ML20195H154
| ML20195H154 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/08/1988 |
| From: | Bliss H COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 4769K, NUDOCS 8806280230 | |
| Download: ML20195H154 (4) | |
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'N Commonwealth Edison d One First National Plaza Chicago, Illinois
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' Address Reply to: Post Offica Box 767
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Chicago, Illinois 60690 0767 June 8, 1986 Mr. A. Bert Davis Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 subject:
LaSalle County Station Units 1 and 2 Response to Inspection Report Nos.
50-373/88009 and 50-374/88009 NRC Docket Nos. 50-373 and 50-374 Reference (a):
Letter dated May 10, 1988 from W.D. Shafer to Cordell Reed.
Dear Mr. Davis:
This letter is in response to the inspection conducted by Messrs.
R.A. paul, W.J. Slawinski and M.A. Kunowski, between March 27 and April 7, 1988, of certain activities at LaSalle County Station. Reference (a) indicated that certain activities appeared to be in noncompliance with NRC requirements. The Commonwealth Edison Company's response to the Level IV violation with 3 examples identified in the Notice of Violation is provided in
- the Attachment.
If you have any further questions on this matter, please direct them to this office.
Very truly yours, 8806280230 880608.
DR ADOCK 0500 H. E. Bliss Nuclear Licensing Manager 1m Attachment 1
C6 E
cc: NRC Resident Inspector - LSCS 1
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4769K 16
ATTACHMENT VIOLATION:
IR 373/88009-01A,B,C IR 374/88009-OlA,B,C Technical specification 6.2.B. requires that radiation control procedures be maintained, made available to all personnel, and adhered to.
a.
LaSalle Radiation Protection Procedure (LRP-1310-4) requires that the Respirat>rl Equipment Log Sheet include the RCT's initials verifying that the individual who receives respiratory equipment is qualified for the respiratory equipment.
Contrary to the above, during this inspection information on several Respiratory Equipment Log Sheets for March did not include RCT initials.
(373/88009-01A) b.
LaSalle Radiation Protection Procedure (LRP-1480-4) requires that individuals using friskers survey themselves by moving the probe slowly (one to two inches per second) over the area of interest.
Contrary to the above, two workers who were observed at the R-5 line (turbine building) frisker station were noted by the inspectors to perform very rapid, superficial frisks.
(373/88009-01C) c.
LaSalle Radiation Protection Procedure (LRP-11670-4) states that ALARA reviews must be amended or rewritten when actual radiological conditions are significantly different than those that were present when the initial ALARA reviews were performed.
Contrary to the above, an ALARA review prepared for flapping operations on the Unit 1 feedwater nozzles was not amended or rewritten when actual radiation conditions were found to be significantly higher than the radiation fields that were present when the initial ALARA review was performed for a similar job in the Unit 2 drywell in 1987.
Two workers exceeded an administrative dose limit while working on the job.
(373/88009-01B) 373/88009-01A CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED The RCTs were instructed in the importance of completing the Respiratory Equipment Log and the supervisory oversight of this activity was increased to ensure compliance. Additional manpower was assigned to the control point area to help during peak periods.
The logkeeping of respirators has improved following these actions.
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. CORRECTIVE ACTION TAKEN TO AVOID FURTHER NONCOMPLIANCE
.LRp 1310-4 will be revised to allow the Respiratory Equipment Log to be kept via a computer program. The Technical Staff and Health physics are in the process of developing the computer based recordkeeping program.
DATE OF FULL COMPLIANCE The station is currently in full compliance. The computer based recordkeeping program is scheduled to be operational by June 15, 1988.
323/88009-01B CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED Station procedure LRp 1160-4, "ALARA Action Review", was revised to include specific criteria for the evaluation of actual dose rates that are significantly different than those present when the initial ALARA review is performed. The dose rate upon which the ALARA review was based is listed on the ALARA review form. When the criteria are met, the Radiation Work permit is modified to include the phrase, "If actual dose rates are greater than 25% above the maximum expected dose rate, AMEND or REWRITE the ALARA review as applicable (LRp-1160-4, Step D.2)."
This is effective because it gives the personnel in the field the information necessary to comply with this procedure.
l' CORRECTIVE ACTION TAKEN TO AVOID FURTHER VIOLATION The station believes that the corrective actions above which were implemented during the inspection are sufficient to avoid further l
violation.
DATE OF FULL COMPLIANCE The station is currently in full compliance.
373/88009-01C CORRECTIVE ACTION TAKEN AND RESULTS ACHIEVED The station has placed additional emphasis on the workers to perform i
proper frisking. Station Management has reinforced the expectations in these areas to all workers including contractors.
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.. CORRECTIVE ACTION TAKEN TO AVOID FURTHER VIOLATION-The Personnel Contamination Event Reduction Task Force is looking closely at the point at which contamiliation is detected. The Task Force has made recommendations to ensure compliance with Station Procedures.
This process is continuing.
In addition, the station Radiation Protection Technicians have been given specific instructions to immediately correct observed deficiencies in this. area.
DATE OF FULL COMPLIANCE The station is currently in full compliance, 4769K