ML20217Q153
| ML20217Q153 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 08/22/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20217Q145 | List: |
| References | |
| 50-254-97-10, 50-265-97-10, NUDOCS 9708290228 | |
| Download: ML20217Q153 (3) | |
Text
,
4 NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-254; 50-265 Quad Cities Station, Units 1 and 2 License Nos. DPR 29; DPR 30 During an NRC inspection completed on July 25,1997, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violations are listed below:
1.
10 CFR 50, Appendix B, Criterion lil, " Design Control," requires that measures be established for the selection and review for suitability of application of parts, equipment and processes that are essential to the safety related functions of the structures, systems and components.
Contrary to the above, adequate design control measures were not used for the following design changes:
a.
Alternate parts evaluation 0 1997-0023-00, issued April 15,1997, authorized the replacement of model 150BMPOR89 (model 89) air start motors on the Unit 2 (U-2) emergency diesel generator (EDG) with model 150BMPDR88 (model 88) motors as a like for-like replacement. However, the new model 88 air start motors contained significant dimensional differences from the model 89 motors, thus resulting in a design change. As a result, the U 2 EDG failed to start during maintenance verification testing on May 8,1997 (254/265/97010-01a(DRS)).
b.
Ahernate parts evaluation M930030008, issued May 23,1994, authorized the replacement of residual heat removal heat exchanger relief valve 2-1001-165A, Type 1910MC-1 XMC324 (vapor trim), with a Type 1910MC 1-XLS324 (liould trim) valve. The replacement valve type contained documented functional differences, including re-closing pressure, from the original valve type, thus resulting in a design change. As a result, two replacement valves of the vapor trim type failed to re-close during testing (254/265/97010-01b(DRS)).
This is a Severity Level IV violation (Supplement 1).
2.
Criterion XI of 10 CFH 50, Appendix B, " Test Control," requires that testing be performed to demcnstrate that structures, systems and components will perform satisfactory in service and that the testing be performed in accordance with written test procedures which incorporate requirements and acceptance limits. Test results shall be documented and evaluated to assure that test requirements have been satisfied.
9708290228 970822 PDR ADOCK 050002S4 G
4 Notice of Vio'ation 2
Contrary to the above:
On May 10,1997, after installation of model 150BMPDR88 air start motors with mounting shims on EDGs U-2 and U 1/2, the licensee failed to perform adequate testing to ensure that the EDGs would start as required (254/265/97010-02 (DRS)).
This is a Severity Level IV violation (Supplement 1).
3.
10 CFR 50, Appendix B, Criterion XVI, " Corrective Actions," requires that conditions adverse to quality be promptly identified and corrected and that for significant conditions adverse to quality the cause of the condition be determined and corrective action be taken to preclude repetition.
Contrary to the above:
a.
Because of the continuing reliance on an inadequate alternate parts evaluation and inadequate testing, sufficient action was not promptly completed to identify and correct the cause of the May 8,1997 failure to start of the U-2 EDG following installation of the model 88 air start motors.
As a result, model 88 air start motors were installed on the U 1/2 EDG on May 17,1997. The model 88 air start motors were subsequently determined to be unacceptable and the U-2 and U-1/2 EDGs were declared inoperable on June 12,1997 (254/265/97010-03a(DRS)).
b.
Inadequate alternate parts evaluations, a condition adverse to quality, was not identified as a cause of the failures during testing of two liquid trim type replacement relief valves following the April 5,1997 failure of the residual heat removal heat exchanger relief valve. As a result, actions to correct inadequate alternate parts evaluations had not been taken as of the start of the inspection on June 9,1997 (254/265/97010-03b(DRS)).
This is a Severity Level IV violation (Supplement l).
Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison is hereby required to submit a written statement of explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington D.C. 20555 with a copy to the Regional Administrator, Region 111, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice of Violation (Notice), within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violation, and (4) the date when full compliance will be achieved. Your response may referer.ce or include previous docketed correspondence, if the correspondnce adequately addresses the required response, if an adequate reply is not received within the time J
l l
specified in this _ Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards
'information so that it can be placed in the PDR without reaction. Howevei, if you find it-necessary to include such information, you should clearly indicate the specifk. information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information frora the public.
Dated at Lisle, Illinois, this 22ndday of August 1997
,