ML20197A635
| ML20197A635 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/22/1986 |
| From: | Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-11552, NUDOCS 8605120355 | |
| Download: ML20197A635 (2) | |
Text
T "r, D DA/RYLAND h
k OOPERAT/VE PO BOX 89 M5 EAST AV SOUTH t A CROSSE WSCONS:N M601 (f>08) 788 4000 April 22, 1986 In reply, please refer to LAC-11552 DOCKET No. 50-409 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 RESPONSE TO NOTICE OF VIOLATION FROM INSPECTION REPORT 50-409/86003 (DRSS)
Reference:
(1) NRC Inspection Report 50-409/86003 (DRSS) dated March 28, 1986.
Dear Mr. Keppler:
This submittal is in repsonse to the inspection report of March 28, 1986 (Reference 1) regarding a Notice of Violation found during this inspection.
Our response is attached.
If you have any questions regarding this submittal, please contact us.
Sincerely, DAIRYLAND POWER COOPERATIVE
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4-James W. Taylor General Manager JWT:LLN:sks Attachment d
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cc: NRC Resident Inspector g'
Mr. John Stang, LACBWR Project Manager
%C Document Control Desk I
8605120355 860422 WP4.41 PDR ADOCK 0500 9
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"h' ATTACHMENT 1 NRC Notice of Violation As a result of the inspection conducted on March 10-14, 1986, and in acconiance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part i, Appendix C (1985), the follouing violation was identified:
Technical Specification 6.11 requires that procedure for personnel radiation protection be prepared consistent uith the requirenanta of 10 CFR 20 and shall be approved, maintained, and adhered to.
Procedure HSP-02.6, Section 5.9, requires that beta dose equivalent rates be determined along uith gama dose equivalent rates if piping or components of systems are opened, drained, or in areas where surface contantination in excess of 500,000 dpm/ft2 emearable is evident or expected.
Contn1ry to the above, beta dose equivalent rates vere not determined or known while workers performed tasks in the reactor head cavity area where amearable 2
contamination levels on the cavity valls vert up to 7,000,000 dpm/ft.
This is a Severity E,evel IV violation (Supplement IV).
DPC Response The importance of determining beta dose equivalent rates has been re-addressed to the Health Physics Technicians. Beta surveys will be performed as per HSP-02.6, Section 5.9, in the future. Special Work Permits (SWP) covering work on open contaminated systems conponents will include the requirements for a beta dose equivalent rate determination in the special requirements section.
WP4.41