ML20039F015
| ML20039F015 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/05/1982 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20039F012 | List: |
| References | |
| 50-440-81-16, 50-441-81-16, NUDOCS 8201110722 | |
| Download: ML20039F015 (3) | |
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Appendix l
NOTICE OF VIOLATION The Cleveland Electric Illuminacing Docket No. 50-440 Company Docket No. 50-441 As a result of the inspection conducted on November 17-20, December 10-11 and 15, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified:
1.
10 CFR 50, Appendix B, Criterion III states, in part:
" Measures shall be established to assure that... design basis...for those structures, syatems, and components...are correctly translated into specifications, drawings, procedures, and instructions. These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are centrolled."
Perry Nuclear Power Plant, Units 1 and 2 PSAR Chapter 17, Paragraph 17.1.3.1 states, in part, that, " Design control in performed by par-ticipating design groups to assure that the design of safety class structures, systems, and components will provide for their safe and reliable performance... The participant's procedures will cover specific design control methods and certain provisions to ensure that control will be applied to... selection and review for suitability of application of materials, parts, equipment, and processes... revision of design, including field changes, so that the changes comply with the original design control requirements."
Contrary to the above, the emergency service water pump restraint clearance was not in accordance with the GAI generic restraint design requirement. Carbon steel boltr and studs were installed in water without protective coatings. There was also a lack of inspection criteria to ensure full thread engagement at the sleeve nuts, and bolt torquing requirements to prevent loosening due to system vibration.
This is a Severity Level V violation (Supplement II).
2.
10 CFR 50, Appendix B, Criterion X states, in part:
"A program for inspection of activities affecting quality shall be established and executed by or for the organization performing the activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity."
H001110722 820105 PDR ADOCK 05000440 G
Appendix Perry Nuclear Power Plant, Units 1 and 2 PSAR Chapter 17, Paragraph 17.1.10.1 states, in part, that, "A program for inspection has been established by CEI to assure that all safety class equipment and structures meet required quality standards... The CEI program delegates responsibility for inspection to appropriate participating organizations and requires that the criteria set forth in 10 CFR 50, Appendix B, be met,"
Contrary to the above, relative to the inspection of restraints in-stalled on the emergency service water pumps, there was no detailed inspection checklists and/or measurement records. A subsequent field engineering inspection indicated that the restraint clearance did not meet the acceptance values established in the QC inspection procedure.
This is a Severity Level V violation (Supplement II).
3.
10 CFR 50, Appendix B, Criterion VI stctes, in part, " Measures shall be established to control the issuance of documents... including the changes thereto, which prescribe all activities affecting quality.
These measures shall assure that documents, including changes, are reviewed...and approved...by authorized personnel and are distributed to and used at the location where the prescribed activity is performed."
Perry Nuclear Power Plant, Units 1 and 2 PSAR Chapter 17, Paragraph 17.1.6.1 states, in part, that, " Procedures shall be utilized to control those documents which specify, describe or evidence activities affecting the quality of the PNPP. These procedures shall be in accordance with the CEI Nuclear Quality Assurance Program and 10 CFR 50, Appendix B, and will identify persons who review for adequacy and approve documents for use.
Document distribution shall be specified and controlled.
Control Methods will include periodic issuance of revision status lists to prevent use of obsolete information.
Changes or revisions to documents will be processed by the same method as the original issue or by an approved alternate method."
Contrary to the above, the Piping Engineering Department Perry Project Instruction, Section C - Support Design, and the design allowables developed for Hilti bolts used by the site small bore piping group, had not been issuanced, reviewed, and approved in accordance with approved document control procedures.
Tbis is a Severity Level V violation (Supplement II).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notica a written statement or explanation in reply, including for each stem of nancompliance:
(1) c0rrective l
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Appendix l I
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action taken and the results achieved; (2) corrective action to be taken to j
avoid further noncompliance; and (3) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Consideration may be given to extending your response time.for good cause shown.
I JAN 5: IM b
L Dated C. E. Norelius, Director E
Division of Engineering and Technical Inspection-l I
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