ML20072U385

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Supplemental Interim Deficiency Rept PRD-81/29 Re Incorrectly Welded Spokes on Bellows End Sleeves of Penetration Assemblies Mfg by Temp Flex Co.Initially Reported on 810529.Final Rept by 831007
ML20072U385
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/31/1983
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-83-2-0003, AECM-83-2-3, NUDOCS 8304110295
Download: ML20072U385 (3)


Text

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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 16 4 0, J A C K S O N, MI S SI S SIP PI 3 9?D S

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'A March 31, 1983

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JAMES P. McGAUGHY, JR.

S vece persiosur

,3 Of fice of Inspection & Enforcement h

3 U. S. Nuclear Regulatory Commission Region II j

101 Marietta Street, N.W.

o Suite 2900 Atlanta, Georgia 30303 Attention:

Mr. J. P..O'Reilly, Regional Administrator

Dear Mr. O'Reilly:

SUBJECT:

Grand Gulf Nuclear Station Unit 2 Docket No. 50-417 License No. NPF-13 File 0260/15525/15526 PRD-81/29, Supplemental Interim Report, Temp Flex Penetration Bellows Assemblies AECM-83/2-0003

Reference:

AECM-81/385, 10/6/81 On May 29,1981, Mississippi Power & Light Company notified Mr. V.

Brownlee, of your office, of a Potentially Reportable Deficiency (PRD) at the Grand Golf Nuclear Station (GGNS) construction site. The deficiency concerns incorrectly welded spokes on the bellows end sleeves of penetration assemblies manufactured by the Temp Flex Company of Compton, California.

This deficiency was determined to be not reportable and was closed out for Unit I and Unit 2 in Inspection Report 50-416/81-50 and 50-417/81

2.

However, on March 1,1983, MP&L informed Mr. R. Butcher, of your office, that the PRD was being re-opened to assure that the deficiency is adequately addressed for Unit 2.

Our investigation into this matter is continuing. Details are provided in the attached Interim Report.

MP&L expects to submit a Final Report by October 7, 1983.

Yours truly, M

p B304110295 030331 g

PDR ADOCK 05000417 J. P. McGaughy, Jr.

PDR S

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ATTACHMENT cc:

See page 2 Member Middle South Utilities System

d Mr. J. P. O'Reilly

'AECM-83/2-0003 NRC Page 2 cc:

Mr. J. - B. Richard Mr. R. B. McGehee Mr. T. B. Conner Mr. Richard C. DeYoung, Director 4

Office of Inspection & 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 I

s. l,?

7 Attachment to AECM-83/2-0003 Page 1 of I SUPPLEMENTAL INTERIM REPORT TO PRD-81/29 1.

Description of the Deficiency Penetration bellows assemblies manufactured by Temp Flex have exhibited cracked and broken ' welds at the junction of " Spokes" to the bellows end sleeves.. Contrary to' drawing requirements, fillet welds were used instead of full penetration welds.

This deficiency af fects the Nuclear Boiler System (B21), Standby Liquid Control System (C41), Residual Heat Removal System (E12), Reactor Core Isolation Cooling System (E51), Reactor Water Cleanup _ System (G33) and

^ the Fuel Pool Cooling and Cleanup System (G41).

This deficiency is applicable to Unit 2 only, and does not apply to the NSSS supplier. The safety implications of this deficiency are unknown at this time.

II.

Approach' to Resolution of the Problem The cause and extent of the deficiency are under investigation.

Corrective and remedial actions will be addressed upon completion of the investigation.

A cursory inspection of some of the bellows assemblies in the' field has confirmed that similar problems of broken and incorrect welds exist in the Unit 2 bellows assemblies as did in Unit 1.

Nonconformance report l

NCR 6535 has been initiated to document and track all nonconforming con-ditions that are found from a complete inspection of each Unit 2 bellows assembly. supplied under Bechtel Specification 9645-M-318.0.

Upon comple-

. tion of the inspections, the NCR will be dispositioned and processed in accordance with applicable procedures. Those assemblies not in the field l

will be brought up from Bechtel's Natchez warehouse for inspection and be sent to Bechtel's Vicksburg Fabrication Shop for repair / rework if required.

l l

III.

Status of Proposed Resolution The safety implications, cause, extent and corrective actions are sche-i duled to be resolved by August 26, 1983, based on the results of the investigatin described above.

IV.

Reason Why a Final Report Will Be Delayed Due to the limited ' scope of construction at this time, the investigative actions identified above are scheduled to be completed by July 1, 1983.

l.

(2 V.

Date.When a Final Report Will Be Submitted h

MP&L expects to submit a Final Report, concerning this matter, by October i

7, 1983.

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