ML17328A019
| ML17328A019 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/01/1989 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17328A018 | List: |
| References | |
| 50-315-88-28, 50-316-88-32, NUDOCS 8905050269 | |
| Download: ML17328A019 (2) | |
Text
NOTICE OF VIOLATION Indiana Hichigan Power Company
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D.C.
Cook Nuclear Power Station Docket Nos. 50-315; 50-316 License Nos.
DPR-58; DPR-74 As a result of the inspection conducted on December 12, 1988 through March 16,
- 1989, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for HRC Enforcement Actions (1988), the following violations were identified:
l.
10 CFR 50, Appendix 8, Criterion III, as implemented by the D.C.
Cook Operations guality Assurance Program requires that measures be established to assure design bases are correctly translated into drawings and that the design adequacy is verified and checked.
Contrary to the above, design bases were not correctly translated into drawings and design adequacy was not verified and checked in that:
a.
For Request for Change (RFC)
Ho.
12-2718 a technical review was not performed nor documented for the substitution of lower grade nuts.
b.
For RFC Ho. 01-4091, the required pipe reinforcement calculation was not performed and the size of the reinforcement weld and socket fillet welds were not specified.
Furthermore, the fillet size for socket welds was not specified for any RFC examined during this inspection.
c.
For RFC No. 02-2892, the deflection calculation for support R936 did not properly account for the applied loads and contained a
non-conservative mathematical error.
d.
For RFC Ho. 02-2892, the location specified for installation of support R936 was on the wrong piping system.
e.
For RFC No.
12-2665, the location specified for installation of support 12-ACS-L912 was different from the location assumed in the analysis by 46 inches.
For support 12-CS-L916 structural components were not evaluated and proper loads were not included in evaluating the base plate and anchor bolts.
For RFC Ho. 02-2926, an unverified analytical technique was used to evaluate a structural component for supports
- R590, R593,
- R595, R596, R597 and R599.
Also the load combination used in the evaluation did not give conservative moment results.
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For RFC No. 02-2908, the allowable installation clearances for U-bolts installed on the steam generator instrument piping were not specif ied.
(315/88028-01; 316/88032-01)
Thi s is a Severity Level IV vio 1 ation (Supplement
- 1).
2.
10 CFR 50, Appendix B, Criterion V, as implemented by the D.C.
Cook Operations guality Assurance Program requires that activities affecting quality be prescribed by documented procedures.
Contrary to the above, the design activities associated with small bore piping analyses for RFC No.
12-2889 were not prescribed by documented procedures (315/88028-02; 316/88032-02).
This is a Severity.Level IV violation (Supplement 1).
3.
10 CFR 50, Appendix B, Criterion XVII, as implemented by the D.C.
Cook Opeyations guality Assurance
- Program, requires that sufficient records be maintained to furnish evidence of activities affecting quality.
Contrary to the above, the documentation associated with the Non-destructive examination (NDE) inspections for piping fillet weld sizes was not sufficient to determine that the proper size weld had been installed in the field (315/88028-06; 316/88032-06).
This is a Severity Level IV violation (Supplement 1).
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 Notice a written statement or explanation in reply, including for each violation:
( 1) the corrective actions that have been taken and the results achieved; (2) the corrective actions that will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
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