ML17202G668
| ML17202G668 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/30/1989 |
| From: | Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17202G667 | List: |
| References | |
| 50-237-89-19, NUDOCS 8911080230 | |
| Download: ML17202G668 (2) | |
Text
Commonwealth Edi son Company Dresden Station Unit 2 NOTJCE OF VIOLATION
. Docket No. 50-237 Licetis~ No. DPR 19 As a result of the inspection conducted on August 29 through October 10, 1989, and in accordance with the "Genera 1 Po 1 icy and Procedures for NRC Enforcement
- Actions," 10 CFR Part 2, Appendix C (1989i the following violations were
- identified:
- 1.
Dresde~ Technical Speciffcation Table 3.2.2 requires two oper~ble or tripped trip systems for instrumentation that initiates or co.ntrols the core and containment cooling systems whenever any emergency core cooling subsystem is required to be operable. -
Contrary to the above, on August 30,.1989, reactor low/low water level
- indicating switch (LIS) 2-263-72C, for emergency core cooling system initiation, was not placed iri the tripped condition on* unit 2 when it was isolated for maintenance.
As a result, the minimum number of operable or tripped trip systems did not exist.
This is*a Severity Level IV violation (Supplement I).
{No. 237/89019-0l(DRP))
- 2.
10 CFR 50, Appendix _B, Criterion Vas impleme_nted_ by Commonwealth Edison
- Company's Quality Assurance Program, as described in Section 5 of Topical Report CE-IA, requires that activities affecting quality be prescribed by documented instruct ions, procedures or drawi rigs of a type app.ropri ate to the circumstances and be accomplished in accordance with these instructions, procedures or drawings.
Dresden Administrative Procedure 7~27, Independent Verifications, Revision 0, requires that independent verifications ensure that each check constitutes an actual component identification.
Contrary to the above, on September 21, 1989, removal of a primary containment isolation fuse. for Equipment Outage Number II~1209 was not accomplished i~ actordance with instructions in that the independent verification did not constitute an adequate component identification.
An incorrect reactor protection system scram fuse was removed which resulted in an unexpected half scram on Unit 2.
This is a Severity Level V violation (Supplement I).
(No. 237/S9019-02(DRP))
Pursuant to the provisions of 10 CFR 2.201,. you are required to submit t~ this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation:
(l} c6rrective action 991030 8911oso23g 05000237 pDR ADDC~
pNV Q
. Ncitice of Violation 2
taken and the results achieved; (2) coirective action to be taken to avbid further violations; and (3) the date when full compliance will be*a*chieved.
Consideration may be given to extending your response time for good ~ause shown.
~)&)*~*
.~~sa~c1et Reactor Projects Branch 1