IR 05000320/1986002
| ML20202G151 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/07/1986 |
| From: | Bell J, Dan Collins, Cook R, Cowgill C, Moslak T, Myers L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20202G138 | List: |
| References | |
| 50-320-86-02, 50-320-86-2, NUDOCS 8604140288 | |
| Download: ML20202G151 (8) | |
Text
-
!
)
U. S. NUCLEAR REGULATORY COMMISSION
.-
Report No.
50-320/86-02 Docket No. 50-320 License No. DPR-73 Priority
--
Category C
,
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:
February 1,1986 - February 28, 1986 dWk.
4 // [M Inspectors:
R.'CVok, e 'or R id n Inspector (TMI-2)
date signed s
-
% \\ /TC T. Moslak, Resid~ent spector (TMI-2)
d'a'te 4igned
- \\
Ob
'
d. Be' 1, Senidr Radiation Specialist date(signed amWQ W rNu D. Collins', Radiation Specialist date signed L Crkuw >
</h6 L".' Myer1, RadiaR. ion Specialist ddte signed Approved By:
[ b / d JT Y
%
C.Qwgi'yChief,TMI-2ProjectSection date signed Inspection Summary:
Areas Inspected:
Routine safety inspection of plant operations (long term shutdown) including review of licensee action on previously identified inspection findings; defueling operations; reactor building entries by NRC inspectors; off site visit to inspect rail shipping cask; health physics and environmental reviews; radiological shipments; independent radiation measurements; licensee reactor building entries; and records associated with the radiological controls program.
Results: No violations were identified.
G PDR l
.-
.
.-
DETAILS 1.0 Ongoing Recovery Operations Routine Plant Operations On a periodic basis, resident inspectors obtained information on plant conditions, reviewed selected plant parameters for abnormal trends, ascertained plant status from a maintenance / modification standpoint, and assessed plant operations to determine compliance with applicable procedures and Unit Work Instructions.
During the regular and backshift hours, resident inspectors made random visits to the Control Room and Defueling Coordination Center, observed defueling operations and support tasks, reviewed logs, and attended selected licensee plan of the day meetings. Logs reviewed included the Control Room Opr.rators' Log, Fuel Handling Senior Reactor Operators' Log, Submerged Demineralizer System (SDS) Operations Log, Group Radiological Controls Supervisor's Log, and Shift Foremen's Log. Plant cleanliness, control room conduct, and the control of switching and tagging was also assessed during plant inspections.
Operability of components in systems required to be available for response to emergencies was reviewed to verify that they could perform their intended functions. Such systems included Emergency Diesel Generators, Fire Protection Systems, Effluent Monitoring Systems, and Reactor Coolant Processing, Boration, and Level Control Systems.
No violations were identified.
2.0 Licensee Action on Previous Inspection Findings (Closed) Inspector Follow Item 50-320/85-21-04: " Organization of Waste Management Section not described by Procedure."
On August 12, 1985, Technical Specification Change, Revision 11, to 6.2.2
" Organization Plan TMI-2" was approved. A position of Manager, Waste Management was created who reports directly to the Site Operations Director. On January 28, 1986, Administration Procedure 4230-ADM-1000.01, "TMI Unit 2 Waste Management Organization, Responsibility and Authority," was issued which describes the Waste Management Section. The inspector determined that the procedure adequately described the organization, delineated responsibilities and defined authority of the Waste Management Section.
(0 pen) Inspector Follow Item (320/85-21-05): Evaluate unmonitered release pathways and update the Semi Annual Radiological Effluent Palease Report when evaluation is complete.
The licensee completed the evaluation for the unmonitored release pathway from the Contaminated Drain Tanks to the atmosphere which existed during
)
i ani after the accident.
The evaluation was reported in the Semi Annual
'
Radiological Effluent Release Report for July 1,1985 through December 31, 1985. The licensee estimated that, conservatively, the I-131
!
l
_
c-
-
.
.
available for release was 1.75x10 3 Ci which was insignificant compared to the reported released value of 14.4 Ci during and after the accident.
This item remains open pending evaluation of ten potential unmonitored release pathways identified by the licensee.
3.0 Defueling Operations During the reporting period the licensee continued defueling operations.
At the end of the reporting period 18 defueling canisters had been transferred from the reactor vessel to the spent fuel pool storage racks.
The total weight of fuel debris and structural material transferred out of the reactor vessel to date is about 16,000 pounds.
The estimated total weight of fuel debris and structural materials originally in the reactor vessel after the accident was 308,000 pounds. The most efficient means of transferring fuel debris is by use of a hydraulically operated spade bucket discharging directly into a fuel canister. Because of the poor visibility, the licensee uses a three axis coordinate technique at the fuel handling bridge to guide the fuel handling tool over the canister. This has proven an effective way of compensating for poor visibility in the vessel.
,
Visibility in the reactor vessel continues to be poor because of biological growths. The organic growths are composed of algae, fungi and bacteria in suspension with aerobic and anerobic organisms attached to metal surfaces including the lower head.
The organic growths have progressed to a point where a self-sustaining community exists in the reactor vessel. The licensee is continuing to evaluate various techniques to stifle the biological growth and have retained consultants in the field to assist in developing a viable solution which will not cause any jeopardy to existing systems or personnel safety.
The licensee has developed a Temporary Reactor Vessel Filtration System consisting of a small circulating pump and diatomaceous earth filter in an attempt to remove the biological organisms and fines from the reactor coolant. The material captured on the filter is then subsequently discharged to a 55 gallon drum for further disposal. The temporary filtration system does appear to cleanup the water and is presently the only functional cleanup system available to the reactor coolant system.
The inspectors will continue to follow this area.
On February 24, 1986, the licensee reorganized the Unit 2 Project organizational structure to incorporate a newly formed Defueling Group reporting directly to the Director of THI-2.
The new group is managed by a Defueling Manager and consists of a Defueling Operations Section, a
,
Defueling Engineering Section and a Defueling Support Section. The new group was formed to place management emphasis on achieving improved defueling productivity and effectiveness in both the defueling operations and the support activities required for expeditious defueling. At present the Deputy Director of TMI-2 is the Acting Manager of the DeQeling Group.
l l
I
.
.
- -
- -
-
-
-
-
- -
-
- - - - - - - - - - - - - - - - -
,
"
.
4.0 Reactor Building Entries by NRC Inspectors
'
A radiation specialist entered the reactor building (RB) on February 8, 1986, to assess radiological and industrial safety conditions, especially those associated with the Temporary Reactor Coolant Filtration System (TRCFS) and its startup. The TRCFS was developed as an interim measure to help improve visibility in the turbid water in the reactor vessel and thereby improve defueling efficiency.
A number of problems developed prior to and during the entry that delayed startup of the TRCFS until after the inspector had left the reactor building because of limitations on work time in a respirator. Startup of the TRCFS was monitored by the inspector in the licensee's Coordination Center by means of the closed circuit television system.
The pre-entry briefing of the team was generally satisfactory; however, two problems were noted. An unexpected delay was experienced while the defueling crews were instructed on operation of the TRCFS. This was necessary since the crews had apparently received only minimal training on the mockup TRCFS.
(Some of the crew members did have experience operating other filter systems similar to the TRCFS.) Also, the radiological engineer was not made aware of the nature of a change in the method used to brace the TRCFS lead blanket shield racks. This resulted in some delay on the defueling platform while an inspection was made of the racks to determine the adequacy of the bracing.
The team brought an AMS-3 air monitor into the RB to replace a defective unit on the defueling platform. The entire team entered the RB and waited while the service crane skip pan was positioned to move the AMS-3 from the 305' level to the defueling platform. The radiological controls technician directed those crew members not involved with the crane to a lower dose rate area to wait.
Upon reaching the defueling platform, it was observed that the positioning of the TRCFS hoses on the platform could present a trip hazard, the AMS-3 could not be assembled so as to function properly, the lead shielding at the bottom of the TRCFS canister was not in place, and a section of guard rail separating the uncovered end of the fuel transfer canal from the defueling platform was missing. The licensee staff exhibited considerable resourcefulness, vigor and team work in correcting these problems.
The TRCFS was successfully started on February 8,1986. From a radiological standpoint, the unit generally functioned as predicted by the licensee.
A radiation specialist inspector and the Senior Resident Inspector made an entry into the RB on February 24, 1986 to assess radiological and housekeeping conditions in the RB. The inspectors determined that the trash compactor installed on the 347' elevation had been provided with l
.
,
I
.
supplemental ventilation to assure continuous airflow into the compaction chamber and the. cleanliness of the working areas was acceptable. Storage of radioactive waste (i.e. high radiation waste, transuranic and high strontium waste from the defueling platform, and low level waste storage)
was acceptable and had not been permitted to accumulate to unacceptable levels..The inspectors had expressed a concern to the licensee with respect to accumulation and hazards associated with the increased fire loading. The licensee plans to reduce fire loading in the building by removing waste to the interim storage facility in steel LSA boxes until high-integrity containers are approved for use at the burial facility and -
Class B waste can be shipped without stabilization. The inspector found that the handling of waste being generated on the work platform was acceptable.
The. inspectors found no accumulations of waste elsewhere in the RB or any
. place where trash or construction debris could interfere with safe work in the RB. Radiation levels at selected waiting areas were acceptably low and the protective clothing prescribed was adequate. The inspectors examined the physical conditions inside the upper levels of the "A" D-ring, especially around the upper portions of the "A" 0TSG. Conditions were acceptable.
The inspector found the available radiological controls instrumentation to be calibrated and appropriate.
No violations were identified.
-5.0 Off Site Visit to Inspect Shipping Cask On February 5 and 6,1986, an inspector visited the assembly and test site being used by the Department of Energy (D0E), vendor for the railcar-mounted fuel debris shipping cask. The site, located at Richland, Washington, was prepared to assist the vendor and the licensee in setting up and loading the shipping cask under realistic conditions.
Licensee staff was able to perform all the motions required for preparing the rail cask for shipment. The test procedures in use were appropriately prepared and sufficiently detailed to enable a reasonable test of the operation. The licensee staff included persons from waste shipping, radiological engineering, radiological controls, maintenance, crane operators, site engineering and quality assurance. The length of time available and the location made for an appropriate training facility provided a good demonstration of the teamwork which will be required to make the project proceed successfully. The vendor, the licensee and DOE have identified items needing repair / modification, and have engaged in negotiations to resolve the differences.
No violations were identifie ~
p
<
,
t
<
-
-j l-t
'
6.0 Health Physics and Environmental Review j.
a.
P1 ant-Tours
'
!
The TMI-2 NRC site radiation specialists performed plant inspection tours and reviewed specific radiological controls program elements.
Included. areas were all radiological controls check points, selected radiologically controlled areas within the protected areas, such as the Auxiliary, Reactor and Fuel. Handling Buildings; and
- radiologically controlled areas in the owner-controlled area, such
'
as the paint shed, laundry-respirator facility and solid waste
- -
storage facility.
Among the items inspected were:
Access controls utilized for radiologically controlled areas
--
i Personnel adherence to Radiation Work Pennit (RWP) requirements
'
--
Appropriate use and storage of respiratory protection equipment
---
,
i l
Maintenance, inspection and use of radiation instruments
--
,
Adherence to radiological controls procedures l
--
Cleanliness and housekeeping
--
..
Fire protection
--
Appropriate air sampling techniques, devices and calculations;
--
and Proper record-keeping for dosimetry.
--
The inspectors performed backshift tours at irregular times during the month. The inspectors reviewed the application of radiological controls within the plant, and the solid waste storage facility.
The inspectors reviewed the logbouks maintained by Radiological Controls in the foreman's office and in the Reactor Building Entry Coordination Center. These logbooks were frequently examined by departmental management. The inspectors noted the entries were appropriate and reflected conditions in the plant.
b.
Radiological Shipments The inspectors examined two selected shipments of vaste and
'
radioactive materials from the site on February 21, 1986. The shipments were evaluated for compliance with DOT and NRC requirements regarding:
External package and vehicle contamination
--
External package and vehicle radiation levels
- - -
,
,
..._.,_.....-,m.-,..,.,,---,_._.r,
_.., _ - -.,..,
.,.
--...-..,,....,,,,,.----,,..._mm...,..
_ _. _.,,.,
.
..
.. - -.
..
~
--
>
.,
..
Verification of licenses allowing receipt and possession of the
--
material shipped Labels placed on packages, placards offered to the carrier l>
--
Proper shipping papers, certifications regarding
--
classifications, package marking for transport.
No violations were noted.
c.
Measurement Verification-l The inspectors made independent measurements of radiation and
~
contamination levels using NRC radiological instrumentation. These measurements were performed as verification of licensee performance in shipping surveys, onsite environmental air analyses, and area surveys for radiation and contamination.
No violations were identified.
d.
Reactor Building Entries The inspector monitored the conduct of reactor building ( sB) entries during the month. The areas inspected included review of documents and direct observations of RB entry activities. The following were verified on a sampling basis:
The RB entry was properly planned and coordinated to assure
--
that adequate ALARA review, personnel training, and equipment testing had been performed The RWP work being conducted had been planned, using specific
--
work instructions.
That each individual entering the RB had an alarming dosimeter
--
and a breathing zone air sampler.
That mock-up training and special instructions were developed
--
and used for unique tasks.
Entries 812 through 839 were made into the RB during this
--
period.
No violations were identified.
e.
Records Review
.The inspector reviewed selected radiological records during the period to assure the accuracy and completeness of the licensee documentation of occupational exposure. The records reviewed were selected from the following:
-
-
-
-
-
-
-
.
..
,
e g
.
Radiation Work Permits (RWPs)
--
Dosimetry Investigative Reports
--
--
Incident Evaluation Reports Radiological Awareness Reports
--
Dosimetry Exceptions Reports
--
No violations were identified, f.
Additional Reviews The inspector reviewed various licensee records and periodic reports concerning the radiological controls program, including current data and trends in such areas as manrem per RWP hour, decontamination
.
status, skin contaminations, environmental monitoring, radiological events, whole body counting, training, dosimetry, shipments, progress toward achievement of goals and objectives, storage tank radioactivity content, airborne radioactivity, and manrem by work category; effluent releases, including sump releases and sources of sump contamination; and the cumulative dose (manrem) to all plant personnel.
No violations were identified.
7.0 Inspector Follow Items Inspector follow items are inspector concerns or perceived weaknesses in
'
the licensee's conduct of operation (hardware or programmatic) that could I
lead to violations if left uncorrected.
Inspector follow items are addressed in paragraph 2.0.
8.0 Exit Interview The inspectors met periodically with licensee representatives to discuss inspection findings. On March 6,1986, the inspector summarized the inspection findings to the following personnel at the exit meeting:
J. Byrne, Manager, TMI-2 Licensing W. Craft, III, Manager, Radiological Controls Field Operations C. Dell, Licensing, Technical Analyst W. Heysek, TMI-2 Audit Supervisor S. Levin, Site Operations Director M. Slobodien, Manager, Radiological Engineering F. Standerfer, Director, TMI-2 At no time during the inspection was written material provided to the licensee by the TMICPD staff except for procedure reviews pursuant to Technical Specification 6.8.2.
,