ML20030D500
| ML20030D500 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/24/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20030D477 | List: |
| References | |
| 50-413-81-10, 50-414-81-10, NUDOCS 8109010457 | |
| Download: ML20030D500 (3) | |
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4 APPENDIX A NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-413 & 50-414 Catawba 1 and 2 License Nos. CPPR-116 & CPPR-117 As a result of the inspection conducted on May 18-22, 1931, and in accordance with the Interim Erforcement Policy, 45 FR 66754 (October 7,1980), the following j
violations were identified.
A.
10 CFR 50, Appendix B, Criterion V as implemented by Duke Power Company i
(DPC) Topical Report " DUKE 1-A", Section 17, paragraph 17.1.5 requires that
" Activities affecting quality shall be prescribed by... procedures...and shall be. accomplished in accordance with those... procedures." Babcock and Wilcox (B&W) Inservice Inspection Procedure 151-120, Rev. 11, references B&W's Surface Preparation Procedure ISI-50 for ultrasonic examination j
surface preparation.
B&W',s procedure ISI-7.0 requires that the finished contact surface shall be free from weld spatter and any roughness that would interfere with free movement of the search unit or impair tne trans-mission of ultrasonic pulses.
Contrary to the above, on May 21, 1981, activities affecting quality were not accomplished in accordance with documented procedures in that Reactor Coolant System Welds Number 1NC-44-7, INC-31-1 and 1NC-44-20 were observed with surface conditions that interfered with free movement of the search unit and impaired the transmission of ultrasonic pulses (tape residue ard/
l or raised metal). All three weld joints had been preservice inspected and accepted by the licensee prior to the NRC reinspection.
This is a Severity Level V Violation (Supplement II.E).
This violation 1
applies to Unit 1 only.
B.
10 CFR 50, Appendix B, Criterion V as implemented by Duke Power Company (DPC) Topical Report " DUKE 1-A", Section 17, paragraph 17.1.5 requires that
" Activities affecting quality shall be prescribed by... procedures...and shall be accompsished in accordance with those procedures." ANSI N45.2.2-1972, " Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power Plants (During the construction phase)" has been identified as the applicable standard for storage and preservation.
Duke p ocedure i
P-3 revision 12 " Storage Inspection" implements the storage and preserva-tion requirements of ANSI N45.2.2. ANSI N45.2.2 requires items in storage I
to have caps, covers and closures intact.
P-3 requires diesel generator starting air compressors to be inspected monthly and, to assure that their crankcase was full of oil.
P-3 requires that steam generator primary nozzles be inspected monthly to insure freedom from rust.
8109010457 810824 M PDR ADOCK 050004131 Q
PDR.
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Duke Power Company 2
Docket Nos. 50-413 & 50-414 Catawba 1 and 2 License Nos. CPPR-116 & CPPR-117 Contrary to the above, on May 21, 1981, storage procedure requirements to control and preserve materials and eqt *pment from damage or deterioration were not being impletented in that:
1.
Diesel generator starting air compressor 181 had no documented storage inspections after October 1979.
2.
The air filter on the air intake part of diesel generator starting air compressor 181 was missing.
3.
Diesel generator starting air compressor 1A1 was low on oil.
4.
A severe rust condition was evident on the -'imary nozzle of Loop No.
3 steam generator (Unit 1).
5.
Gage pressures of stored components, under nitrogen purge, were being inspected without adequate &cceptance criteria.
This is a Severity Level V Violation (Supplement II.E).
C.
10 CFR 50, Appendix B, Criterion XIII as implemented by Duke Power Company (DPC) Topical Report " DUKE 1-A", Section 17, paragraph 17.1.13 requires measures be established to control handling of materials and equipment in accordance with work and inspection procedures to prevent damage and deterioration.
ANSI N45.2.2-1972, " Packaging, Shipping, Receiving, and Handling of Items for Nuclear Power Plants (During the construction phase)"
has been identified as the applicable standard for material and equipment handling. ANSI N45.2.2 paragraph 7.t requiies an ircoection program to be established for rigging and consideration for acceptability of all rigging af ter each inspection.
Contrary to the above, on May 21, 1981, adequate measures were not estab-lished to control handling of material and equipment in accordance with work and inspection procedures in that the licensee had no documented program for the inspaction of rigging slings or chokers used for handling safety-related materials or equipment.
This is a Severity Level V Violation (Supplement II.E).
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged viola-tiont; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will
Duke Power Company 3
Docket Nos. 50-413 & 50-414 Catawba 1 and 2 License Nos. CPPR-115 & CPPR-117 be achieved. Consideration may be given to extending your response time for good cause shown.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
JE 2 4 198l Date:
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