ML20003B615

Interim Deficiency Rept,Originally Reported on 801222,re Spring Guide Sleeve Shifting Internally on safety-related Actuators.Supplier Investigation Still in Progress.Final Rept to Be Submitted by 810616

ML20003B615
Person / Time
Site:	Grand Gulf
Issue date:	01/23/1981
From:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, AECM-81-42, NUDOCS 8102250040
Download: ML20003B615 (3)

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Office of Inspection & Enforcement /f  %

U. S. Nuclear Regulatory Commission Region II Q dl.

101 Marietta Street, N.W. p h Suite 3100 -

g4 Ag (~3 Atlanta, Georgia 30303 6; Attention: Mr. J. P. O'Reilly, Director g  % C

Dear Mr. O'Reilly:

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SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416/417 File 0260/15525/15526 PRD-80/72, Interim Report, Bettis Spring Return Actuators AECM-81/42 On December 22, 1980, Mississippi Power & Light Company noti-fled Mr. P. K. VanDoorn of your office of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) construc-tion site. The deficiency concerns spring guide sleeve shifting internally on safety related actuators supplied by GH-Bettis to Henry Pratt Co.

We have determined that this deficiency is reportable under 10CFR50.55(e). GH-Bettis has reported the deficiency under 10CFR

21. We are currently working with the constructor to determine cause, extent, remedial actions needed, actions required to pre-vent recurrence, and reportability under 10CFR21. We expect to file our final report on this matter on or before June 16, 1981.

This report was due on January 21, 1981, but our T. E. Reaves, Jr. obtained an extension from your Mr. Jack Bryant by telephone on 1/21/81 until this date.

Yours truly,

/ J. P. McGaughy, Jr.

Attachment l cc: See page 2 81022500'10 S OmCIAL COPY

4 MISSISSIPPI POWER & LIGHT COMPANY Mr. J. P. O'Reilly AECM-81/42 NRC Page 2 cc: .Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner Mr. Victor Stello, Director Div. of Insp. & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. B. Taylor South Miss. Electric Power Association P. O. Box 1589 Hattiesburg, MS 39401 r

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- Attachm nt to AECM-81/42

• Page 1 of 1 INTERIM REPORT TO PRD-80/72 I. Description of the Deficiency GH-Bettis Corporation notified the NRC on November 13, 1980, in accordance with 10CFR21 of a ccndition concerning N521C-SR/N522C-SR actuators. Bettis supplies actuators to Henry Pratt Company.

The condition was identified during surveillance testing by the R&D Laboratory of GH-Bettis Corporation of their 521C-SR actuator, where a defect was discovered which may affect actuators presently installed in safety related service. It was found that the spring guide sleeve shifting internally could prevent the movement of the actuator. This failure to actuate can only occur in the normal power stroke, and if the "0" degree position of the valve is ac-tually past the normal "0" of the actuator. This spring stroke of the actuator, which is the normal safety function stroke, is unaffected by this defect. Model N521C-SR-80 actuators were fur-nished only on Henry Pratt Valves supplied the constructor for GGNS Unit #2. A total of five (5) valves purchased have been identified, which function in the containment isolation or con-tainment purge service within the Combustible Gas Control (E61)

System. Four of the above valves are uninstalled and currently in storage. The fif th valve MPIT. Number F007 was returned to Henry Pratt Company for "New loads" testing on March 25, 1980.

Oar Architect / Engineer has evaluated the CH-Bettis 10CFR21 defi-ciency for its effect on safety of plant operations and determined that the cited actuators may not allow the valves to perform their intended function in the event of an accident. Therefore, the condition has- been determined to be- reportable under 10CFR50.55(e) .

II. ' Approach to Resolution to the Problem We will work with the constructor to ensure proper identification of all involved actuators, their impact on safety, and proper cor-rective actions to include prevention of recurrence. Further in-vestigatiort till be conducted to determine 10CFR21 reportability by MP&L/Ccastructor.

'III. Status of Proposed Resolution A total of five (5) invofved valves have been identified and lo-cated. None are currently installed at GGNS. We are currently working with the constructor to determine final impact on safety and to develop proper corrective actions.

IV. Reasons for Delay in Final Report The supplier investigation is still in progress.

V. Final Report Date We expect to file.our final report by June 16, 1981.

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