ML17263A573
| ML17263A573 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/06/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17263A572 | List: |
| References | |
| 50-244-94-05, 50-244-94-5, NUDOCS 9404120027 | |
| Download: ML17263A573 (3) | |
Text
ENCLOSURE NOTICE OF VIOLATION Rochester Gas and Electric Corporation Ginna Station Docket No. 50-244 License No. DPR-18 During an NRC inspection conducted on February 8, '1994 to March 8, 1994, one 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 XI, "Test Control," states, in part:
"A test program shall be established to assure that all testing required to demonstrate that structures,
- systems, and components willperform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents."
Contrary to the above, two conditions were identified that demonstrated that testing was not being appropriately performed.
Specifically:
On February 15, 1994, itwas determined that the two manual containment isolation pushbuttons had not been periodically tested each refueling outage as required by Technical Specification Table 4.1.2 item 9.
On March 4, 1994, the licensee determined that containment pressure (P) channels P-947 and P-948 had been inoperable since June 1992, due to an obstruction in the common containment pressure sensing line for the pressure transmitters (PT)-947 and PT-948.
The monthly channel functional test and annual channel calibration, as required by Technical Specification Table 4.1-1, items 17 and 25, associated with these channels, did not detect the obstructed tubing due to the obstruction being located in an untested section of the pressure sensing line between the open end in the containment vessel and the root isolation valves for PT-947 and PT-948.
This is a Severity Level IV violation.
(Supplement I)
Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation 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 I, 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 a "Reply to a Notice ofViolation" and should include for each violation: (1) the reason for the violation, or, ifcontested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that willbe taken to avoid further violations, and (4) the date when full compliance wiU be achieved. Ifan adequate reply is not received within the time specified in 9404i20027 94040b PDR ADOCK 05000244 Q
PDR 0~0~ RECOao Copy
~ ~~i '( ~)<~ F
> YW~pj ~j'L~~~
kg Q$J'
Enclosure 1
this Notice, an order or a Demand for Information may be issued to show cause why the license
'hould 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 willbe given to extending this response time.
Dated at Kin f P ia PA this ~TH day of APRIL 1994