IR 05000320/1982013
| ML20028B849 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/22/1982 |
| From: | Barr K, Boyd R, Fasano A, Oneill B, Thonus L, Joel Wiebe NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028B847 | List: |
| References | |
| 50-320-82-13, NUDOCS 8212070111 | |
| Download: ML20028B849 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION 50320-820915
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- Region I Report No.
504320/8_2-13
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Docket No.
50-320'
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Li cense - No.~. DPR-73 "
Priority Category C
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Licensee:
GPU Nuclear Corporation P.O. Box 480
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Middletown,_ Pennsylvania 17057 m
Facility Name: Three Mile Island Nuclear Sta' tion, Unit 2 Inspection At: Middletown, Pennsylvania
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inspection Conducted:,0ctober 10 - November 6_, 1982 Inspectors:
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ll//I/PS-JgWiebe, Senior Resident Inspector (THI-2)
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K.13arr, Radiation Specialist date signed NAme-
M B. O'tjeill,/ Rad ation Specialist date signed b I 'W-
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L. Thonus, Resident Inspector (TMI-2)
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Accompanied by:
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//[///cfd froyd, Pydiation Specialist (Intern)
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///2,2/f7 Approved by:
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A. Fasano, Chief, Three Mile Island Section ddte signed Projects Branch No. 2 Inspection Summary:
Insaection conducted on October 10 - November 6,1982 (Inspection Report Num)er 50-320/82-13)
Areas Inspected: Routine safety inspction conducted by site inspectors of licensee action on previous inspection findings; routine plant operations; routine health physics and environmental areas; reactor building entries; radioactive material shipments; licensee event reports; and Once Through Steam Generator level indication. The inspection involved 115 inspector-hours.
Results:
No violations were identified.
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8212070111 821123 PDRADOCK05000g G
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DETAILS
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Persons Contacted General Public Utilities (GPU) Nuclear Corporation
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- S. Chaplin, Licensing Engineer
- J. Chwastyk, Manager, Plant Operations J. Flanigan, Radiological Engineering Manager
l W. Griffith, Radiological Controls Foreman J. Hildebrand, Manager, Radiological Controls.
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- L. King, Director, Site Operations
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- G. Kunder, Acting Technical Specification Compliance Supervisor
H. McGovern, Shift Supervisor A. Miller, Technical Assistant
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- E. Mitchell, Operations Quality Assurance Monitor
- R. Neidig, Jr., Senior Cormiunications Representative J. Renshaw, Manager, Radiological Field Operations W. Zewe, Radwaste Supervisor (TMI-1)
I Other licensee personnel were also interviewed.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Inspector Follow Item (320/79-17-07):
Inadvertent transfer of water from Three Mile Island Unit 2 (TMI-2) to Three Mile Island Unit 1
(THI-1). The interconnecting piping (two places) between the TMI-2 Auxiliary Building sump and the TMI-1 radwaste system is isolated with locked closed valves.
Identification of other connections between TMI-1 and TMI-2, and the resulting corrective actions is being followed as a
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TMI-1 restart item (289/82-BC-16). The inspector had no further questions.
3.
Routine Plant Operations
Inspections of the facility were conducted to assess compliance with general operating requirements of TS 6.8.1 in the following areas:
licensee review of selected plant parameters for abnormal trends; plant l
status from a maintenance / modification viewpoint including plant cleanliness; licensee control of ongoing and special evolutions including control room personnel awareness of these evolutions; control of documents including log keeping practices; and area radiological controls.
Random inspections of the control room during regular and back shift hours were conducted at least three times per week. The selected sections of the shift foreman's log and control room operator's icg were reviewed for the period October 10 - November 6, 1982.
Selected sections of other control room daily logs were reviewed for tt.e period from
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midnight of the day of review to the time of review.
Inspections of areas outside the control room occurred on October 12, 15, 21, 27, and November 2 and 3, 1982.
Selected licensee planning meetings were observed.
No violations were identified.
4.
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. Observations included:
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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
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Cleanliness and housekeeping conditions
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Fire protection measures.
No violations were identified.
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Measurement Verification Measurements were independently made by the inspector to verify the quality of licensee performance in the following areas:
Radioactive material shipping
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Radiation and contamination surveys
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Onsite environmental air and water sampling and analyses.
No violations were identified.
5.
Reactor Building Entrieq a.
The site staff monitored reactor building (RB) entries conducted during the inspection period to verify the following en a sampling
basis:
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The RB entry was properly planned and coordinated for effective
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task implementation including adequate as low as is reasonably achievable (ALARA) review, personnel training, and equipment testing.
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Proper radiological precautions were planned and implemented,
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including the use of a-Radiation Work Permit (RWP).
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Specific procedures were developed for unique tasks and were
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properly implemented.
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b.
The site staff reviewed selected documents, applicable procedures, and RWPs concerning these entries.
Entries 104 through 118 were conducted during this inspection period.
No violations were identified.
6.
Radioactive Material Shipments
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The NRC site radiation specialists inspected all radioactive
material shipments during the inspection period to verify the items
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listed below.
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Licensee had complied with approved packaging and shipping procedures.
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Licensee had prepared shipping papers, which certified that the
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radioactive materials were properly classified, described, packaged, and marked for transport.
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Licensee had applied warning labels to all packages and had placarded vehicles.
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Licensee had controlled the radioactive contamination and dose rates below the regulatory limits.
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Inspector review of this area consisted of: examination of shipping
. papers, procedures, packages, and vehicles; and performance of radiation and contamination surveys of each shipment.
During this period, twenty radioactive material shipments were made by the license.
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b.
EPICOR II Prefilter Shipments The following prefilters were shipped from TM1 to the Idaho National Engineering Laboratory (INEL) in Scoville, Idaho.
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PF-7 on October 21, 1982 PF-8 on Octcher 23, 1982 PF-9 on October 28, 1982 PF-45 on November 2.1982 PF-46 on November 3, 1982 7.
Licensee Event Reports The inspector reviewed Licensee Event Reports (LERs) required to be submitted in accordance with Technical Specifications (TS) 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
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properly completed; and adequute corrective action was specified.
i Initial screening of these events was completed to determine generic
applicability, need for additional site verification, and the necessity for additional NRC management review.
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LER 82-28/03L-0, dated October 22, 1982, Auxiliary Building ventilation exhaust flow below TS 3.9.12 limits, was reviewed.
No violations were identified.
8.
Once Through Steam Generator Level-Instrumentation a.
Background The installed Once Through Steam Generator (OTS nitoring
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instruments became inoperable as a result of the
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accident. The instruments were not repairable becausa of the high radiation levels and approximately 7 feet of water in the Reactor Building (RB) basement. A post accident OTSG level monitoring system was installed on the feedwater lines just outside the RB penetrations. Technical Specification 3.3.3.6 requires that one post-accident OTSG level instrument be operable for each 0TSG.
b.
Review On October 21, 1982, the licensee identified that the post accident
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OTSG level instruments were inoperable. This event was reported to the NRC pursuant to Technical Specification 6.9.1.8.(b).
The licensee investigation revealed that valves GRV-7A and 7B were closed, which isolated the level instruments from the "A" and "B" 0TSGs, respectively. The valves were opened and the instruments were restored to an operable status. This item remains unresolved pending completion of the licensee's investigation of the cause of the event and development of corrective actiras (320/82-13-01).
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Unresolved Items Unresolved items are findings about which more information is needed to ascertain whether it is a violation, a deviation, or acceptable.
An unresolved item is addressed in paragraph 8.
10.
Exit Interview On November 9, 1982, a meeting was held with licensee representatives (denoted in paragraph 1) to discuss the inspection scope and findings.
Other NRC personnel, other than the reporting inspectors, present at the exit interview are noted below.
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A. Fasano, Chief, Three Mile Island Section t