ML20097J866
| ML20097J866 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/20/1984 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20097J863 | List: |
| References | |
| ACEM-84-0418, ACEM-84-418, NUDOCS 8409240073 | |
| Download: ML20097J866 (2) | |
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LCOPV MISSISSIPPI POWER & LIGHT C
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Helping Build Mississippi +eWY P. O. B O X 1640, J AC K S ON, MIS SIS SIP PI 3 9 2 0 5 N Auqugust24 A 9 : 53 20, 1984 NUCLEAR LICENSING & $AFETY DEPARTMENT U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Attention:
Mr. J. P. O'Reilly, Regional Administrator
Dear Mr. O'Reilly:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File: 0260/15524/0310 Report No. 50-416/84-11, dated April 24, 1984 (MAEC-84/0162)
AECM-84/0418 Attached is a supplemental response to the Notice of Deviation
416/84-11-05, which provides additional information on the corrective actions taken to fulfil the commitment requiring periodic testing of remote shutdown control components.
Yours truly,
<A_
L. F. Dale Director RLS/SHH:rg Attachment cc:
Mr. J. B. Richard (w/a)
Mr. R. B. McGehee (w/o)
Mr. N. S. Reynolds (w/o)
Mr. G. B. Taylor (w/o)
Mr. Richard C. DeYoung, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
Document Control Desk (w/a)
U. S. Nuclear Regulatory Commission j
Washington, D. C.
20555 i
8409240073 840829 PDR ADOCK 05000416 G
PDR Member Middle South Utilities System e
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Page 1 SUPPLEMI2 ITAL RE3PONSE TO NRC DEVIATION 416/84-11-05 J
Directive 06,0P-1C61-Temp 1.was ~ issued to-perform the necessary, tests to prove operability on the control devices contained on the remote shutdown panels.
- These tests were successfully completed on August 4,1984, except for valve
- E12-F053A and RCIC. The surveillance requirements;will be incorporated into Surveillance Procedure 06-OP-1C61-R002 which will implement the new requirements' contained in Amendment 13 to the GGNS Operating License Manual.
. This procedure will be issued upon issuance of. Amendment 13.
Valve E12-F05'3A was tagged-out to perform feedwater check valve local leak-rate tests and could not be:surveilled. Testing-will be completed prior to start-up.-
The controls associated with the RCIC System cannot be surveilled.until the-plant becomes critical and reaches 150 pounds reactor vessel pressure. This Ltest will be performed per Surveillance Procedure 06-OP-1E51-P005 which will be revised to reflect the new Technical Specification requirements.-
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