ML20010G877

Final Deficiency Rept Re GH-Bettis Spring Return Actuators, Initially Reported on 801222.Spring Guide Sleeve Shifting Internally Could Prevent Movement of Actuator.Caused by Design Deficiency.Actuators Repaired & Redesigned

ML20010G877
Person / Time
Site:	Grand Gulf
Issue date:	09/15/1981
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-81-282, NUDOCS 8109220615
Download: ML20010G877 (4)

Text

MISSISSIPPI POWER & LIGHT COMPANY

]

Eumailbliddll Helping Build Alississippi P. O. B O X 1640, J AC K S O N, MIS SIS SlP PI 3 9 2 05

~

Yssfs$$rYNs%'/r September 15, 1981 Office of Inspection & Enforcement f ?L!no '

/

U. S. Nuclear Regulatory Commission Region II hd~ffQ LU j q

101 Marietta Street, N.W. 2 g { p "9* 9 I98I A -8 Suite 3100 Atlanta, Georgia 30303 ""fg O n g " = [

+ p Attention: Mr. J. P. O'Reilly, Director ,

l -

!.1 \

SUBJECT:

Grand Gulf Nuclear Station Unit 2 Docket Nos. 50-416/417 File 0260/15525/15526 PRD-80/72, Final Report Bettis Spring Return Actuators AECM-81/282 Re ferences : 1) AECM-81/197, 6/16/81

2) AECM-81/42, 1/23/81 On December 22, 1980, Mississippi Power & Light Company notified Mr. P.

K. Van Doorn, of your of fice, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) construction site. The deficiency con-cerns the spring guide sleeve shifting internally on safety related actuators supplied by GH-Bettis to valve manufacturers.

On November 18, 1980, CH-Bettis reported this deficiency to the NRC under the provisions of 10CFR21. Working with our Constructor, we have determined that this deficiency, had it remained uncorrected, could have affected the safety of operations of the nuclear power plant and is thus reportable by us under 10CFR50.55(e). It is not reportable by Mississippi Power & Light under 10CFR21 as explained in our attached final report.

There is a discrepancy in our last report to the NRC dated June 16, 1981, letter AECM-81/197. The attachment reads " Final Report to PRD-80/72." This should have been " Interim Report No. 2 to PRD-80/72."

Yours truly d

J. P. McGaughy, Jr.

l KDS:dr y ATTACHMENI /

lll cc: See page 2 F109220615 810915 gDRADOCK 05000416 Member Middle South Utilities System PDR

i

• l l

l Mr. J. P. O'Reilly AECM-81/282 NRC Page 2 j l

r e: Mr. N. L. Stampley  ;

Mr. R. B. McGehee Mr. T. B. Conner T

Mr. Victor Stello, Director Of fice of Insp: etion & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 3

Mr. G. B. Taylor South Miss. Electric Power Association P. O. Box 1589 Rattiesburg, MS 39401 a

Y f

l s

. . 3 bbe: Mr. D. C. Lutken Mr. J. Leatherman Dr. D. C. Gibbs Manager of BWR-6 Licensing Mr. J. N. Ward General Electric Company Mr. J. P. McGaughy, Jr. 175 Curtner Avenue Mr. J. D. Heaton San Jose, CA. 95125 Mr. R. Trickovic j Mr. J. W. Yelverton ,

Mr. L. F. Dale Mr. D. M. Houston Mr. C. K. McCoy U. S. Nuclear Regulatory Commission Mr. T. H. Cloninger Division of Licensing Mr. R. A. Ambrosino Washington, D. C. 20555 Mr. A. J. Iosue Mr. G. B. Rogers Mr. S. H. Hobbs Mr. J. Matore Mr. L. E. Ruhland U. S. Nuclear Regulatory Commission Mr. D. L. Hunt Division of Licenr.ing Mr. A. G. Wagner Washington, D. C. 20555 Mr. P. A. Taylor PRD File File t

t

- Attcchment to AECM-81/282 Pcg2 1 cf 2 FINAL 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 condition concerning N521C-SR/N522C-SR actuators. Bettis supplies actuators to several valve manufacturers. The condition was identified during surveillance testing by the R&D Laboratory of GH-Bettis Corporation of their $21C-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 actually past the normal "0" of the actuator. The spring stroke of the actuator, which is the normal safet- I.o; tion stroke, is unaf fected by this defect.

Model N51C-SR-80 actuators were furnished on Henry Pratt Valves supplied to our Constructor for GGNS Unit 2. A total of five (5) of these valves have been purchased for Combustible Gas Control (E61) System. Four of the above valves are currently in storage. The fif th valve, MPL Number Q1E61F007, was returned to Henry Pratt Company for "new loads" testing on March 25, 1980.

This deficiency does not apply to the NSSS vendor.

II. Analysis of Safety Implications Our Constructor has evaluated the identified valves with the defective GH-Bettis actuators on them for ef fect on safety of plant operations and has determined that the cited actuators may not allow the valves to perform thr4.r intended function in the event of an accident. Therefore, the condi-tion has been determined to be reportable under 10CFR30.55(e). It is not reportable under 10CFR21 because the af fected items have not been turned over to MP&L.

III. Corrective Actions Taken The cause of the probics was a design deficiency as reported by GH-Bertis Corporation to the NRC. The extent is limited to five (5) actuators rounted on valves which function in the containment isolation or containment purge service within the Combustible Gas Control (E61) System.

To correct the deficiency, GH-Bettis has redesigned the actuator. The five (5) identified Grand Gulf actuators will be repaired in accordance with prescribed procedcres furnished by GH-Bettis. Repair of these actuators is expected to be completed by October 31, 1981. To preclude recurrence of the condition, the manufacturer has issued an Engineering Change Notice to correct the problems with the defective manufactured parts.

_ _