ML17202L257
| ML17202L257 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/15/1990 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17202L256 | List: |
| References | |
| 50-237-90-11, 50-249-90-10, NUDOCS 9006060017 | |
| Download: ML17202L257 (2) | |
Text
NOTICE OF VIOLATION Commonwealth Edison Company Dresden Station - Units 2 and 3 Docket Nos. 50-237; 50-249 License Nos. DPR-19; DPR-25 As a result of the inspection conducted on April 2-6, 1990, and jn accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions, (1990), the following violation was identified:
10 CFR 50, Appendix B, Criterion V, as implemented by Commonwealth Edison Company's Quality Assurance Program, requires that activities affecting quality be accomplished in accordance with documented instructions, procedures, or drawings.
- a.
- b.
Procedure OAP 7-2, "Conduct of Shif~ Operations," Revision 15, requires the Nutlear Station Operator to ensure that the Degraded Equipment Log is properly completed with a notation of any equipment in a degraded condition and/or which may require further ac~ion.
Contrary to the above, on April 2, 1990., the inspector observed that the Control Rod Dtive (CRD) position indication lights wert not properly illuminated in about one quarter of the CRO positio~s in both Units 2 ~nd 3 vertical panels.
The inspector also noted that the control room operators had not documented the deficient conditions in the o~grdded equipment log, nor had any work requests been initiated to correct the deficient rod position indications. These conditions had existed ~or an indeterminate amount of time (237/90011-0lA(DRS); 249/90010-0lA(ORS)).
Procedure OEP 040-6, "Safety*Related Motor.Operated Valves Data and Settings",
Revision 5, established the settings for* thermal overloads, including a statement that the thermal overload settings could not be changed without approval from the Nuclear Engineering Departm~nt (NED).
Contrary to the above, without approval from NED, changes were observed
. to have been made on April 5, 1990 to eight of ten valve thermal overloads associated with the Unit 3 HPCI 250Vdc motor control center.
In seven of the valves, the motor would have tripped earlier than required, that is, in the non-conservative direction (237/90011-0lB(ORS); 249/90010-0lB(DRS)). *
- c.
Procedure OAP 15-01, Initiating and Processing a Work Request," Revision 22, required the maintenance work analyst/maintenance staff to verify that all requirements of the work package had been completed prior to forwarding the package to the QC department.
Contrary to the above, the work package performed under Nuclear Work Request 086234 was signed off on January 14, 1990, by QC but the work analyst had not confirmed that steps on the post verification test were complete.
As a result, the condition of the circuit breaker was not known because the work package was final QC accepted without documentation that the 300%
breaker trip test was accomplished for the A and C phases (237/90011-0lC(ORS);
249/90010-0lC(ORS)).
This is a Severity Level IV violation (Supplement 1).
900(:.0c.OO 1 7 F'DR ADOU=::
0 900515 0500(1237 F'DC
Pursuant to the prov1s1ons 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 st~ps that have been taken and the results achieved; (2) the corrective ste~s 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.
Dated A. J.. Mi1er~r Division of.Reactor Safety
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