ML20236V735
| ML20236V735 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/27/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20236V728 | List: |
| References | |
| 50-413-98-07, 50-413-98-7, EA-98-370, NUDOCS 9808040177 | |
| Download: ML20236V735 (3) | |
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' Duke Energy Corporation Docket No. 50-413 l
Catawba Nuclear Station License No. NPF-35 EA 98-370 During an NRC inspection conducted from May 24, 1998 - July 4. 1998.
l violations of NRC requirements were identified.
In accordance with the l
~ General Statement of Policy and Procedure for NRC Enforcement Actions."
L NUREG-1600. the violations are listed below:
A.
10 CFR 50 Appendix B. Criterion XVI. Corrective Action, as implemented by the Duke Energy Corporation Topical Report Quality Assurance Program.
Revision 22. recuires in part, that measures shall be established to assure that concitions adverse to quality are promptly corrected, and in the case of significant conditions adverse to quality, that measures be established to assure that the cause of the condition is determined and corrective action taken to preclude recurrence.
Contrary.to the above. the licensee failed to identify and take prompt l
corrective action following Unit 1 upper surge tank over-temperature l
events on January 20. 1996, and January 11. 1998. to preclude recurrence of an adverse system interaction and significant condition adverse to
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cuality.
Consequently. Unit 1 auxiliary feedwater system became cegrtded and was declared inoperable for approximately three hours on i
May 7, 1998.
This is a Severity Level IV Violation (Supplement I).
l B.
Technical Specification 6.8.1.a requires, in part, that written procedures shall be established. implemented, and maintained for I
applicable procedures in Appendix A to Regulatory Guide (RG) 1.33.
Quality Assurance Program Requirements (Operation). Revision 2. 1978.
As referenced in Sections 2 and 5 of RG 1.33. this includes general operating procedures, as well as those for abnormal operating conditions.
Contrary to the above as of May 7,1998. the licensee failed to establish adequate operating and abnormal operating procedures related to excessive auxiliary feedwater system suction source temperatures'as indicated by the following examples:
l 1.
Abnormal Operations Procedure AP/1/A/5500/006. Loss of Steam Generator Feedwater, did not provide instructions to manually realign auxiliary feedwater pump suction to the assured safety-related source when preferred source temperatures exceeded the 138 F design value used in Updated Final Safety Analysis Report (UFSAR) accident analyses.
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2.
Operations Procedure OP/1/A/6250/002. Auxiliary Feedwater, did not include guidance to ensure auxiliary feedwater suction source temperatures did not exceed the 138 F design temperature value used for UF5AR accident analyses.
3.
Operations Procedure. OP/1/A/6250/001. Condensate and Feedwater, did not contain detailed instructions to ensure proper operation of the digital controller for valve 1CM-127. This deficiency resulted in extended operation with the controller outside of prescribed parameters, which led to degradation of the auxiliary feedwater system on May 7, 1998.
This is a Severity Level IV Violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201. Duke Energy Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission. ATTN:
Document Control Desk. Washington, D.C. 20555 with a copy to the Regional Administrator Region II and a copy to the NRC Resident Inspector at the Catawba facility within 30 days of the date of the letter transmitting this Notice of Violation (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 or severity level. (2) the corrective steps that have been taken and the results achieved. (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence if the correspondence adequately addresses the required i
response.
If an adequate reply is not received within the time 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.
l Where good cause is shown consideration will be given to extending the l
response time.
If you contest this enforcement action, you should also provide a copy of your response to the Director. Office of Enforcement. U. S. Nuclear Regulatory Commission. Washington, DC 20555-0001.
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 redaction.
If personal privacy or proprietary information is necessary to provide an acce) table response, then please provide a bracketed copy of your response tlat identifies the informa-tion that should be protected and a redacted copy of your response that deletes such information.
If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information
l required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or finar.cial information).
If safe information is necessary to provide an acceptable response,guardsplease provide the level of protection described in 10 CFR 73.21.
Dated at Atlanta, Georgia this 27TH day of July,1998 l
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