View source for 1CAN068307, Discusses Plans to Close Out Open Item 7725-29 in IE Insp Rept 50-313/77-25 Re Fresh Fuel Insp & Storage.Closeout Based on Extensive Acceptable/Approved Insp Criteria in B&W & C-E Fuel Mfg Qa/Qc Programs

{{Adams
| number = ML20082L104
| issue date = 06/30/1983
| title = Discusses Plans to Close Out Open Item 7725-29 in IE Insp Rept 50-313/77-25 Re Fresh Fuel Insp & Storage.Closeout Based on Extensive Acceptable/Approved Insp Criteria in B&W & C-E Fuel Mfg Qa/Qc Programs
| author name = Marshall J
| author affiliation = ARKANSAS POWER &amp; LIGHT CO.
| addressee name = Seidle W
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000313
| license number = 
| contact person = 
| document report number = 1CAN068307, 1CAN68307, NUDOCS 8312050412
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}

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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501)371-4000 June 30, 1983 1CAN068307 Mr. W. C. Seidle, Chief r
t g-@MDM D         j Reactor Project Branch #2                                     Li.
i U. S. Nuclear R     latory Commission Region IV                                                     i' .s    JUL - 5 883 611 Ryan P1aza Drive, Suite 1000                                                - - -     d Arlington, TX 76011
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==SUBJECT:==
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Closecut of Open Item 7725-29 (Ref: Inspection Report 50-313/77-25)
Gentlemen:
During a recent review of various NRC commitments, a discrepar$cy was discovered relative to an open item (01) cited in Inspection Report 50-313/77-25 dated January 3,1978,(1CNA017806).          Specifically, open item 7725-29 stated
            " Insertion of the dummy control rod to assure proper fit is to be added to Procedure 1503.02, (Fresh Fuel Inspection and Storage)." The open item was subsequently closed by NRC iallowing the revision of Appendix B to Procedure 1503.02, Fresh Fuel Receipt, and Form NF11-2 to require a controls rod be used to verify proper fit during the new fuel receipt inspection.
A subsequent revision, Revision 3 of Procedure 1503.02, now makes the requirement for control rod insertion optional. Our review of 01 7725-29 reinforces our position that this inspection is no longer necessary for the following reasons. Both Babcock and Wilcox and Combustion Engineering fuel manufacture quality assurance / quality control programs have extensive acceptable / approved inspection criteria. The AP&L inspection is primarily for detection of receipt / handling damage and not reverification of dimensional tolerances. The final safety significant check of control component to fuel 8312050412 830630 PDR ADOCK 0500r'313 P                  .'DR
((O        I MEMBER MIDDLE SOUTH UTILITIES SYSTEM

  , ,   , 'wMr. W. C. Seidle                                          June 30, 1983 assembly interface is acceptable rod drop times as given in the Technical Specifications. Thus, the additional requirement for control component insertion is not. justifiable.
Based on the above, we do not plan to revise the affected procedure to reinstate the requirement for such inspections.
Very truly yours,
                                                    &         h John R. Marshall Manager, Licensing JRM:RJS:sl cc: Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Norman M. Haller, Director Office of Management & Program Ar.alysis U. S. Nuclear Regulatory Commissf oi Washington, D. C. 20555
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