ML19332C629
| ML19332C629 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 10/27/1989 |
| From: | Verrelli D NRC Office of Inspection & Enforcement (IE Region II) |
| To: | |
| Shared Package | |
| ML19332C627 | List: |
| References | |
| 50-416-89-23, NUDOCS 8911280362 | |
| Download: ML19332C629 (2) | |
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I ENCLOSURE 1 NOTICE OF VIOLATION E
-System Energy Resources, Inc.
Docket No. 50-416 Grand Gulf License No NPF During the Nuclear Regulatory Commission (NRC) inspection conducted on August 26 - September 30, 1989, a violation of NRC requirements wat identified.
In accordance with the " General - Statement of Policy and Procedure for NRC Enforcement ~ Actions, 10 CFR Part 2, Appendix C (1989), the violation is listed below-
. Technical Specification 6.8.1.a requires that written procedures be established, implemented and maintained covering the activities recommended in Appendix' A, of_ Regulatory Guide 1.33, Revision 2, February 1978.
Regulatory Guide 1.33, states that activitiet such as those involving the instrument air system,: reactor protection system and the reactor core isolation cooling system should-be covered by written procedures.
JA.
System Operating Instruction 04-1-01-P53-1, Instrument
'ystem.,
Attachment II, Remote Operated Valve Lineup Checksheet.
"s valve L
IP53F013, instrument air system cross-tie to unit 2, to be l
, Contrary to the above, on September 9,'1989, an operator closed tha -
1 instrument air system cross-tie valve (F013) without logging the repositioning or tagging the valve.
This resulted in a decrease in -
l instrument air pressure from 125 psig to approximately 90 psig.
Li B.
Surveillance Procedure 06-IC-1C51-W-0006,. Average Power Range Monitor Calibration, step 5.6.2 requires placing APRM D ' flow card switch S1 in the " test" position.
~v Contrary to the above, on September 26, 1989, while performing APRM D calibration, an I&C technician incorrectly placed the APRM H flow card switch in " test" instead of placing the APRM D switch in the " test" position.
This resulted in a half scram on reactor protection system o
L division II.
C.
Surveillance Procedure 06-IC-IE31-A-1002, Main Steam Line Tunnel, RCIC Steam Pipe Tunnel and RCIC Equipment Room High Temperature /High Differential Temperature Calibration Attachment IV, step 5.13.7, requires placing the reactor core isolation cooling system (RCIC) isolation bypass switch in the bypass position.
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-System Energy Resources Inc.
2 Docket No. 50-416 Grand Gulf-License No. NPF-29
' Contrary to the above, on September 29, 1989, while performing surveil-lance 06-IC-1E31-A-1002 an operator incorrectly placed the reactor water i
cleanup (RWCU) " bypass" switch to " normal" instead of placing the RCIC isolation bypass switch to " bypass". This resulted in a RWCU isolation, s
This is a Severity Level IV violation (Supplement I).
Pursuant' to the provisions of 10 CFR 2.201, System Energy Resources, Inc. is t
hereby required to submit a written statement or explanation to the Nuclear Regulatory - Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice.
This reply should be -clearly rerked as a " Reply to a Notice of Violation" and should include for each violation:
(1) admission or denial of i
the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken-and the results achieved, (4) the corrective stops which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be
.given to extending the response time.
If an adequate reply is not received within the ~ time specified in this Notice, an order may be issued to show cause 4
why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
s FOR THE NUCLEAR REGULATORY COMMISSION 9
David M. Verre111 "tMef Reactor Projects Branch 1 Division of Reactor Projects-Dated at Atlanta, Georgia this27th day of October 1989
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