ML20054H047
| ML20054H047 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/10/1982 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20054H031 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM GL-82-05, GL-82-5, NUDOCS 8206220522 | |
| Download: ML20054H047 (3) | |
Text
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Carolina Power & Light Compan)Tl ANTA, G EOR 0u SNRC-REGION :;
MAY 101982 32 MAY 13 A 8 32 Mr. James P. O'Reilly, Regional Administrator United States Nuclear Regulatory Commission Region II 101 Marietta Street, N.W., Suite 3100 Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS DPR-71 AND DPR-62 SUPPLEMENTAL RESPONSE TO INFRACTIONS OF NRC REQUIREMENTS
Dear Mr. O'Reilly:
By our letter dated April 30, 1982, Carolina Power & Light Company (CP&L) responded to IE Inspection Report 50-324/82-05 and 50-325/82-05. In that letter, CP&L advised NRC that we would provide on May 7,1982, a supple-mental response addressing the deviation from NRC commitments (Enclosure 1) and a supplemental response to Generic Letter 82-05 (Enclosure 2) concerning interim actions associated with NUREG-0737, Item II.B.3 (Post-Accident Sampling).
This letter is to forward the above outstanding items and document a telephone call between NRC (I&E) and CP&L on May 7, 1982 which extended our response date to May 10.
Should you have any questions, please contact my staff.
Yours very truly, I
C B. J. Furr Vice President Nuclear Operations MSG /lr (n-52)
Enclosures cc:
Mr. D. G. Eisenhut (NRC)
Mr. J. Van Vliet (NRC)
B. J. Furr, having been first duly sworn, dit. d? pose and say that the information contained herein is true and correct to his own personal knowledge or based upon information and belief.
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ENCLCSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 IE INSPECTION REPORT 50-324/82-05 AND 50-325/82-05 RESPONSE TO DEVIATION FROM COMMITMENT Based on the results of the hRC inspection conducted on January 15, 1982 through February 15, 1982 certain activities appeared to deviate from commitments to the Commission as indicated below:
Commitment CP&L's letter dated December 31, 1979, to the NRC documenting licensee actions taken in response to NUREG-0578 and NUREG-0737, stated that the three noble gas effluent radiation monitors installed in shielded containers on the plant stack and turbine building vents would be calibrated quarterly in accordance with the manufacturer's recommendations.
Deviation Contrary to the above, on Feb-uary 9, 1982, the three gas radiation monitors had not been calibrated since April 1981.
Carolina Power & Light Company's Response Carolina Power & Light Company acknowledges that this deviates from commitments made to the Commission in a CP&L letter dated December 31, 1979 This event occurred as a result of establishing the required maintenance procedures for calibration of this instrumentation without including this maintenance procedure in the maintenance scheduling program. The required calibrations were performed on all three radiation monitors by February 25, 1982, and all monitors were found to be in a satisfactory condition. The maintenance scheduling program has been revised to include these tests on a quarterly basis. Appropriate maintenance procedures are currently being revised to ensure that when new maintenance procedures are written or current maintenance procedures are revised, appropriate maintenance scheduling is also completed. This series of revisions will be completed by June 30, 1982.
ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 SUPPLEMENTAL RESPONSE TO GENERIC LETTER 82-05 ADDITIONAL INFORMATION CONCERNING NUREG-3737 ITEM II.B.3 - POST-ACCIDENT' SAMPLING-As provided in our April 23, 1982 response to Generic Letter 82-05, Carolina Power & Light Company (CP&L) has reviewed the compensatory actions presently in place at Brunswick for NUREG-0737 Item II.B.3 (Post-Accident Sampling). As a result of this review, we have determined that the interim actions presently in place at Brunswick for this item are adequate and that no i
additional compensatory actions are needed at this time.
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