ML20236M274

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Notice of Violation from Insp on 870919-1016.Violation Noted:Failure to Document & Evaluate Test Discrepancies Noted on 870910 & 11 During Standby Liquid Control Sys Testing
ML20236M274
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/27/1987
From: Verrelli D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20236M269 List:
References
50-416-87-26, NUDOCS 8711130067
Download: ML20236M274 (2)


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ENCLOSURE 1 NOTICE OF VIOLATION System Energy Resources Docket No. 50-416

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Vi Grand Gulf License No. NPF-29 7,.

During the Nuclear Regulatory Commission (NRC) inspection conducted on September 19 - October 16, 1987, a violation of NRC requirements was identified.

The violation involved failure to document and evaluate Standby Liquid Control System test discrepancies.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2,

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s Appendix C (1986), the violation is listed below:

Technical Specification 6.8.1. requires written procedures be estabished 9

and implemented for safety related activities.

Procedure

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06-0P-1C41-M-001, paragraphs 5.1. 7, 5.1.9 and 5.2.13.c require the operator verify that the Standbv Liquid Control system relief valve

.T F029A(B) does not lift during recirculation to the test tank.

The ASME 8 & PV Code,Section III, NC-7513.1, requires the system relief valve lift tolerance not exceed + 3% of set pressure.

Administrative procedure t

01-S-03-3, Revision 70, Material Nonconformance Reports (MNCRs),

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1. 2 states "This procedure shall be used to document

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discrepancies concerning material related documentation, i.e. test results, certification, etc, which leave the continued acceptability of installed hardware indeterminate."

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v-Contrary to the above, on September 10, 1987 the Standby Liquid Control (SLC) system relief valve lifted while the SLC system was recirculating i

water to a test tank.

On Ceptember 11, 1987 while performing a SLC system

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relief valve functional test, the relief valve lifted outside the allowable + 3% lift tolerance.

In both events the licensee failed to initiate a lonconformance Report and did not evaluate the acceptability of continued SLC system operability before returning the SLC system to operation.

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3 This is a Severity Level IV violation (Supplement I).

i Pursuant to the provisions of 10 CFR 2.201, Systems Energy Resources, Inc. is i

hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including for each violation: (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been

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taken and the results achieved, (4) the correcthe steps which will be taken e.

8711130067 871027 PDR ADOCK 05000416 G

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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.

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'FOR THE NUCLEAR REGULATORY' COMMISSION

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cgolNAl. SIGNED 8T 9' AVID glVEW

' David.M. Verrell'1, Chief.

Reactor. Projects. Branch 1

' Division:of.ReactorProjectsL

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Dated at Atlanta, Georgia l/.

this27thday of October 1987 VW I

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