ML20092F209
| ML20092F209 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/13/1992 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-92-00018, GNRO-92-18, NUDOCS 9202190158 | |
| Download: ML20092F209 (3) | |
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~u n n-W. T. Cottle february 13. 1992 l
U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.
20555 Attention: Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Report No. 50-416/91-23 dated January 17, 1992 (GNRI-92/00012)
GNRO-92/00018 Gentlemen:
Entergy Operations, Inc. hereby submits the response to Notice of Violation 50-416/91-23-01.
Yours truly, w r--- o.,,,,
WTC/RRicg attachment cci Mr. D. C. Hintz (w/a)
Mr. J. L. Mathis (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region 11 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager (w/a)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C.
20555 9202190158 920213 i
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Attechment to GNRo-92/o0018 e
Pags 1 of 2 Notice of Violation 91-23-01 Technical Specification 6.8.1 requires that written procedures be established, implemented, and maintained for surveillance and test activities of safety related equipment.
Contrary to the above procedure 06-ME-1H61-V-0001, Local Leak Rate Test, was inadequate in that no provisions were provided to install or remove a protective tube plug in a check valve associated with the drywell airlock prior to or during periodic testing of the airlock.
I.
Admission or Denial of the Alleged Violation Entergy Operations, Inc. admits to this violation.
II.
The Reason For the Violation, If Admitted On November 19, 1991 following an automatic scram, plant personnel attempted to enter the D/W personnel airlock.
Entry was prevented by a differential pressure (dp) across the outer door (containment-side door).
The door interlock actuates at 2 psid. Using calibrated test equipment, the internal pressure of the airlock was detennined to be 40 psig, which is greater than the airlock's design pressure (30 psig).
SeeVoluntaryLER91-014(GNR0-91/00194) for details on this event.
Upon-investigation of the cause of the overpressurization, personnel discovered a plug installed in the inlet port of the outer equalizing valve (EV).
The EV appears to have been plugged since construction.
The EV is the only means of relieving internal pressure in the D/W airlock. The plugged inlet port allowed pressure to increase without a relief function during plant operation.
Neither the potential for overpressurization of the airlock or presence of the relief function was realized by plant personnel.
Identified differences in the design of the D/W and containment airlocks led to a misinterpretation of the D/W airlock design.
Therefore, the relief function was never required to be tested by plant procedures.
l VIOL 2301/SCMPFLR - 3 l
Attachment to GNRO-92/00018 r
Page 2 of 2
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111. The Corrective Steps Which Have Been Taken and the Results Achieved A Material Nonconformance Report was written to dr ument the
- ondition and initiate an evaluation of the airlo", Based on
'he evaluation of the CiW airlock overpressurizatten, it has been ktermined that the condition did not adversely affect the 4tructural integrity or functionality of the airlock.
The results of the evaluation revealed that with an internal pressure of 40 psig, in ccmbination with the design basis loading, the airlock components remained within the code allowable limits.
B.
The plant surveillance procedure, which governs leak rate testing, has been revised to include provisions for installation and removal of a protective tube plug for the D/W airlock relief valve.
C.
The weekly Operations surveillance procedure used to verify airlock accumulator pressures has been revised to require internal barrel pressure readings from the local airlock indications.
IV. The Corrective Steps Which Will Be Taken To Preclude Further Violation A new test will be added to existing procedures to verify the relief valve on all airlocks which will relieve internal pressure.
V.
Date When Full Compliance Will Be Achieved Full compliance will be achieved by April 17, 1992.
VIOL 2301/SCMPFLR - 4
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