ML18005A668
| ML18005A668 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/26/1988 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CON-NRC-647 HO-880220-(O), NUDOCS 8811020049 | |
| Download: ML18005A668 (6) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8811020049 DOC.DATE: 88/10/26 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION WATSON,R.A.
Carolina Power
& Light Co.
RECIP..NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET
- 05000400,
'R 05000400 1
'S NOTES:Application for permit renewal filed.
SUBJECT:
Responds to NRC 880926 ltr re violations noted in Insp Rept-50-400/88-25.
DISTRIBUTION CODE
, IE01D COPIES RECEIVED:LTR ENCL 4 SIZE-TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS DEDRO NRR/DLPQ/PEB 11 NRR/DOEA DIR ll NRR/DREP/RPB 10 NRR/PMAS/ILRB12 OF I IEBERMAN,J RE+ FILE~
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1 RECIPIENT ID CODE/NAME BUCKLEY,B AEOD NRR MORISSEAU,D NRR/DLPQ/QAB 10 NRR/DREP/EPB 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT OGC/HDS1 RES/DSR DEPY NRC PDR RESL MARTIN,D COPIES LTTR ENCL 1
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8 R
D NOTE 'ZO ALL RIES" RECIPIENIS'LEASE HELP US TO RIXN3CB %ASTE!
CGMZLCT 'IHE DOCUMENZ CABAL DESK, ROOM Pl-37 (EXT.20079)
TO EXAMINATE YOUR NAME FRCH DISTRIKEXGN LISTS FOR DOCGMEWIS KRJ DONiT NEED)
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 25 ENCL 25
'i'arolina Power S Light Company HARRIS NUCLEAR PROJECT P.
O. Box 165 i New Hill, North Carolina 27562 OCT 261988 File Number'SHF/10-13510E Letter Number:
HO-880220 (0)
NRC-647 Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO ~ 50-400 LICENSE NO. NPF-63 REPLY TO A NOTICE OF VIOLATION Gentlemen:
In reference to your letter of September 26, 1988, referring to I.E. Report RII:
50"400/88-25, the attached is Carolina Power 6
Light Company's reply to the violation identified in Enclosure 1.
It is considered that the corrective actions taken/planned are satisfactory for resolution of the item.
Thank you for your consideration in this matter.
Very truly yours, R. A. Watson Vice President Harris Nuclear Project MGW:acm Attachment Ih cc:
Messrs.
W. H. Bradford (NRC-SHNPP)
B. C. Buckley (NRC)
M. C. Ernst (NRC) 8811020049 881026 PDR ADOCK 05000400 O
PDC MEM/HO-8802200/1/OS1
Attachment to CPSL Letter of Res onse to NRC I.E.
Re ort RII:
50-400 88-25 Violation Re orted Violation.'echnical Specification 6.8.1 requires that written procedures be established and implemented covering procedures outlined in Appendix A of Regulatory Guide 1.33, Rev.
2, February 1978.
Surveillance and Calibration procedures are identified in,Appendix A of the Regulatory Guide.
V 1.
A surveillance procedure, Operational Surveillance Procedure (OST)-1826, Train "B" SI ESF Response Time Test, requires the lifting of leads in order to test the auxiliary feed water (AFW) pumps.
Contrary to the above, OST-1826-was established inadequately, in that the procedure did not require the main feedwater pump switches be placed in the "Stop" position prior to reconnecting the AFW lifted
- leads, which resulted in an inadvertent start of the "B"
train AFW pump on August 9, 1988..
2.
A calibration procedure, Maintenance Surveillance Test (MST)-I-0401, Containment Hi Range Accident Radiation Monitor RM-01CR-3589-SA Calibration, requires calibration data base changes to be entered into the containment Hi Range Accident Radiation Monitor, RM-01CR-3589-SA.
Contrary to the
- above, MST-I-0401 was not implemented, in that on August 8,
- 1988, calibration data base changes for monitor RM-01CR-3589-SA were inadvertently entered into the Control Room Area and Radiation Monitor RC-21RR-3560-SA.
This is a Severity Level IV violation (Supplement I).
Denial or Admission and Reason for the Violation:
The violation is correct as stated.
1.
On August 9,
- 1988, with the plant shutdown in Mode 5,
surveillance test OST-1826, ESF
Response
Time, Train B, was being performed.
OST-1826 required lifting electrical leads to ensure that the "B" Train Auxiliary Feedwater (AFW)
Pump would start as a result of a Safety Injection (SI) signal, but not due to the trip of both Main Feedwater (MFW) Pumps, which occurs as a result of the SI signals This portion of the test was completed satisfactorily',
- however, when the disconnected electrical leads were placed back in the pretest
MEM/HO-8802200/2/OS1
Attachment to CP6L Letter of Res onse to NRC I.E. Re ort RII:
50-400 88-25 Violation (continued The cause of the event was a procedure deficiency.
The test procedure failed to instruct the operator to place the "B" MFW Pump control switch in the "STOP" position before reconnecting the electrical leads in the MFW Pump control
'ircuitry.
2.
On August 8,
- 1988, while performing MST-I0401, Containment High Range Accident Monitor RM-01CR-3589SA Calibration, in the Main Control
- Room, an I6C technician placed the "NORM/SUPV",key switch located on the RM-23 bay in the "SUPERVISOR" mode.
In this
- mode, any setting of the eight RM"23s in the bay may be changed.
The technician was aware of which monitor was to be calibrated
- However, the act of reading the next step in the procedure required the technician to look away from,the panel.
When he turned to implement the action, he mentally transposed the positioning of the monitors and changed 'he conversion factor on the wrong monitor (RM-21RR-3560A).
This immediately set off the RM-21RR-3560SA alert alarm in the Control Room.
The Shift Foreman asked if he had caused the alarm.
The technician rechecked the panel and discovered that he had changed the setting on the
~rong monitor.
He immediately notified the Shift Foreman.
Once the correct values were entered into RM-21RR"3560SA, the alarm cleared.
Corrective Ste s Taken and Results Achieved:
1.
The Auxiliary Feedwater System functioned as designed during the test, and proper operation was verified by the Control Operator.
No water was actually injected into the steam generators because of the valve lineup required by the test procedure.
2 The correct setting was re-entered into the Control Room Area Monitor, RM-21RR-3560SA to clear the alarm.
Corrective Ste s Taken to Avoid Further Noncom liance.
1.
Procedures OST-1825 "ESF Response Time, Train A" and OST-1826 "ESF
Response
Time, Train B" will be revised before further use to ensure that both MFW Pump control switches are placed in the "STOP" position prior to lifting/reconnecting electrical leads in the MFW/AFW circuitry.
MEM/HO-8802200/3/Osl
Attachment to CP&L Letter of Res onse to NRC I.E.
Re ort RII:
50-400 88-25 Violation (continued) 2.
The responsible technician was counseled on the importance of procedure compliance and attention to detail.
Maintenance Work In Progress'ags were created for use on the Radiation Monitors while being tested.
These tags are customized for these monitors.
These tags are
- colored, plastic templates which attach to and encircle the RM-23 panel face being worked on.
The template highlights the RM-23 compared to the others such that, as the technician glances back and forth between his procedure and the RM-23, his attention will be drawn to the RM-23 with the template around it.
The use of the above tags will be incorporated into the appropriate maintenance and radiation control procedures.
Date When Full Com liance Will Be Achieved:
1.
Procedures OST-1825 and 1826 are performed on a staggered 18 month interval and the next test scheduled is during the Fall 1989 refueling outage.
It is projected that the procedure changes as stated above will be completed by September 1,
1989.
2.
Full compliance will be completed upon revision
, to appropriate maintenance and radiation control procedures as stated above.
Completion is currently projected by December 1,
1988.
MEM/HO-8802200/4/OS1
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