ML18139B154
| ML18139B154 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 03/09/1981 |
| From: | Joshua Wilson Virginia Power (Virginia Electric & Power Co) |
| To: | O'Reilly J NRC Office of Inspection & Enforcement (IE Region II) |
| Shared Package | |
| ML18139B155 | List:
|
| References | |
| 81-014, 81-14, NUDOCS 8103130470 | |
| Download: ML18139B154 (3) | |
Text
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Vepco-VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box-315 Surry,. Virginia 23883
- MAR 9* 1981 Serial No: 81-014 Docket Nos: 50-280 50-281 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Cormnission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 License Nos: DPR-32 37
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COMA11ssaoH TOIY
Dear Mr. O'Reilly:
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Pursuant to Surry Power Station Technical~: the Virginia Electric and Power Company hereby submits the following Licensee Event Reports for Surry Unit l & 2.
Report Number 81-014/03L-0 8l-019/03L-0 80;...063/01.X-l Applicable Technical Specification T. S. 6.6.2.b (4)
T. S. 6.6:2.B (2)
T. S. 6.6.2.a (9)
These-reports have been reviewed by the Station-Nuclear Safety and Operating Committee, and.will be placed on the* agenda for the next qu~-i:terly meeting of *the System Nuclear Safety&. Operat~ng Committee.
Very trulyrrours,
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- L. -W:ilson ENCLOSURES cc:
Mr. Victor Stello, Director (3)
Office of Inspection and Enforcement Mr. Norman Haller, Director (3)
Office of Management and Program Analysis s10111.0L\\1D
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S1 COCXiT NUMBER S8 69 EVENT CATS 7"'
7S REPORT CA, E 80
- VENT DESCRIPTION-ANO PROSASI.E CONSEQUENCES@
I On February 12,1981, the alarm setpoint for RM-CC-106 was found to be in error (greater than twice background).
This condition had existed since February 6,1981.
((J7J This is contrary to T.S. 3. 7, Table 3. 7-5 and is reportable per T.S. 6.6.2.b(4).
Since RM-CC-106 remained functional and the activity in the component cooling system L...;:.d,;:i;:.d.... n;;;o;.t.:...:e:::x::;c;,;e;,;e:;:;d:....:tw~i;.;c;;e;...:b::a;;c;.:k::1g.:r;,;;o;;.;;u:.:;n::d::.izi.....:;t~h:.:.e;..:.:hi.::e;;;:a.;:;l.:.t.:;.:h....:.:;an,:;,:,:;:;d...:.:.s*::.a.:..f.:.:.e.:::;.t;v...,.A?i.:.f~t.:..h~e;;;;.*..:P11:.:u~b,:,,;ll;;,,;11o,l*ca...1Yl~e...
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[II[] I The cause was personnel error-in *that the' setpoint calculatfon's were not yerifjed as cr:IJJ I required.
The alarm setpoints were reset to comply with Teen. Specs.
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ATTACHMENT 1
- --------* ---*--** *-1 SURRY POWER STATION, UNIT 2 DOCKET NO:.
50-281 REPORT NO:
81-014/0JL-O EVENT-DATE:
2-12-81 TITLE OF EVENT:
IMPROPER.SETPOINT* FOR RM-CC-106...
- 1.
DESCRIPTION OF EVENT:
On February 6,1981, as a result of data obtained frmn.:_f.'.f-.~-14~..il.Jt..Eml.iaJ:_iQJl. __ _
Monitor Surv~illance), the alarm setpoints for RM-CC~l06 were reset.
On February 12,1981, as required by Unit 1 rag:(~tJ..on__mQ.tiit..Ql:.S..._+efuel.inz_..:... __ ~-.. --~-.
calibration procedure, the setpoints for RM-C~~106 were recalculated. It was discovered that the February 6th' s
- calculations. wel!e....in errar_and._..t:b:e....alaJ:m:__ ______ _
setpoint had. been set at greater than twice ba.ckground.
This. is contrary to Tech. Spec.JP~. and ~epo_rtable per Tech. Spec~.6. 6-2..h.(4.>--.----------*-~-.,--.-----*-----..
- 2.. PROBABLE CONSEQUENCES and STATUS of REDUNDAN~.EQUIPMENT~-.. --- *-----*---. _.. _. __.. ____,. --- ----*
A review of component cooling activity levels., for the perj.od of concern, indicated that the activity in. this system lia<L'not exceeded-tw.i.ce backgi-:ound.
Since RM-CC-106 remained functional,. although the alarm s~_tpoint. was slightly higher (factor of 1.5) the. health and safety of the public were not affected.
- 3.
CAUSE:
The* cause of the event was personnel error.
Specifically, the setpoint..
calculations on.February 6,1981 were not verified as required by Health Physic's procedure.
- 4.
IMMEDIATE CORRECTIVE ACTION:
Radiation monitor, RM-CC-106, alarm setpoin.ts--were--Fe-Se-t-t-e-eempl,y-w~~h...,..---,-
Specs.
- 5.
SUBSEQUENT' CORRECTIVE ACTION:
None required *.
- 6.
ACTIONS TAKEN TO PREVENT RECURRENCE:
The personnel involved have been re-instrumctto insure compliance with established procedures.
- 7.
GENERIC Il1PLICATIONS :
None.
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