IR 05000320/1981022
| ML20040C725 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/07/1982 |
| From: | Fasano A, Oneill B, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20040C707 | List: |
| References | |
| 50-320-81-22, NUDOCS 8201290184 | |
| Download: ML20040C725 (6) | |
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e U.S. NUCLEAR REGULATORY COMMISSION OFFICE 0F INSPECTION AND ENFORCEMENT Region I
Report No.
50-320/81-22
~ Docket No.
50-320
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License No. DPR-73 Priority
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Category C
Licensee :
General Public Utiliti_es Nuclear Corporation P.O. Box 480 Middletown, Pennsylvania 170_57 Facility Name: Three Mi_le Island Nuclear Station, Unit 2 Inspection at: Middletown, Pennsylvania Inspection conducted: December 17-22, 1981 Inspector:
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dia[ionSpecialist d td signed Reviewed by:
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/![/72 M. Shanbaky, Senior RMiiation Specialist date' signed
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Approved by:
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'A. F@ano, Chief, Three Mile Island Section, d'atd signed Projects Branch No. 2
_ Inspection Su_mmary:
Inspection on December 17-22,1_981 (Inspection Report No. 50-320/81-22)
Areas Inspected: Special safety inspection by one onsite inspector of events concerning an unscheduled reactor building entry on September 3,1981.
The inspection involved 32 inspector-hours.
Resul ts : Of the one area reviewed, one apparent item of noncompliance was-identifled (failure to conduct a radiation survey, paragraph 6).
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Details 1.
Persons Contacted General Public Utilities (GPU) Nuclear Corporation
- C. Adams, Quality Assurance, Audit M. Beers, Quality Assurance, Audit
- S. Chaplin, Licensing Engineer
- J. Chwastyk, Manager Plant Operations
- B. Della Loggia, Radiological Engineer
- J. Fidler, GPU Nuclear Media Representative
- J. Flanigan, Manager Radiological Engineering E. Hemmila, Shift Supervisor W. Heysek, Quality Assurance, Audit
- J. Hilderbrand, Manager Radiological Health '
- L. King, Plant Operations Director
- J. Marsden, Quality Assurance, Engineer
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- M. Pastor, Recovery Programs, Operations and Construction Director J. Patterson, Radiation Control Technician
- J. Renshaw, Manager, Radiation Control Field Operations
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- P. Ruhter, Manager Radiological Technical Support
- S. Smith, Licensing Engineer Bechtel Corporation J. Gilbert, Assistant Entry Supervisor
- D. Machiela, Entry Coordinator
- T. Morris, Entry Supervisor J. Thiesing, Project Manager Other licensee personnel were also interviewed.
- denotes those present at the exit interview 2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved (320/81-17-02): NRC to complete review of unscheduled reactor building entry on September 3,1981.
See paragraphs 3, 4, 5, and 6.
3.
D_i scussion The unscheduled reactor building (RB) entry, which occurred on September 3,1981, was detailed in Inspection Report 50-320/81-17, dated December 11, 1981.
In that report it was stated "...the inspector reviewed the circumstances and the documentation of the unscheduled RB entry which was made at 4:29 AM on Thursday, September 3,1981.
The one man entry was made to visually ascertain the RB sump / basement water level in the RB after an instrument, a manometer which is normally used to measure the elevation of the water, began giving erratic indication.
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k-3-The inspector interviewed the licensee's entry personnel and personnel that supported the entry.
The inspector reviewed
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RWP No.1866, dated September 3,1981 which described the scope of the task to be performed during the entry.
The inspector noted that the RWP [ Radiation Work. Permit] was specific as to the [only]
work to be performed in that item 5 [of the RWP] stated ' visual inspection of water level and positioning of CCTV [ closed circuit television] camera'.
Item 13 of the RWP required an HP (health physics technician) escort for the individual making the. entry.
The inspector also reviewed the following documents concerning the unscheduled entry:
Letter to Mr. M. K. Pastor, GPU Service Corporation, dated
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September 8,1981, from Mr. R. Rider, Project Engineer, Bechtel Northern Corporation.
Radiation Work Permit No.1967, ' Anteroom and Airlock,' dated
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September 3,1981.
Radiological Survey Form, dated September 4,1981, ' Anteroom'
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(SIudge Samp1e Tool).
TMI Unit-2 Radiological Deficiency Report No. 81-0061, dated
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September 3,1981.
Unit 2 Radiological Control Log.
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From discussions with involved personnel and the documentation review, the inspector determined that during the unscheduled RB-entry on Septembe 3,1981, two failures to follow RWP requirements occurred.
Removal of the sludge. sample tool from PB staging area, 305'
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elevation, to the anteroom No HP escort during the entry
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The inspector noted that failure to properly follow RWP require-ments was identified by licensee personnel, in that at 6:30 AM on September 3,1981 a Radiological Deficiency Report (RDR) (No. 81-0061)
describing the deficiency had been filed by the duty Radiological Control Foreman and approved by the Radiological Control Department Manager.
The inspector reviewed the corrective actions documented on the RDR, dated September 17, 1981, and discussed the seriousness of failure to follow RWP requirements during a special meeting with licensee staff concerning RB entries on October 2,1981.
Corrective actions included involved perscnnel counseling on following RWP requirements, HP Foreman review of future R8 entry scenarios for an understanding of specific tasks, and one final discussion on expected
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-4-actions prior to [the] entry...." This apparent item of non-compliance (320/81-17-01) was previously discussed in NRC Inspection Report 50-320/81-17.
However, NRC review of the unscheduled entry and other related licensee actions was not completed at the close of that inspection period.
This area was unresolved pending completion of that review (320/81-17-02).
During this inspection period, the inspector completed the interviews with involved licensee personnel.
The inspector also reviewed additional documents concerning the unscheduled reactor building entry.
Control Room Operators Log for September 2,1981, and
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Septem5er 3,1981 Documentation of Notification and Briefings conducted
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September 3,1981 Procedure 2104-4.55, Revision 4, Reactor Building Entry and
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Pre-Decon, used and dated September 3,1981 (work copy used in the reactor building command center)
Procedure 2104-4.91, Revision 4, Reactor Building Purge Using-
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the Modifled Purge System
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Unit 2, Air Sample Report #68005, dated September 3,1981 (reactor building air sample)
4.
Sequence of Events Based on-interviews and document review, the inspector determined the following sequence of events:
September 2, 1981 (7:00 PM) - Unit 2 NRC Senior Resident
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Inspector was notified by the licensee that the manometer used to measure the water level in the reactor building sump indicated questionable measurements.
September 2,1981 (sl0:00 PM) - Unit 2 manage;aent members
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directed that a reactor building entry be accomplished, as soon as possible, to visually ascertain sump water level.
September 2,1981 (s10:00 PM) to September 3,1981 (s4:30 AM) -
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Preparations were in progress for reactor building entry.
However, no reactor building purge was initiated.
NRC site staff was not notified of pending personnel entry into the reactor building as was established for all previous entrie _.
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-5-September 3,1981 (s2:00 AM) - Problem with sump level indication
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was determined to be faulty manometer. Members of reactor building entry command center were aware that no emergency existed.
. September _3,1981 (2 :00-4 :30 AM) - Personnel in command center
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decided to proceed with the reactor building entry.
. September 3, 1981 (4:27-4:38 AM) - Individual performed tasks
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in reactor building to include removal of sludge sample tool.
No radiatien survey of sludge sample tool was-performed.
No written record of the removal of the sludge sample tool was entered in the command center or procedure log.
This was subsequently documented in licensee correspondence.
Control of Airborne _ Radioactive Concentrations The inspector reviewec licensee records of the reactor building entry, and braathing zone air sample results for the
individual entering the reactor building on September 3,1981.
The inspector verified that the airborne concentrations in the reactor building were at 7 to 8 MPC (Maximum Permissible s
Concentration) as established in 10 CFR 20.103.
Although respiratory protection equipment was used, a reactor building purge was not performed to minimize the MPC air prior to and during the reactor building entry.
During the exit interview on December 22, 1981, the inspector discussed with licensee staff members the need for appropriate use of engineering controls to limit airborne radioactive concentrations as a -precautionary procedure.
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Radiological Surveys From discussions with licensee personnel, the inspector determined that during the reactor building entry on September 3,1981,' a sludge sample tool was removed from the building without performing a radiation survey, A subsequent survey of the equipment indicated 10. mR/hr gamma, and 160 mrad /hr beta at contact.
Failure to perform a radiation survey of the sludge sample tool prior to its removal from the reactor building constitutes an apparent item of noncompliance with the requirements as defined in 10 CFR 20.201(b) (320/81-22-01).
The inspector also identified several weaknesses in Station Operating Procedure 2104-4.55, Revision 4, (now Revision 5), Reactor Building Entry and Pre-Decon.
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-6-Weaknesses included:
No requirement to purge the reactor building during personnel
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entries to minimize airborne radioactive concentrations.
No casualty criteria were planned or incorporated into the
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entry procedure.
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Procedure did not address minimum radiological precau'tions to be exercised based on the unique radiation environment of the Unit 2 reactor building, e.g. High Radiation Area.
The NRC onsite staff is presently discussing with licensee repre-sentatives the need to upgrade the reactor building entry procedure prior to approval of the reactor building Decontamination Experiment which was tentatively scheduled for the end of January 1982.
7.
Interviews with. Licensee Quality Assurance Personnel On December 22, 1981, the inspector met with licensee quality assurance personnel and reviewed the licensee's program for audit of reactor building entries.
The inspector emphasized the importance of the pending Decontamination Experiment and questioned quality assurance involvement in this area.
Licensee representatives stated that the quality assurance staff plans to conduct a comprehensive audit of the reactor building entry program during January 1982.
The inspector had no further comments in this area.
8.
E_x_it Interview The inspector met with licensee representatives (denoted in paragraph 1),
and with representatives of the NRC TMI Program Office at the conclusion of the inspection on December 22, 1981.
The inspector summarized the inspection findings, and indicated that this inspection completed the review of the September 3,1981, unscheduled reactor building entry. Accordingly, unresolved item 320/81-17-02 is closed.
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