ML14178A255
| ML14178A255 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/22/1992 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14178A254 | List: |
| References | |
| 50-261-92-19, NUDOCS 9208110098 | |
| Download: ML14178A255 (2) | |
Text
ENCLOSURE1 NOTICE OF VIOLATION Carolina Power and Light Company Docket No.: 50-261 H. B. Robinson License No.: DPR-23 During an NRC inspection conducted on June 15-19, 1992, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
10 CFR 50, Appendix B, Criterion III and the licensee's accepted Operations Quality Assurance Program, updated Final Safety Analysis Report (FSAR),
Section 17.2.3, Design Controls, collectively require that the adequacy of design changes be verified by the performance of design reviews, alternate calculations or qualification testing. Control measures for control of design verification activities shall include reviews to assure that design parameters are defined and that inspection and test criteria are identified.
In January 1992 design basis calculation number RNP-M/MECH-1398, 1399, and 1400 determined the differential pressure across feedwater block valves FW-2V-6A, B, and C to be 50 psid based on postulated assumptions that (1) the feedwater regulating valves located downstream of each block valve will close in seven seconds upon receipt of a safety injection (SI) signal and (2) the reactor feedwater and condensate pumps will trip and coast to a stop.
Contrary to the above, on June 15, 1992 feedwater block valve FW-2V-6A failed to close fully because of a high differential pressure of 480 psid. The differential pressure was the result of the condensate pump discharge pressure being greater than 50 psid and an unverified assumption that the condensate pump is tripped upon receipt of an SI signal. The condensate pump can only be tripped manually by operator action and not by an auto trip signal.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light 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 facility that is the subject of this Notice, 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, (2) the corrective steps that have been taken and the results achieved, (3) the 9208110098 920722 PDR ADOCK 05000261 PDR
Carolina Power and Light Company 2
Docket No.: 50-261 H. B. Robinson License No.: DPR-23 corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in this Notice, an order or 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.
Corrective actions for the violation addressed in this Notice have been completed and the actions reviewed by NRC representatives. Therefore, no reply to the Notice is required.
Dated at Atlanta, Georgia this 22nd day of July 1992