ML20012B606

LER-90-001-00:on 900209,primary Containment Isolation Sys Group III Isolation & Subsequent Standby Gas Treatment Sys Initiation Occurred.Caused by Personnel Error.Isolation Reset.Personnel Counseled on Proper procedures.W/900308 Ltr

ML20012B606
Person / Time
Site:	Vermont Yankee
Issue date:	03/08/1990
From:	Pelletier J VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-001, LER-90-1, VYV-90-067, VYV-90-67, NUDOCS 9003150401
Download: ML20012B606 (4)

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I VERMONT YANKEE NUCLEAR POWEn CORPOR ATION P. O. DOX 157 GOVERNOR IIUNT ROAD VERNON, VERMONT 05354

• y March 8, 1990 VYV# 90-067 U.S. Nucleat Regulatory Commission Document Control Desk F Washington, D.C. 20555

[.

REFERENCE:

Operating License DPR-20 Docket No. 50-271 Reportable Occurrence No. LER 90-01 l

Dear Sirs:

w As defined by 10CFR50.*l3, we are reporting the attached Reportable Occurrence as LER 90-01.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION

<b James P. Pelletier Plant Manager cc: Regional Administrator USNRC Region I 475 Allendale Road King of Prussia, PA 19406 i

9003150401 900308 PDR- ADOCK 05000271 9 s l\ i S- h .

PDC W c1

i NRC Fork 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0104

'(6-89) EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY

[ WITH THIS INFORMATION COLLECTION REQUEST:

50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20603.

FACILITY NAME (5) DOCKET NO. e) PAGE (*)

VERMONT YANKEE NUCLEAR POWER STATION O l 5 l 010 l(0 l 2 l 70l1l0Fl0l3 l1 l TITLE (*) INADVERTENT PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION AND STANDBY GAS TREATMENT START DUE TO PERSONNEL ERROR l- EVENT DATE (5) ,,

LER NUMBER (*) REPORT DATE (?) OTHER FACILITIES INVOLVED (*)

, MONTH DAY YEAR YEAR SEQ. # REV# MONTH DAY YEAR FACILITY NAMES DOCKET NO.(S)

! O 5 0 0 0 0l2 0l9 9l0 9l0 -

0l0l1 -

0l0 0l3 0l8 9l0 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO RE0'MTS OF 10CFR 6: / ONE OR MORE ($')

MODE (') N 20.402(b) __ 20.405(c) _X 50.73(a)(2)(iv) __ 73.71(b)

POWER 20.405(a)(1)(I) __ 50.36(c)(1) __ 50.73(a)(2)(v) . _ _ 73.71(c)

LEVEL (to) Il d O__ 20.405(a)(1)(II)

_ __ 50.36(c)(2) __ 50.73(a)(2)(vii) __

OTHER:

............... .__ 20.405(a)(1)(III) __ 50.73(a)(2)(I) __ 50.73(a)(2)(viii)(A)

............... __ 20.405(a)(1)(iv) __ 50.73(a)(2)(II) __ 50.73(a)(2)(viii)(B)

............... 20.405(a)(1)(v) 50.73(a)(2)(III) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (18)

NAME TELEPHONE NO.

AREA CODE JAMES P. PELLETIER, PLANT MANAGER Bl d 2 21 d 7l -l 7l 7l Il 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (sa}

CAUSE SYST COMPNT MFR REPORTABLE ..... CAUSE SYST COMPNT MFR REPORTABLE ......

TO NPRDS ..... TO NPRDS ......

l ..... ......

NA --------- ,---------------------- ..... NA -------------------------------- ......

l l l ......

l l l .....

NA -------------------------------- ..... NA -------------------------------- ......

SUPPLEMENTAL REPORT EXPECTED (94) EXPECTED M0 DA YR SUBMISSION

~~l YES (If ves, complete EXPECTED SUBMISSION DATE) X l NO DATE () l l l ABSTRACT (Limit to 1400 spaces, i.e., approx. fifteen single-space typewritten lines) ($*)

ABSTRACT At approximately 1445 on 02/09/90, with the Reactor at approximately 100% power, a Primary Containment Isolation System (PCIS, EIIS=JE) Group III Isolation and subsequent Standby Gas Treatment System-(SBGT, EIIS=BH) initiation occurred. The PCIS Isolation, which

-ieslates the Primary and Secondary Containment Ventilation, was initiated when Radiation ,

Pr?tection Technicians were performing a calibration on the Reactor Building Ventilation Monitor (EIIS= MON).

The isolation was promptly reset and systems restored to normal operation after Plant personnel verified acceptable radiological conditions. Tech. Spec, operability requirements were satisfied at all times.

The cause of this event was attributed to personnel error. The Technicians performing the calibration did so without using the appropriate procedure and took the monitor out of bypass, before the test signal decreased below the monitor trip setpoint.

NRC Form 366 (6-89)

r NRC Aorm'366A U.S. NUCLEAR REGULATORY COMMISSION APPPOVED OMS NO.3150-0104

[ (6-89) EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:

50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TO THE RECORDS AND REPORTS TEXT CONTINUATION MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON, DC 20603.

UTILITY NAME (5) DOCKET NO. (8) LER NUMBER (s) PAGE (8)

YEAR SEO. # REV#

VERMONT YANKEE NUCLEAR POWER STATION d SI d d Ol 2l 7] 1 910 -

0l0l1 -

0l0 d2 0F d3 TEXT (If more space is required, use additional NRC Form 366A) ($')

L DESCRIPTION OF EVENT At approximately 1445 on 02/09/90, with the Reactor at approximately 100% power, a Primary Containment Isolation System (PCIS) Group III and subsequent Standby Gas Treatment Sy3 tem initiation occurred.

At the time of the event, Technicians, without using the appropriate procedure, were eclibrating the Reactor Building Ventilation Radiation Monitor. During this test the trip function of the monitor is bypassed to prevent inadvertent isolations. A high level test cignal had been introduced as part of the calibration; when the signal was removed, the Technician removed the bypass condition before the test signal had returned to normal, and the isolation occurred.

The isolation was promptly reset and systems restored to normal operation after Plant personnel verified acceptable radiological conditions.

-CAUSE OF EVENT The immediate cause of the event was the presence of a high level test signal intro-duced during the calibration of the monitor.

The root cause of this event is personnel error. The Technicians performing the calibration were not using a procedure during the calibration. When they switched the moni-t:r out of bypass, the test signal had not decreased below the trip setting and a PCIS iso-lation and SBGT start occurred.

ANALYSIS OF EVENT The PCIS and SBGTS operated as designed and successfully isolated the Primary and Secondary Containment Ventilation. A PCIS Group III isolation and SBGTS initiation are the Cxpected results of a trip of one side of the Reactor Building Ventilation Monitor System.

This event did'not adversely affect the safety of Plant equipment or the public.

Tech. Spec. operability requirements were satisfied at all times.

CORRECTIVE ACTIONS

1. After plant personnel verified acceptable radiological conditions, the isolation was promptly reset and the systems were returned to normal.

2.. -The Technicians were reminced that procedures must be used when performing any calibrations on plant equipment.

NRC Form 366A (6-89)'

k t -

NBC.5com-366A.U.S.NUCLEARREGULATORYCOMMISSIO"l APPROVED OMS NO.3150-0104  ;

~

, -(6-89) EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:

50.0 HRS. FORWARD COMMENTS REGARDING  !

f LICENSEE EVENT REPORT (LER) BUROEN ESTIMATE TO THE RECORDS AND REPORTS i TEXT CONTINUATION MANAGEMENT BRANCH (P-530), U.S. NUCLEAR  ;

REGULATORY COMMISSION, WASHINGTON, DC

, 20555, AND TO THE PAPERWORK REDUCTION  ;

PROJECT (3160-0104), OFFICE OF MANAGEMENT  !

AND BUDGET, WASHINGTON, DC 20603.  !

. UTILITY NAME ($) DOCKET NO. (*) LER NUMBER (*) PAGE (a}

YEAR SEQ. # REV#

! VERMONT YANKEE NUCLEAR POWER STATION d d d d d 21711 9l0 -

0l0lI -

0l0 d3 0F d3 TEXT (If more space is required, use additional NRC Form 366A) (5')

3. The Plant Health Physicist reviewed the procedure with the Technicians that were doing the calibration.

l

4. Following a review, the prceedure will be revised to a step-by-step method with sign-offs acknowledging the completion of each step.

5. Other procedures that can potentially result in a trip and/or isolation function ,

will be reviewed and revised to a step-by-step method as appropriate.

ADDITIONAL INFORMATION Similar incidents were reported to the Commission as LER 84-23, LER 85-05, and LER 89-06.

r

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i I

s NRC Form 366A (6-89)

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