ML20132E081
| ML20132E081 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/20/1985 |
| From: | Bicehouse H, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20132E050 | List: |
| References | |
| 50-277-85-31, 50-278-85-28, NUDOCS 8509300379 | |
| Download: ML20132E081 (17) | |
See also: IR 05000277/1985031
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos. 50-277/85-31
50-278/85-28
Docket Nos.
50-277
50-278
License Nos.
Priority
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Category
C
Licensee: Philadelphia Electric Company
2301 Market Street
Philadelphia, PA 19101
Facility Name:
Peach Bottom Atomic Power Station
Inspection-At: Delta, PA
Inspection Conducted: _ July 29 - August 1, 1985
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Inspectors:
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Approved by:
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W PJ. Pa$ci ak, Chief, BWR Radiological
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Protect %n Section
Inspection Summary:
Inspection on July 29 - August 1, 1985 (Combined Report
Nos. 50-277/85-31; 50-278/85-28)-
Areas Inspected:
Special, announced inspection of the licensee's transporta-
tion activities (i.e. radioactive materials shipping / receipt and radioactive
waste disposal) including: previously identified items, quality assurance /
quality control, indoctrination and training, procedures, procurement and reuse
of packagings, implementation of the program and incidents.
The inspection
involved 33 inspector-hours onsite by a regionally-based inspector.
Results: Three violations were identified, i.e. failure to provide accurate
radionuclide activities in shipping papers (Detail 9.2), certifying transported
materials were accurately described when they were not (Detail 9.2), and
contamination exceeding 220dpm/cm2 on the exterior of a shipping package
(Detail 9.3).
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DETAILS
1.0 Persons Contacted
During the course of this special inspection, the following personnel were
contacted or interviewed:
1.1 Licensee Personnel
D. Ahmuty, Administrative Assistant-Training
T. Donnell, Quality Control Supervisor
- A. Hilsmeir, Senior Health Physicist
- W. Knapp, Director, Corporate Radiation Protection Section
G. McCarty, Support Health Physicist
J. McElwain, Quality Control Engineer
- R. Moore, Lead Auditor, Quality Assurance
C. Nelson, Applied Health Physicist
P. Pauly, Radwaste Supervisor
- D. Smith, Superintendent-Operator
R. Smith, Physicist
D. Wheeler, Test Engineer, Reactor Engineer
J. Wilson, Quality Assurance Supervisor
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Other licensee personnel were also contacted or interviewed during
this inspection.
1.2 NRC Personnel
T. Johnson, Senior Resident Inspector
- J. Williams, Resident Inspector
- Attended the exit interview on August 1, 1985.
2.0 Purpose
The purpose of this special safety inspection was to review the licensee's
transportation activities in the areas of radioactive materials receipt
and shipping and radioactive waste (radwaste) disposal with respect to the
following elements:
Previously Identified Items
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Quality Assurance / Quality Control
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Indoctrination and Training
Procedures
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Procurement and Reuse of Packagings
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Implementation
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Incidents
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3.0 Previously Identified Items
3.1 (Closed) Inspection Followup Item (50-277/84-09-05) Determine if
audits are adequate. Audit Report No. AP84-67HPL, Radwaste/ Material
Handling and Shipping", (October 16, 1984 - December 10,1984),was
reviewed relative to criteria to 10 CFR 50, Appendix B applicable to
shipping. Audit Report No. AP84-67HPC addressed each criterion of 10 CFR 50, Appendix B and was comprehensive in terms of the licensee's
site shipping activities.
The audit was conducted by a trained
quality assurance auditor. This item is closed. See related
information in Section 4.1 of this report.
3.2 (Closed) Violation (50-277/84-42-02) Failure to provide QC Program in
accordance with 10 CFR 20.311(d)(3). Actions described in the
licensee's letter (dated February 28,1985), were reviewed. The
licensee completed actions as described in the response letter. This
item is closed.
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3.3 (Closed) Inspection Followup Item (50-277/84-42-03) Licensee's
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actions regarding NRC Information Notice No. 84-72 for solified
contamination resin shipment. The licensee developed Special
Procedure 769, " Final Verification of Opening And Venting of CNS
6-80-2 Cask", (June 24, 1985), and Special Procedure 775, " Gas
Sampling of Cask Using Marinelli Beaker", (January 23,1985),in
response to this item.
The procedures adequately addressed gas
generation concerns.
This item is closed.
4.0 Quality Assurance (QA)/ Quality Control (QC)
A QA program is required for transport packages in accordance with the
provisions of 10 CFR 71, Subpart H.
A Commission approved QA program
which satisfies the applicable criteria of Appendix B of 10 CFR 50 and
which is established, maintained and executed with regard to transport
packages is acceptable to meet the requirements of 10 CFR 71, Subpart H.
.The licensee elected to apply their currently established 10 CFR 50,
Appendix B, QA program to the packaging and transportation of radioactive
material.
In addition to the general QC provisions required by 10 CFR 50, Appendix
B, specific QC requirements to assure compliance with 10 CFR 61.55 and
61.56 are required by 10 CFR 20.311.
The packaging and transportation QA/QC activities implemented by the
licensee's site QA and QC organizations was reviewed.
4.1 Audits / Appraisals
The licensee's program for audits of radwaste/ material shipment
activities (including radwaste preparation and classification) was
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reviewed against requirements, commitments and guidance provided in:
10 CFR 50, Appendix B, Criterion XVII, " Audits";
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Technical Specification 6.5, " Review And Audit";
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Peach Bottom Atomic Power Station, Units 2 and 3 Quality
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Assurance Plan; and
NRC-IE Information Notice 84-50, " Clarification of Scope of
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Quality Assurance Programs for Transport Packages Pursuant to 10
CFR SC, Appendix B."
.The licensee's performance in this area was determined by interviews
of site QA personnel, examination of Quality Assurance Division Pro-
cedures for scheduling, performing, reporting and closing audits and
review of Audit Reports Nos. AP 84-67HPC and AP 83-04HPC.
The inspector noted that:
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corrective action measures initiated as a result of audit find-
ings are reviewed for implementation on followup audits;
adequate QA procedures and checklists were used in auditing
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shipping activities; and
a review of the QA program was conducted in 1984 to ensure that
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the licensee had adequate procedures to implement the QA plan
for transport packages.
Within the scope of this review, no violations were identified. The
licensee has implemented an audit program for shipping activities
addressing applicable criteria in 10 CFR 50, Appendix B.
4.2 Surveillance / Inspection Activities
The licensee's program for surveillance and inspection activities was
reviewed against criteria provided in 10 CFR 50, Appendix B,
Criterion X, " Inspections" and commitments in the licensee's approved
QA plan.
The licensee's performance relative to these standards was
determined by interviews of site QC personnel, review of procedures
and other documents and observation of QC inspection activities
during Shipment No. 173-85.
Tne site QC organization provides surveillance and inspections cover-
ing radwaste/ material shipment activities (including radwaste pre-
paration). Detailed Monitoring Checklists have been developed for
-surveillance activities. Mandatory inspection hold points in plant
operating procedures related to shipping require witnessing or
inspection by QC personnel prior to continuation of the procedures.
Within the scope of this review, no violations were noted. The
licensee has implemented a generally effective surveillance and
inspection program.
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4.3 Radwaste Generator QC Program
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Under 10 CFR 20.311(d)(3), each licensee is required to conduct a
quality control program to assure compliance with 10 CFR 61.55 and
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61.56 requirements for waste classification and waste characteris-
tics. The licensee's performance in this area was determined by:
review of procedures for preparation of radwaste shipments;
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examination of records relating to shipments of dewatered
resins, control rod blades and dry active waste;
review of actions taken regarding findings in Combined Inspec-
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tion Reports Nos. 50-277/84-09; 50-278/84-09 and 50-277/84-42
50-278/84-34; and
discussions with cognizant health physics and operations
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personnel.
Within the scope of this review, no violations were noted.
5.0 Indoctrination and Training
The general indoctrination and specific training of personnel assigned to
radioactive materials shipping activities were reviewed relative to
criteria provided in 10 CFR 50, Appendix B, Criterion II, " Quality
Assurance Program", and commitments in the licensee's response to NRC-IE
-Bulletin No. 79-19, " Packaging of Low-level Radioactive Wastes for Trans-
port and Burial".
Selected training records for operations, health
physics, quality control and maintenance personnel were reviewed and
representatives from each group were interviewed regarding training for
use of the FSV-1 cask in irradiated control rod shipments and dewatered
resins in HN-100 series casks.
Within the scope of this review, no violations or deviations were noted.
6.0 Procedures
The licensee's procedures for selected shipping and receiving activities
were reviewed relative to criteria provided in 10 CFR 20.205, 10 CFR 71
and Technical Specification 6.8, " Procedures", Procedures in the HP0/C0-71
series, HP0/C0-17 series and selected fuel handling procedures were
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reviewed to determine if instructions concerning acceptance criteria and
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regulatory limits were provided for-
receipt of shipments containing radioactive materials, i.e. previous-
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-ly used casks supplied by contracted vendors;
selection of packaging for licensee-initiated shipments;
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maintenance of packaging;
marking and labeling shipments and placarding vehicles;
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monitoring shipments for radiation and contamination; and
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providing shipments of radwaste meeting disposal site acceptance
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criteria.
In addition, the licensee's procedures for preparation, classification,
packaging and shipping radwaste were reviewed against criteria contained
in:
10 CFR 20.311, " Transfer for Disposal and Manifests"; and
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NRC-NMSS Low-level Waste Licensing Branch, " Final Waste Classifica-
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tion and Waste Form Technical Position Papers", (May 1983).
6.1 Health Physics / Chemistry Operating (HP0/CO) Procedures
The licensee's procedures for receipt of radioactive materials,
(HP0/C0-16), shipment of radioactive materials, (HP0/CO-17 series),
handling high integrity containers, (HP0/C0-70), and selected casks
shipments, (HP0/CO-71 series) were reviewed and discussed with health
physics personnel.
Special emphasis was placed on the review of QC1
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hold and inspection points.
Within the scope of this review, the following items were noted:
HP0/CO-17C, " Compliance with 10 CFR Part 61", Revision 0 (March 19,
1984) contained several errors in technical content:
Section B, (Page 2), referred to Appendix D, however, the
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correct reference was Appendix C of the procedure;
Section D, (Page 4), indicated that a description of the Atomic
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Industrial Forum's method of waste classification was provided
in Appendix C, but it was not;
Section F.1.d (Page 6) omitted the words, " explosive reaction",
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while discussing requ,irements in 10 CFR 61.56(a)(4);
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Appendix A, Table 1 " Classification of Wastes" did not list
Nb-94 and had incorrect units for transuranic materials with
half lives greater than 5 years (i.e. Pu-241 and Cm-242) listing
those materials in curies per cubic meter instead of nanocuries
per gram; and
Appendix A, Table 2 listed incorrect Class B limits for Sr-90,
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incorrect Class C limits for Sr-90 and an incorrect limit for
unacceptable levels of Sr-90.
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In addition, HP0/CO-17C failed to discuss 10 CFR 61.55(a)(5) concern-
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ing classification by long and short-lived radionuclides and the " sum
of the fractions" rules in 10 CFR 61.55(a)(7).
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These errors in technical content in HP0/C0-17C were discussed with
the licensee and will be reviewed in a subsequent inspection,
50-277/85-31-01; 50-278/85-28-01.
6.2 Fuel Handling (FH) Procedures
The following fuel handling procedures related to the preparation,
packaging and shipping of irradiated control rod blades were
reviewed:
FH-48A, " Control Rod Corner Shearing Procedure", Revision 2,
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(May 15, 1985);
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FH-48B, " Control Rod Burial Liner Loading Procedure", Revision
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3, (June 13, 1985);
FH-48C, " Handling of the FSV-1 Casks", Revision 13, (July 24,
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'1985); and
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FH-480, " Radiation Survey of Spent Control Blades", Revision 0,
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(March 7, 1984).
Previous revision (to Revision 0) of FH-48A, FH-48B and FH-48C were
also reviewed to note developments technical changes in the
licensee's handling and shipping of irradiated control rod blades
since 1983.
Within the scope of this review, the following items were noted:
FH-48C failed to provide acceptance criteria for radiation dose
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rates associated with collected drainage water from the loaded
FSV-1 cask at Step H-4.
Although health physics technicians
were required to record measured dose rates on small quantities
of collected drainage water, acceptable dose ' rates for collected
water were not provided. Acceptance criteria were necessary
since the dose rates could be high if radioactive chips
associated with the shearing of the satellite rollers were
contained in the drainage.
In addition, the collected drainage
water discharged to a floor drain and the water's acceptability
to the liquid radwaste shipment must be determined prior to
discharge.
FH-48C failed to instruct crafts and quality control personnel
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to ensure that the entire sealing surface was " soap" tested at
Step H-21.
This " soap" test provides a test for cask leakage
following pressurization in earlier steps.
If the entire
sealing surface being tested is not covered with soap solution,
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an uneven pressure differential is created between the
pressurized cask and the surrounding atmosphere.
Leakage gas
would need to overcome the soap solution surface tension plus
atmospheric pressure in one area and only atmospheric pressure
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in unsoaped areas. The sensitivity of the leak test method
could thus be compromised.
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Final cask draining to remove water trapped in the two inverted
control rods' velocity limiters at Step H-2 and succeeding steps
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could lead to radioactive contamination of the trunion area. See
related item in Section 9.3 of this report.
These items were discussed with the licensee and will be reviewed in
a subsequent inspection.
50-277/85-31/02; 50-278/85-28-02.
6.3 QC Procedures
The following Detailed Monitoring Checklist (DMC) used by QC inspec-
tors reviewing radwaste preparation and shipping operations were
reviewed:
DMC 4.1, "Radwaste Shipping", (August 27,1984);
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DMC 4.2, "Radwaste Packaging and Storage", (March 1984); and
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DMC 4.3, "Radwaste Solidification", (April 3, 1984).
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Within the scope of this review,' no items of noncompliance were
noted.
7.0 Procurement and Reuse of Packagings
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The licensee's' program for selection of packages was reviewed against
requirements of 10 CFR 71.12. " General License: NRC Approved Package", and
the DOT requirements of 49 CFR 173, " Shippers - General Requirements for
Shipments and Packagings".
Records for 21 shipments were reviewed and
discussed with the licensee to determine that:
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for shipment in packages which the licensee had registered to use,
the licensee possessed copies of the specific NRC or Agreement State
Certificate of Compliance, drawings, procedures and referenced
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documents;
the licensee's practices regarding use and maintenance were in
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accordance with the applicable certificates and other documents
referenced in the certificate; and
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for NRC-certified pa'ckages, the licensee had registered with NRC-NMSS
prior to the first use of the package.
Within the scope of this review, no violations were identified.
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8.0 Implementation
The implementation of the licensee's program for transportation of
radioactive material was reviewed against criteria contained in 10 CFR 71,
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49 CFR 172-173 and the licensee's procedures.
For radwaste shipments,
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criteria in 10 CFR 20.311 and 10 CFR 61.55 and 61.56 were also used in the
review.
Each shipment examined was reviewed to determined the adequacy
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of:
radiation and contamination measurements;
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shipping paper documentation;
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package marking and labeling;
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loading and storage of packages;
vehicle placarding; and
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notification to state agencies for shipments of radwaste (as
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applicable under 10 CFR 71.97).
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The licensee's performance relative to these requirements was determined
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observation of shipment No. 173-85 (dewatered resin shipment);
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review of shipping records and other documents related to 8 Low
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Specific Activity (LSA) solidified drum and dry active waste box
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shipments, 8 irradiated control rod blade shipments in 1984 and 1985
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and 5 Certificate of Compliance cask shipments of dewatered resins;
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discussion with licensee personnel.
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Within the scope of this review, no violations were noted.
9.0 Incidents
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Three problems associated with radwaste shipments reported by the licensee
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were reviewed to determine that:
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the event was reported in a timely manner;
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the report made by the licensee was adequate;
the licensee took prompt corrective actions; and
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those corrective actions were adequate to prevent recurrence.
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9.1 Shipment No. 103-85 (Solidified Waste Drum)
On May 30, 1985, a representative of the State of Washington,
Department of Social and Health Services identified a " puncture hole"
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in Drum No. S-146-85 (one of a number of low specific activity (LSA)
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drums in Shipment No. 103-85). This problem was the subject of
enforcement action by the State of Washington and a Notice of
Violation from the NRC (see Combined Inspection Report Nos.
50-277/85-27; 50-278/85-25).
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Actions taken by the licensee to identify the cause(s) of this
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problem and to take corrective action were reviewed. The licensee
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verified that a " puncture hole" in Drum No. S-146-85 was present and
postulated that it was caused by fork lift handling devices used by
the licensee.
Corrective actions included:
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revision of HP0/CO-71G, " Loading of a Radioactive Waste Shipping
Van", and HP0/C0-71I, " Solidification, Packaging and Inspection
of Liquid and Materials in Preparation for Shipment", to reduce
the likelihood of damage during handling preparatory to
shipment;
examination of fork lift handling devices for possible causes;
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precautionary instructions to fork lift operators; and
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Although the licensee's actions appeared to be adequate, it was
unclear that handling preparatory to shipment had punctured the drum.
- 9.2 Shipment No.145-85 (FSV-1 Cask)
On July 7,1985, an FSV-1 cask containing 4 irradiated control rod
blades was sent for disposal at the low-level waste burial site in
South Carolina. Shipping papers sent with shipment indicated that
the cask contained 4 f rradiated control rod blades in cask liner No.
10.
In reality, cask liner No. 98 had been loaded and shipped in the
FSV-1 cask.
The differences between the original shipping papers
description and the actual description of the shipment are shown
below:
Original Shipping
Actual Shipment
Papers
Liner No.
10
98
- Total Activity
4,984.6 curies
7,643.5 curies
- Tritium Activity
166.26
224.6
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0.194 "
0.269
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0.0047 "
0.0065 "
- Iodine-129
4.8E-8 "
4.8E-8 "
Waste class
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- Dose Rate (liner
12,300.
19,600.
contact R/hr)
Advance notification to the states (under 10 CFR 71.97) sent by the
licensee's Reactor Engineering group on June 28, 1985 correctly
indicated a total activity of 7,645 curies and reflected the radio-
nuclidic activities in liner No. 98.
The original shipping papers
contained a certification that the transport materials were properly
described in the shipping manifest (shipping papers).
The following
violations associated with Shipment No. 145-85 were identified:
10 CFR 71.5(a) requires each licensee who delivers licensed
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material to a carrier for transport to comply with the require-
ments of the regulations appropriate to the mode of transport of
the Department of Transportation (00T) in 49 CFR Parts 170
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through 189.
49 CFR 176.203(d)(iii) requires that the activity
contained in each shipment be included in the shipping papers.
Contrary to these requirements, shipping papers accompanying
Shipment No.145-85 on July 7-9, 1985, incorrectly listed the
individual radionuclide activities and the total activity.
Failure to include accurate activities in Shipment No. 145-85
shipping papers constitutes a violation of 10 CFR 71.5(a)
50-277/85-31-03; 50-278/85-28-03.
10 CFR 20.311(c) requires, in part, that each shipping manifest
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include a certification by the waste generator that the trans-
ported materials are properly described.
Contrary to this requirement, the shipping manifest accompanying
shipment No. 145-85 on July 7-9, 1985, certified that the transported
materials were properly described when the individual and total
activities of the radionuclides listed on the shipping, manifest were
incorrect.
Certification that the transported materials were
properly described when the individual activities and total activity
in shipment were incorrectly listed constitutes a violation of 10 CFR 20.311(c).
50-277/85-31-04; 50-278/85-28-04.
On July 9, 1985, during discussions between Reactor Engineering and
Health Physics personnel, the licensee recognized that shipping
papers and manifests accompanying shipment No. 145-85 were incorrect.
The following corrective actions were taken:
Shipping papers and manifests reflecting the correct activities
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were prepared;
The low-level waste burial site was telephoned and requested to
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hold Shipment No. 145-85 to prevent removal and burial of the
liner;
A physicist was sent to South Carolina on July 9, 1985 with the
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corrected shipping papers and waste manifest;
The licensee informed the Senior Resident Inspector of the
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problem on July 9, 1985;
Procedure HP0/C0-71Y, " Shipment of the FSV-1", Revision 0, (July
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24,1985) was prepared which provided a verification by Health
Physics and QC personnel that the liner serial number in the
FSV-1 cask was consistent with the serial number on the shipping
papers and waste. manifest;
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Procedure FH-48C, " Handling of the FSV-1 Cask", was revised to
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include a QC verification of liner serial number (Step F-2 of
the procedure); and
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The licensee suspended control red blade shipments voluntarily
until-the corrective measures were ,in place.
The inspector noted that.the safety significance of this incident was
lessened by.the following considerations:
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actions to be taken in the eventi f a mishap in transport would
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not have been significantly affected by the errors in total
activity and liner contact radiation levels; and
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actions to prevent exposure at the low-level waste burial site
for these shipments _are based on contact liner dose rates up to
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30,000 R/hr.
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9.3 Shipment No.169-85 (FSV-1 Cask)
On July- 26,1985, 'the licensee shipped a FSV-1 cask containing 4
irradiated control rod blades to the low-level waste disposal site in
South Carolina. On July 30, 1985, the licensee reported that
representatives of the low-level burial site had discovered removable
radioactive contaminatio1 on the trunion cup area of the FSV-1
cask / trailer interface. This area is accessible for contamination
measurements only when the cask is separated from the trailer. The-
contamination levels reported by the low-level waste burial site
operator were'18,000 disintegrations per minute per 100 centimaters
squared (dpm/1002), 32,000 dpm/100cm ,-and 48,000 dpm/100cm'
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' July 30, 1985, a physicist and a test engineer were sent to ' 'e
low-level = waste burial site by the licensee to investigate 'ae
contamination.
On July 31, 1985, the physicist reported that measurements made by
the licensee confirmed the presence of removable contamination on the
trunion cup area of the _FSV-1 cask / trailer interface. Other areas of
the FSV-1 cask and trailer were uniformly measured to be less than
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1,000 dpm/100cm2 removable contamination.
Recorded removable con-
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tamination measurements made by the licensee on July-26, 1985, also
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.showed less than 1,000 dpm/100 cm
FSV-1 cask and trailer immediately prior to shipment. However, the
trunion cup had not been measured for removable contamination since
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the loaded cask had been joined to the trailer.
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During the licensee's review of the events surrounding the removable
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contamination,_a contractor health physics technician reported that
he had observed residual water in the vent / drain operation as the
venting apparatus was_being removed. The vent / drain operation
removes residual fuel pool water retained by the two inverted control
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rods' velocity limiters. During this operation, the cask and trunion
cup are mated and the cask is lowered from a vertical orientation to
one approximately 30 degrees from the horizontal. Nitrogen gas
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_ _ . _ . - - _ _ _ . _ . _ . - _ . _ - - - , _ _ - - - _ _ - - - - _ - - -
- - - - -
--&
.
.
.
.
13
pressure is applied to expel the final residual fuel pool water in
the velocity limiters which has been mobilized by placing the cask at
the 30 degree angle to the horizontal. Removal of the vent tube
causes the escape of small amounts of retained fuel pool water. The
vent tube apparatus is positioned in an area that would allow
drainage between the cask and the trunion cup area.
On August 6,1985, the NRC Region II State Agreement Officer con-
tacted the South Carolina Department of Health and Environmental
Control. The State of South Carolina's radiological controls
personnel have evaluated the removable radioactive contamination
associated with Shipment No. 169-85. No action was taken by the
state because the surface contamination was not accessible because
(1) it was located inside the trunion cup and (2) the area was
wrapped.
The following violation associated with Shipment No. 169-85 was
noted:
--
10 CFR 71.87(1)(2) requires, in part, that levels of non-fixed
(removable) radioactive contamination on the external surfaces
of each package offered for shipment as exclusive use shipments
not exceed 220 dpm/cm2 at any time during transport.
Contrary to this requirement, non-fixed radioactive contamina-
tion in the trunion cup area of the FSV-1 cask / trailer used in
Shipment No. 169-85 to the low-level waste burial site in South
Carolina exceeded 220 dpm/cm2 on July 30, 1985, upon arrival.
Non-fixed radioactive contamination was measured to be 320 and
2
480 dpm/cm . The presence of non-fixed radioactive contamina-
tion on Shipment No. 169-85 exceeding 220 dpm/cm2 upon arrival
at the low-level waste burial site constitutes a violation of 10 CFR 71.87(1)(2). 50-277/85-31-05; 50-278/85-28-05. The inspec-
tor noted that the presence of the removable radioactive con-
tamination in the trunion cup area presented little risks to the
public since the area is inaccessible during transport. How-
ever, the removable contamination was accessible during cask
unloading and presented a radioactive contamination problem to
the low-level waste burial site operators.
10.0 Exit Interview
The inspector met with the licensee representatives (denoted in Paragraph
1) at the conclusion of the inspection. The inspector summarized the
scope of the inspection and the findings. The inspector expressed his
concern over the problems noted in the control rod blade shipments. The
licensee's representative indicated that licensee management shared that
concern and intended to take additional action to identify and correct the
causes for the problem.
,
-
. . - - .
u m
.
m.
.
m
.
.
.
14
At no time during this inspection was written material provided to the
licensee by the inspector. No information except from disclosure under 10 CFR 2.790 is discussed in this report.
_
.-
.
_
.
. .
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