ML20032D700

Interim Deficiency Rept Re Pressure Door Failure to Provide Adequate Shielding & to Withstand Compartment Design Pressures,Initially Reported 811008.Deficiency Apparently Due to Human Design Error.Final Rept Submitted by 820104

ML20032D700
Person / Time
Site:	Grand Gulf
Issue date:	11/09/1981
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-81-441, NUDOCS 8111170403
Download: ML20032D700 (5)

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]l MISSISSIPPI POWER Etl%%CO'MPANY Helping Build Mississ!ppi-2 US Ol4 P. O. B O X 16 4 0, J A C K S O N. MIS SIS SI P PI 3 9 2 0 5 3l NOV 12 A 8 3J

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- g t-}f N J'x Office of Inspection & Enforcement

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U. S. Nuclear Regulatory Commission Region II

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Attention:

Mr. J. P. O'Reilly, Director

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SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416/417 File 0260/15525/15526 PRD-81/41, Interim Report, Main Steam Door Radiation and Pressure Requirements AECM 81/441 On October 8,1981, Mississippi Power & Light Company notified Mr. P. A.

Taylor, of your of fice, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) construction sita. The deficiency concarns the inadequacy of Pressure Door No. 1A320 to provide adequate shielding be-tween the Main Steam Tunnel and the Auxiliary Building Corridor as well as its inability to withstand compartment design pressures.

Our ir.vestigation into this mat:er is continuing but has determined that this deficiency is reportable under the provisions of 10CFR50.55(e) but not under 10CFR21. The Interim Report is attached. We expect to provide our Final Report on or before January 4, 1982.

Yours trul,

g J. P. McGaughy, Jr.

ACP:dr ATTACHMENT cc: See page 2 g:MCIM8 8111170403 811109

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PDR ADOCK 05000416

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ppg Member Middle South Utilities System l l

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Mr. J. P. O'Reilly AECM-81/441

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Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner Mr. Victor Stello, Director 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 e

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bec: Dr. D. C. Gibbs Mr. D. M. Houston Mr. J. N. Ward U. S. Nuclear Regulatory Commission i

Mr. J. P. McGaughy Division of Licensing Mr. J. D. Heaton Washington, D. C.

20555 Mr. R. S. Trickovic Mr. J. W. Yelverton Mr. Bruce J. Cochran Mr. L. F. Dale Cochran Consulting Company Mr. C. K. McCoy P.O. Box 270503 Mr. T. H. Cloninger Tampa, Florida 33688 Mr. R. A. Ambrosino Mr. R. C. Fron Mr. G. B. Rogers Mr. S. H. Hobbs Mr. L. E. Ruhland Mr. D. L. Hunt Mr. A. G. Wagner Mr. P. A. Taylor Mr. R. F. Phares PRD File File b

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s Attachss.:t to AECM-81/441 s

Page 1 of 2 INTERIM REPORT FOR PRD-81/41 1.

Description of the Deficiency a

Pressure door 1 A320 was determined inadequate in providing sufficient shielding between the Main Steam Tunnel and the Auxiliary Building during normal operating conditions. Also, it had been determined that the pressure retaining capability of the door was inadequate. The door was built to withstand a pressure of 4 psig. The lesign intent of door IA320 is that it maintain a pressure of 15.39 psig. The door must maintain its integrity to prevent over pressurization of the adjacent rooms in the' Auxiliary Building.

Investigative action to determine the extent of the problem has found that door 1A216, located in the Auxiliary Building, is also struc-turally deficient in withstanding a pressure of 15.39 psig. Door 1A216 is not required to provide radiation shielding.

These deficiencies are contained in the Auxiliary Building and are not directly associated with any particular plant system..The deficiencies are applicable to both Unit 1 and Unit 2.

Since the areas have not been turned over to MP&L, 10CFR21 does not apply.

The A/E has determined, that had the deficiencies remained uncorrected, this could have an adverse af fect on plant safety. Under normal oper-ating conditions door 1A320 would not provide the required shielding, i.e., protection from radiation exposure, from the Steam Tunnel to plant equipment or personnel which may be in the Auxiliary Building.

Therefore, the personnel radiation exposure could exceed those dose limits of 10CFR Part 20.

In the event of a pipe break in the Steam Tunnel, the harsh environment which could consist of pressure, temper-ature, and radiation could be released into the Auxiliary Building.

Therefore, the safety-related equipment located in the Auxiliary Build-ing could be exposed to this harsh environment. This harsh environment could exceed the safety-related equipment qualification envelope and the safety of operations of GGNS would not be assured. Therefore, the determination has been made that these deficiencies are reportable under the provisiens of 10CFR50.55(e).

II.

Approach to Resolution _of the Problem The cause for the shielding and pressure deficiency is indeterminate at this time. However, it appears to be a lack of coordination and human error in describing the change in criteria from the current door design pressure of 4 psig to the compartment design pressure of 15.4 psig.

Attachment to AECM-81/441 Page 2 of 2 Our A/E has initiated action to retrofit the doors to achieve the shielding and pressure retention requirements. The design effort for door 1A320 is scheduled for completion by November 13, 1981 and the design ef fort for door.1A216 will be determined upon MP&L's approval of the design approach.

The corrective actions which have been taken or those that will be

-taken to preclude recurrence have not been provided due to the fact that the cause and extent of the deficiency is still under investigation.

III.

Status of Proposed Resolution Our A/E is in the process of determining the cause of the deficiency.

Upon determination, specific corrective actions and actions to preclude recurrence will be formulated. An estimation has been made that the determination of the cause will be completed by December 11, 1981. All actions will be complete prior to fuel load.

IV.

Reason why a Final Report will be Delayed The cause for the change in pressures (i.e. from 4 to 15.4) and a review of dif ferent radiation zones has not been completed.

V.

Date when Final Report will be Submitted We expect to submit our Final Report on this deficiency on or before January 4,1982.

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