ML19330A662

Responds to NRC 800523 Ltr Re Violations Noted in IE Insp Rept 50-482/80-09.Corrective Actions:Daniel Mechanical Supervision Instructed by Const Manager Re WP-I-01 Procedures

ML19330A662
Person / Time
Site:	Wolf Creek
Issue date:	06/24/1980
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19330A659	List: ML19330A662
References
NUDOCS 8007290017
Download: ML19330A662 (4)

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June 24, 1980 Mr. W.C. Seidle, Chief Reactor Construction and Engineering Support Branch U.S. Nuclear Regulatory Commission Region IV

, 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 KMLNRC-005 Ref: NRC Docket No. STN 50-482/Rpt. 80-09

Dear Mr. Seidle:

This letter is written in response to your letter of May 23, 1980, which transmitted Inspection Report 50-482/80-09. As requested, each finding is being addressed in three parts:

a) Corrective steps which have been taken and the results achieved; b) Corrective steps which have been taken to avoid further noncompliance; and c) The date when full compliance will be achieved.

Finding On April 29, 1980, approximately ten stainless steel spool pieces and fittings, including IEJ-01-S-010/12 and 1PCl-EN-01-S-007/ll2 were observed standing on the floor in water and excessive dirt on the lower level of the Auxiliary Building.

Response

a) When the above infraction was pointed out to Daniel forces, they immediately brought the material into compliance with storage requirements.

b) Daniel's mechanical supervision was instructed by the Construction 201 N. Market - WWuta, Kansas - Maol Address PO. Box 200 / Wichsta. Kansas 67201 - Telephone: Area Code (316) 261-6451 80072900l? -

Mr. W.C. Seidle KMLNRC-005 June 24, 1980 Manager to re-emphasize- the procedural requirements of WP-I-01 with personnel responsible for the incorrect storage of the material, Storage and protection of piping will be audited by both KG&E and Daniel QA organizations for the next three months to verify continued compliance with project requirements.

c) Full compliance was achieved on April 30, 1980.

Finding On April 29, 1980, during the observation of the spalled concrete in the reactor cavity, the IE Inspector identified cracks in the concrete adjacent to the stainless steel refueling cavity seal ring. The damage apparently occurred during the vessel setting procedure and had not been reported to Quality Control or Engineering.

During a site tour conducted November 28, 1979, the IE Inspector identified broken concrete in six separate areas around the Fuel Building fuel transfer canal in placement No. OC-611-SO4. The damaged areas had not been identified to Quality Control or Engineering. This item had previously been considered an unresolved item.

Response

a) On April 29, 1980 DR #1SD-3855-C was initiated to identify and document the damaged concrete adjacent to the reactor cavity seal area. This DR was upgraded to NCR No. ISN-2015-C on 5/1/80 and sent to Bechtel to be evaluated and dispositioned. Bechtel has since dispositioned the NCR by specifying the repair procedure.

On 11/29/79 DR No.1SD-2863-C was initiated to identify and document damaged concrete around the fuel building transfer canal.

This DR was upgraded to NCR No.1SN-1600-C on 1/10/80 and was for-warded to Bechtel to be evaluated and dispositioned. Bechtel has dispositioned the NCR by specifying the repair procedure. The work has been completed, inspected and approved by quality control.

b) By letter dated June 12, 1980 Daniel's Project Manager instructed his top managers to remind employees that Section 4.1.1 of procedure AP-VI-02 requires all Daniel personnel who identify a material non-conformance or a nonconforming activity to bring it to the attention of Quality Control or Engineering personnel.

c) As indicated above, damaged concrete around the transfer canal was repaired. The repair of concrete around the reactor cavity seal area and completion of gang box training sessions on procedure AP-VI-02 will be completed by July 1, 1980.

Mr. W.C. Seidle KMLNRC-005

• June 24, 1980 Finding.

During in-place relative density testing of the Ultimate Heati Sink (UHS)

Dam, a change in the test acceptance criteria was initiated by the Level I - soils Inspector without procedural authorization. Specifically, the reference to Proctor Density Test No. LW-60 in Field Density Test No. LQ-222 was changed to Proctor Density Test No. LW-81 in Field Density Tert No. LQ-223, which was a retest of No. LQ-222.

Response

a) On 4/9/80 during placement of soil on the ultimate heat sink dam density testing was performed as required by specification.

During the testing a soils Inspector noted a change in material from LW-60 to LW-81. He noted the change on his test record.

The Resident Geotechnical Engineer agrees that from a technical e .adpoint the Inspector took the correct action.

b) In reviewing the procedure which controls soils testing (QCP-II-102) we find that the responsibilities for selection of which proctor test to use is not clearly delineated. Therefore, responsibility for the initial selection of a proctor and subsequent changes will be added to procedure QCP-II-102. Prior to issuance of the revised procedure the Lead QC Inspector (Soils) will review and approve all proctor changes made by the Soil Inspectors.

ci A revised procedure will be in effect and full compliance will be achieved by Augu.3t 1, 1980.

Finding Kansas Gas and Electric Company did not provide a written report within 30 days concerning spalling of concrete in the reactor cavity which was initially reported as a construction deficiency (considered to be a reportable deficiency under 10CFR50.55(e) to the Region IV office on March 7,1980.

An interim report was issued on May 14, 1980.

Response

a) As indicated above a review of our records indicates that we did provide an initial verbal report to Mr. C. Oberg on March 7 regarding damaged concrete at elevation 2021'-7" adjacent to the . reactor cavity which was considered to be a potential 50.55(e) item. We failed to get our record of this notification into our tracking system and therefore missed issuing a written report before April 7.

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Mr. W.C. Seidle KMLNRC-005 June 24, 1980 b) When advised on May 9 by Mr. C. Oberg that a report was overdue, we proceeded to prepare the report which was sent to you on May 14. To prevent recurrence, we have checked with Mr. C. Oberg to be sure we are tracking all of the items which have been reported.

c) The NCR's which were issued against the damaged concrete around the reactor cavity at elevation 2021'-7" have now been evaluated and dispositioned by Bechtel. As indicated in our May 15 report, we will report further on this matter by June 30, 1980.

Please advise if you need additional information.

Yours very truly,

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