radiation and contamination surveys of the shipments which were inspected. All of the items examined were acceptable.
9.
Inspector Follow Items Inspector follow items are inspector concerns or perceived weaknesses in the licensee's conduct of operation (hardware or programmatic) that could lead to violations if left uncorrected. An inspector follow item is
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addressed in paragraph 7.
10. Exit Interview On August 8, 1983, a meeting was held with licensee representatives (denoted in paragraph 1) to discuss the inspection scope and findings.
At no time during this inspection was written material provided to the licensee by the TMIP0 onsite staff, except for procedure reviews pursuant
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to TMI-2 Technical Specification 6.8.2.
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