ML20054H048
| ML20054H048 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/21/1982 |
| From: | Lutkehaus T FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20054H038 | List: |
| References | |
| CS-82-132, NUDOCS 8206220523 | |
| Download: ML20054H048 (2) | |
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- 3F-0582-21 Mr. J. P. O'Reilly, Regional Administrator Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303
Subject:
Crystal River Unit 3 Docket No. 50-302 Operator License No. DPR-72 1.E. Inspection Report 82-05
Dear Mr. O'Reilly:
We offer the following response to the violations listed in the referenced inspection report.
I NOTICE OF VIOLATION A.
Technical Specification 4.6.1.2.d requires type C leakrate testing to be conducted on containment isolation valves at intervals no greater than 24 months.
Contrary to the above, as of March 22, 1982, leakrate testing on containment isolation valves (SAV-23, SAV-122, and LRV-46) was not conducted within the required 24 month intervals.
This is a Severity Level IV Violation (Supplement 1.).
A.
Response
Florida Power Corporation concurs with the stated viola-tion.
The violation occurred because a change to Technical Specifica-tions was made and review of this change did not include discipline engineers or supervisors. As a result, the Surveillance Procedure was not revised to include these changes. The current review cycle for Technical Specification changes does include discipline engine-ers and supervisors in order to incorporate appropriate Technical Specification changes into the required procedures.
An interim change to SP-179, Containment Leakage Test Type "B" and "C" includes the valves LRV-46, SAV-23, and SAV-122 in the test pro-gram. The valves were tested under the interim change and the pro-cedure was completed satisfactorily.
8206220523 820611 PDR ADOCK 05000302 G
PDR General Office 3201 Thirty-fourth street soutn. P O Box 14042 st Petersburg. Florida 33733 813-866-5151
o Notice of Violation Response 50-302/82-05 USNRC Page 2 Revision 16 of SP-179 will incorporate the interim change to make these valves testable under a permanent revision. This is expected to be completed June 30, 1982, B.
Technical Specification 6.8.1 requires that applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, 1972, be es-tablished and implemented. Procedure AI-500, Conduct of Operations, Paragraph 4.1 requires the signature or initials of the person per-forming a step-by-step operating procedure at each step of the pro-cedure.
Contrary to the above, during the period of March 7 and 8, 1982, the person performing step-by-step operating procedure OP-403, Chemical Addition System, did not sign or initial any steps within the pro-cedure.
This is a Severity Level V Violation (Supplement I.).
B.
Response
No response required.
Should there be further questions, please contact us.
Very truly yours, W
T. C. Lutchaus k
Nuclear Plant Manager SJ.A David C. Mardis Acting Manager Nuclear Licensing CGB/rc cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555