ML20082A642

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Responds to NRC Re Violations Noted in IE Insp Rept 50-482/83-12.Corrective Actions:Nonconformance Rept Issued to Identify & Disposition Weld & Radiograph & Welds F-204,F-305 & F-405R-2 Under Evaluation
ML20082A642
Person / Time
Site: Wolf Creek 
Issue date: 10/07/1983
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Seidle W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20082A638 List:
References
KMLNRC-83-128, NUDOCS 8311180206
Download: ML20082A642 (4)


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t KANSAS GAS AND ELECTRIC COMPANY THE ELECTAC COMPANY meme GLENN L NOESTER VsCE Pef $.Df 47. feuCLEAR October 7,1983 Mr. W.C. Seidle, Chief 7.

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Reactor Projects Branch 2 U.S. Nuclear Regulatory Commission l I Region IV g g gg 611 Ryan Plaza Drive, Suite 1000 j

i Arlington, Texas 76011

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b KMLNRC 83-128 Re:

Docket No. STN 50-482 Subj: Response to Inspection Report STN 50-482/83-12

Dear Mr. Seidle:

This letter is written in response to your letter of August 26, 1983, which transmitted Inspection Report STN 50-482/83-12. Some of the information necessary to determine corrective action was not available within 30 days of the subject Inspection Report date. Therefore, on September 23, 1983, Mr. Otto Maynard of Kansas Gas and Electric Company and Mr. William Johnson of the Nuclear Regulatory Commission, Region IV, agreed to extend the response due date to October 7,1983.

As requested, the violations identified in the Inspection Report are being addressed in three parts:

a) The corrective steps which have been taken and the results achieved 1 b) Corrective steps which will be taken to avoid further violations; and c) The date when full compliance will be achieved.

VIOLATION 50-482/83-12-01 Finding:

10CFR50.55a (3) requires that reactor coolant pressure boundary piping meet the ASME III Boller and Pressure Code. The ASME III Code directs that radiography be performed in accordance with ASME V Code. The ASME V Code, Article 2, paragraph T-263.1, Placement of Penetrameters, requires that, where feasible, the penetrameter must be placed adjacent to the weld.

8311180206 831010 PDR ADOCK 05000482 O

PDR 201 N. Market - Wictuta, Ka,1sas -I fail Address: PO. Box 208 i Wichita, Kansas 67201 - Telo phone: kea Code (316) 261-6451

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-Mr. W.C. Seidle KMLNRC 83-128 October 7,1983 Finding (continued) :

Contrary to the above, on or before June 6,1983, Dravo Corporation Pipe radiograph 950-D, had penetrameter placed in the weld area at sectors 1-2 and 2-1.

Response

a) Corrective steps which have been taken and results achieved:

Nonconformance Report (NCR) ISNil652PW was issued to identify and disposition the subject weld and radiograph.

(Note: Violation 50-482/83-12-01 identified the subject radiograph as Radiograph 950-D; actual number is Radio-graph 439-D).

The weld in question was radiographed and accepted on GEO Report PBT-RT-10675 on 6/16/83. The NCR was closed on 9/1/83.

b) Corrective steps which will be taken to avoid further violations:

KG&E QA reported on Surveillance Report S-669 dated 7/13/83 that a review of the available Dravo radiographs found no other nonconformances. Additionally, in August 1980, the GEO Level III inspector reviewed radiographs for 579 Dravo welds, and none of these were rejected for improper penetrameter placement. Based on the above investigations, KG&E concludes that this violation is an isolated incident (occurrence) requiring no additional,

corrective action.

c) Date when full compliance will be achieved:

All corrective actions have been completed.

VIOLATION 50-482/83-12-02 Finding:

10CFR50.55 (a) requires that reactor coolant pressure boundary piping meet the ASME III Boiler and Pressure Vessel Code. The ASME III Code, paragraph NB-5300, requires that unacceptable weld defects be removed or reduced to an acceptable limit. It furthar defines unacceptable discon*innitier any e3cngated an

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' " indication exceeding specified lengths.

Mr. W.C. Seidle KMLNRC 83-128 October 7, 1983 Finding (continued) :

Contrary to the aLove, on or before June 6,1983, the reactor coolant pressure boundary weld F-104, pipe line RC-06-BCR-29, was determined to have elongated indications which exceed the specified lengths which were erroneously accepted on Noncon-formance Reports ISN3207MN and ISN2950M.

Response

a) Corrective steps which have been taken and results achieved:

Nonconformance Report (NCR) 1 SN-ll664-PW has been issued to document the questionable weld indications and to track the resolution of the identified weld concerns. Additional radiography has been performed using special radiography techniques to aid in the weld evaluations.

Three different exposures were made for weld F-104R-1 and one exposure appeared to exhibit a questionable indication.

Westinghouse has recommended that this indication be removed for this weld.

Welds F-204, F-305 and F-405R-2 are currently under evaluation.

Additional radiography may be required before a final dis-position can be made for these welds, b) Corrective steps which will be taken to avoid further viola tions :

Weld F-104R-1 will be reworked to remove the questionable indication. The evaluation of welds F-204, F-305, and F-405R-2 will be completed and reworked as necessary.

In addition to the corrective actions being taken to resolve the questionable weld indications, Daniel Internat".onal Corporation will revise Construction Procedure AP-VI-05.

This revision will require all final NDE results for welds /

base metal, not within Daniel's scope of responsibility and having unacceptable indications, to be documented on NCRs and forwarded to the appropriate design organization for disposition.

NCRs are not normally generated when the condition in question has already been dispositioned " Accept-as-is" on w a previou; *CA.

Me,' GWever, appropriate to "re-evaluate" the condition when subsequent work has been performed which may adversely affect the condition and invalidate the original acceptance.

Mr. W.C. Seidle 7JENRC 83-128 October 7, 1983 Response (continued) :

In the case cited by the subject Inspection Report, new NCRs should have been generated when the final code-radiographs were complete so that Westinghouse could evaluate the final weld configuration. Procedure AP-VI-05 will be revised to clarify that nonconformances cannot be accepted on the basis of previously dispositioned NCRs if the nonconformance has been or could have been altered by subsequent work.

c) Date when full compliance will be achieved:

The evaluation of welds F-204, F-305 and F-405R-2 and the revision of AP-VI-05 will be completed by November 30, 1983. The rework of weld F-104R-1 and any rework identified for weld F-204, F-305 and F-405R-2 will be completed prior to primary hydrostatic testing.

Supporting documentation for the responses provided above is available for review at the Wolf Creek job site. If you have any further questions concerning this response, please contact me or Mr. Otto Maynard of my staff.

Yours very truly, M

Glenn L. Koester Vice President - Nuclear GLK:bb cc: WSchum/Asmith

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