ML20138F718

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Rev 2 to Procedure STS IC-275B, Analog Channel Operational Test Containment Purge Sys Radiation Monitor GTRE33
ML20138F718
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 05/07/1985
From:
KANSAS GAS & ELECTRIC CO.
To:
Shared Package
ML20138F694 List:
References
FOIA-85-706 STS-IC-275B, NUDOCS 8512160158
Download: ML20138F718 (52)


Text

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KANSAS GAS & ELECTRIC COMPANY WOLF CREEK GENERATING STATION ANALOG CHANNEL OPERATIONAL TEST CONTAINMENT PURGE SYSTEM RADIATION MONITOR GTRE33 STS IC-275B Revision 2 Classification:

Major ma;//fd c-s-w PREPAREDBY[

^

DATE

$~ d '95 i

te ww-INDEPENDENT REVIEW U

DATE ~

nk Ng G-6 COGNIZANT GROUP SUPERVISOR DATE I

S - fo - V T RES POtTS LE~ SUPER 199TENDENT APPROVAL DATE i

PSRC APPROVAL DATE l

ove PLANT MANAGER APPROVAL' INF0 ONLY S (g51216015e 851203 HEP 5-7 6 M

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1.0 PURPOSE 1.1 The purpose of this procedure is to provide a method for proving the operability of the instrumentation loop for the Containment Purge System Radioactivity Monitor GTRE33.

Completion of this procedure and STS IC-275A will satisfy the Analog Channel Operational Test requirements of Wolf Creek Generating Station Technical Specification 4.3.3.11, Table 4.3-9, Instrument 3.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 In the event of a malfunction, the individual performing the test shall suspend testing and report the malfunction to the Shift Supervisor or his alternate.

The equipment in question shall be left in the tripped condition and declared inoperable.

The Shift Supervisor or his alternate shall determine if the Limiting Condition for Operation is met in accordance with Technical Specification 3.3.3.1.

During the test suspension period, the malfunction should be corrected in an expeditious manner consistent with plant safety and reliability requirements.

3.0 INITIAL CONDITIONS 3.1 This procedure may be performed during any mode of operation.

However, this procedure is not normally performed during power level transients in Mode 2, startup.

Performance of this procedure during Mode 2 may be accomplished under long term, steady state conditions.

~

3.2 Because of the progressive nature of this procedure, specific conditions for test performanc'e are in Section 5.1, Preliminary, and in the leading steps of each succedent section.

3.3 This test shall be performed by a Level II or Level III Instrumentation and Control Technician designated Test Performer #1, who will be responsible to ensure the test is performed in accordance with procedure 3 guidelines.

6 STS IC-275B Rev. 2 INF0 ONLY '"a,*

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4.0 TEST EQUIPMENT ANb REFERENCES 4.1 Test Egoipment W.C.5 Cal. Due Date Stop Watch d

Pulse denerator, H.P. Model 3310B, or Equiv.*

Oscilliscope s

Timer Counter, Fluke 7260A, w

or Equiv.*

RM-23P, General Atomics

  • If "Or Equiv.'" test equipment is used, provide a description and justificatipn for it in Step 6.1.2.

~

4.2 References Manual for Airborne Radiological Mon. Sy's>, J361-A072, Rev. 11

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t Model RM-ll Console-Operator's Guide, J361-Olli, Rev. 2 Manual for' Process / Airborne Radiological Mon. 3ys.,

J361-0109, Rev. 7 Model RM-23 Readout-User's Guide, $361-0078, Rev. 3 Dwg. E13SP02, Rev. 1

~

5.0 PROCEDURE 5.1 Preliminary Set-up and Data 5.1.1 Inform the Reactor Operator of the intent to start the test procedure.

RO Date 5.1.2 Inform the Reactor Operator that CPIS and CRVIS will be initiated as part of this test g

and any system alignment necessary to protect

, operating plant equipment should be done at this time.

R.O.

/

STS.IC-275B l

Rev. 2 l

l Page 2 of 15 INF0 ONLY :;

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s 5.1.3 Inform the Reactor Operator that Annunciator Windows A61, B61 and C61 in RLO20 will be

((]

illuminated periodically during this test.

NOTE:

At the RM-ll, verify that the printer is online and that the G.E.

Terminal is on.

5.1.4 Verify that Annunciators A61, 861 and C61 are not illuminated.

ANNUNCIATOR STATUS A61 OFF

((

B61 OFF

((

C61 OFF 5.1.5 Obtain an Engineered Safety Features Actuation System (ESFAS) Bypass Key for GT RT-33 from the Shift Supervisor, p_

5.1.6 At the ESFAS Cabinet'SA036E, ve-ify that no trip exists for Bistable GTRB-33.

{[]

5.1.7 In SA036E insert the Bypass Key in Bypass Switch GTRB-33 and turn to the BYPASS position.

Verify that the CHANNEL BYPASSED lamp illuminates.

{[]

5.1.8 Request the Reactor Operator to OPEN or CHECK OPEN the following Mini-purg.e System Containment Isolation Dampers -

using the Control Switches in RL320.

Damper Switch Status GT HZ-4 GT HIS-4 OPEN GT HZ-5 GT HIS-5 OPEN

~~

GT HZ-6 GT HIS-6 OPEN

~~

GT HZ-7 GT HIS-7 OPEN

~~

GT HZ-8 GT HIS-8 OPEN

~~

GT HZ-9 GT HIS-9 OPEN

~~

GT HZ-ll GT HIS-ll OPEN

((

3 GT HZ-12 GT HIS-12 OPEN 5.1.9 Request the. Reactor Operator to CLOSE or CHECK CLOSED the Air Return to Control Room Filter Adsorber Unit Dampers GK HZ-160 and GKHZl61 using Control Switches GK HIS-160 and GK HIS-161 in RP068.

GK HZ-160 CLOSED GK HZ-161 CLOS

~~

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Page 3 of 15

INIT/DATE 5.1.10 Request the Reactor Operator to OPEN or CHECK OPEN Isolation Dampers GK HZ-13 A-GK HZ-13H by observing the indication on Control Switch GK HIS-13 in RP068.

[]

GK HZ-13A-GK HZ-13H OPEN 5.1.11 Request the Reactor Operator to OPEN or CHECK OPEN the following dampers by observing the indications on the Control Switches in RP068:

Damper Switch Status

~~

GK HZ-172A/B GK HIS-172 OPEN GK HZ-174A/B GK HIS-174 OPEN

~~

~~

GK HZ-59A GK HIS-59 OPEN

~~

GK HZ-59B GK HIS-59 OPEN

~~

GK HZ-57A GK HIS-57 OPEN

~~

GK HZ-578 GK HIS-57 OPEN

~~

GK HZ-55A GK HIS-55 OPEN GK HZ-SSB GK HIS-55 OPEN

~~

GK HZ-98A GK HIS-98 OPEN

~~

~~

GK HZ-988 GK HIS-98 OPEN

~~

GK HZ-184A GK HIS-184 OPEN GK HZ-184B GK HIS-184 OPEN

~~

~~

GK HZ-184C GK HIS-184 OPEN

~~

GK HZ-184D GK HIS-184 OPEN GK HZ-184E GK HIS-184 OPEN

~~

GK HZ-123A GK HIS-123 OPEN

((

GK HZ-1238 GK HIS-123 OPEN GK HZ-123C GK HIS-123 OPEN GK HZ-122A GK HIS-122 OPEN GK HZ-122B GK HIS-122 OPEN

~~

GK HZ-173A/B GK HIS 1.73 OPEN

))

GK HZ-175A/B GK HIS-175 OPEN 5.1.12 Using a Supervisor Key, place GTRIC33 in SP067 into the Supervisory Mode.

{[l 5.1.13 At GTRIC33 in SP067, record the values found in Channel Items 009, 010, Oll, gsand 012 into Test Data Table 3 for the

, Gas Channel.

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2nd STS IC-275B Rev. 2 Page 4 cf 15 INF0 ONLY

0 5.1.14 At GTRIC33, enter the Channel Item values listed in Test Data Table 1 into the Gas Channel.

TEST DATA TABLE 1 ITEM ITEM ITEM ITEM 009 010 011 012 GAS 1.00 E-3 1.00 E-4 2.85 E-08 2.85 E-08 5.1.15 At the RM-ll, GRID 1, select Channel GTG333 by depressing 333 and then SEL.

Verify that location GTG333 has a rectangle around the green channel square.

[_]

5.1.16 At SP067, loosen the retaining screws and

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remove GTRIC33.

(_]

5.1.17 Verify that the PROCESS RAD MON FAIL Annunciator C61 has illuminated.

{]

5.1.18 Acknowledge the flashing blue indication for Channels GTP331, GTI332, and GPG333 on GRID 1 of the RM-ll by depressing the SEL button.

5.1.19 Reolace GTRIC33 into SP067 and tighten the retaining screws.

{]

5.1.20 Verify that the PROCESS RAD MON FAIL Annunciator C61 has extinguished.

((]

3.1.21 Verify that Channels GTP331, GTI332 and GTG333 on GRID 1 of the RM-ll are in the normal (green) status.

((]

5.1.22 Place the ON/OFF Switch (SI) on GTRE33 into the OFF position.

{[

5.1.23 In the Control Room, verify that the PROCESS RAD MON FAIL Annunciator C61 has illuminated.

Insure that the Reactor Operator acknowledges the flashing alarm on C61.

{]

5.1.24 Place the ON/OFF Switch (S1) on GTRE33

  • into the ON position.

{[]

5.1.25 In the Control Room verify that the PROCESS RAD MON FAIL Annunciator C61 has extinguished.

{]

STS IC-275B Rev. 2 Page 5 of 15 INF0 ONLY+

5.1.26 Acknowledge the ALARM status at the RM-ll and verify that Channels GTP331, GTI332 and GT3333 are green.

((]

NOTE:

If Channels GTP331, GTI332 and GTG333 remain magenta, communication has not been so-established.

When communication has been established, all channels will be green.

If after 25 minutes (worst case) communication has not been established, treat the situation as a malfunction and refer to Step 2.1.

5.1.27 At Radiation Monitor GTRE33 (location shown on Attachment 1), verify that the following switches are in the indicated positions.

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Switch Position ONLINE/ BYPASS (S7)

ON LINE POWER (S1)

ON TEST /RUN RUN HAND / AUTO (VLV)

AUTO HAND /OFF/ AUTO (PUMP)

AUTO DB LOAD (S9)

OFF CONTR.

(S10)

OFF DB ALTER (Sll)

OFF

((

NOTE:

In the following part of the procedure, the Test Performers are required to be at different locations with a form of commun-ications between them.

One Test Performer will be at the Radiation Monitor and one Test Performer will be in the Control Room.

5.1.28 Install an RM-23P in the RM-23P jack at GTRE33.

[

5.1.29 Verify that the RM-23P INSTALLED message is logged at the RM-ll and on the printer.

{[],

5.1.30 At the ESFAS Cabinet (SA036E), verify

\\ that Bistable GTRB33 is in the untripped condition.

(Bistable Trip Light out.)

{[

STS IC-275B Rev. 2 Page 6 of 15 INF0ONLY

INIT/DATE 5.1.31 At the ESFAS Cabinet, place the GTRB3 3 BYPASS Key into the OPERATE position and remove the Key.

/

1st

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2nd 5.1.32 Notify Reactor Operator that a CPIS and CRVIS will be initiated as part of Section 5.4 of this procedure.

R.O.

/

5.2 Gas Monitor Test

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5.2.1 At GTRE33 disconnect the signal cable from the RM-80 preamplifier input J-1.

5.2.2 Verify that the RM-80 LOSS OF COUNTS LED illuminates in 5 minutes +20 seconds of the signal cable removal.-

((]

Response Time 5.2.3 Verify that the RM-80 alarm horn sounds.

{[]

5.2.4 Silence the alarm horn by momentarily depressing the HORN ACK button on the RM-80.

{[

5.2.5 In the Control Room verify that the PROCESS RAD MON FAIL annunciator C61 has illuminated.{]

5.2.6 Verify that the printer indicates a NO PULSES TIMEOUT message.

{_~

5.2.7 Acknowledge the flashing blue indication for Channel GTG333 on GRID 1 at the RM-ll by depressing the SEL button.

{[

5.2.8 Connect a pulse generator and an oscilloscope to TB3-14 (+) and TB3-15 (-) on the RM-80 motherboard.

{[

5.2.9

, Inject a 4.0 VAC square wave (positive in reference to zero level) and verify that Channel GTG333 indicates green on GRID 1.

{[

STS IC-2758 Rev. 2 Page 7 of 15 INF0ONLY

5.2.10 Slowly increase the generator output while monitoring Channel Item 007 and the counter until an Alert Alarm occurs (3500 CPM +

CPM).

- 900

{]

5.2.11 Verify that the RM-80 alarm horn sounds.

((]

5.2.12 Silence the alarm horn by momentarily de-pressing the HORN ACK button on the RM-80.

{[]

5.2.13 At the RM-ll, interrogate GRID 1 and verify that Channel GTG33 3 is in the ALERT status.

((]

5.2.14 Acknowledge the flashing yellow square at location GPG333 on GRID 1 at the RM-ll by depressing the SEL button.

The channel should remain a solid yellow square indicating that GTG333 is in an Alert Alarm condition.

{]

5.2.15 In the Control Room, verify that the alarm is annunciated at Window B61, PROCESSRADHI.{[]

TEST DATA TABLE 2 GAS RADIATION MONITOR SETPOINTS ALERT ALARM SETPOINTS SETPOINT ALLON TOL.

AS FOUND AS LEFT ACTIVITY 1.00E-4 9.50E-5 to 1.05E-4 CPM 3500 2600 to 4400 RESET ALLOW TOL.

AS FOUND AS LEFT ACTIVITY 9.00E-5 8.95E-5 to 9.05E-5 CPM 3150 2250 to 4050 HIGH ALARM SETPOINTS SETPOINT ALLOW. TOL.

AS'FOUND AS LEFT ACTIVITY 1.00E-3 9.50E-4 to 1.05E-3 CPM 35,000 26000 to 44000 RESET ALLOW. TOL.

AS FOUND AS LEFT ACTIVITY 9.00E-4 8.95E-4 to 9.05E-4 CPM 31500 22500 to 40500 5.2.16 Record the valbe at which the Alert Alarm occurred in the ALERT ALARM AS FOUND column of TEST DATA TABLE 2.

(Record the activity level from the RM-ll Printer and the counts per min-jute from the counter.)

((}

NOTE:

If the SETPOINT and AS FOUND responses differ by more than +.05 LSD (3500 CPM +900 CPM), treat the situation as a malfunction and refer to Step.2.1.

If the AS FOUND data is within tolerance record in the AS LEFT space of TABLE 2.

STS IC-275B Rev. 2 INFO ONLY""""

5-o 5.2.17 Slowly decrease the oulse generator output frequency until the Alert Alarm just resets. ]

5.2.18 In the Control Room, verify that Annunciator Window B61, PROCESS RAD HI, has extinguished. ]

5.2.19 Record the values indicated on the RM-ll Printer and the counter in the ACTIVITY RESET and CPM RESET spaces of TEST DATA TABLE 2.

NOTE:

If the RESET value is less than 3150 CPM +900 CPM treat the

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situation as a malfunction and refer to Step 2.1.

If the AS FOUND data is within tolerance, record in the AS LEFT space of TABLE 2.

5.2.20 Verify that GRID 1 on the RM-ll indicateJ green on Channel GTG333.

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5.2.21 Slowly increase the pulse generator output frequency while monitoring Channel Item 007 and the counter until a High Alarm occurs.

(35000 CPM + 0000 CPM).

NOTE:

Insure that the RM-80 Alarm Horn is silenced prior to generating the High Alarm trip.

5.2.22 Verify that the RM-80 alarm horn sounds.

5.2.23 Silence the alarm horn by momentarily depressing the HORN ACK button on the RM-80. p 5.2.24 At the RM-ll, interrogate GRID 1 and verify that Channel GTG333 is in the ALARM status.

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5.2.25 Acknowledge the flashing red square at location GTG333 on GRID 1 at the RM-ll by

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depressing the SEL button.

The channel should remain a solid red square indicating that GTG333 is in a HIGH ALARM condition.

5.2.26 In the Control Room, verify that the alarm

  • is annunciated at window A61, PROCESS RAD HIHI.

~

STS IC-2758 Rev. 2 INF0 ONlT"

e 4

5.2.27 Record the value at which the High Alarm occurred in the HIGH ALARM AS FOUND Column of TEST DATA TABLE 2.

(Record the activity level from the RM-ll Printer and the counts per minute from the counter).

((]

NOTE:

If the Setpoint and AS FOUND responses differ by more than +.05 LSD (35000 CPM + 9000 CPM), treat the situation as a malfunction and refer to Step 2.1.

If the AS FOUND data is within tolerance record in the AS LEFT space of TABLE 2.

5.2.28 Request the Reactor Operator to verify that the following Mini-Purge System Containment Isolation Dampers have CLOSED by observing the indications on the Control Switches in RLG20.

Damoer Switch Status GT HZ-4 GT HIS-4 CLOSED GT HZ-5 GT HIS-5 CLOSED GT HZ-6 GT HIS-6 CLOSED GT HZ-7 GT HIS-7 CLOSED GT HZ-8 GT HIS-8 CLOSED GT HZ-9 GT HIS-9 CLOSED GT HZ-ll GT HIS-ll CLOSED GT HZ-12 GT HIS-12 CLOSED O

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STS IC-275B l

Rev. 2 l

INF0 ONIY"

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5.2.29 Verify that the following dampers have assumed the indicated status by observing the indications on the Control Switches in RPO68.

Damper Switch Status GK HZ-160 GK HIS-160 OPEN

[]

GK HZ-161 GK HIS-161 OPEN GK HZ-13A GK HIS-13 CLOSED

((

GK HZ-13H GK HIS-13 CLOSED

~~

GK HZ-172A/B GK HIS-172 CLOSED GK HZ-174A/B GK HIS-174 CLOSED GK HZ-59A GK HIS-59 CLOSED GK HZ-59B GK HIS-59 CLOSED GK HZ-57A GK HIS-57 CLOSED

[-

GK HZ-578 GK HIS-57 CLOSED

~~

GK HZ-SSA GK HIS-55 CLOSED GK HZ-SSB GK HIS-55 CLOSED GK HZ-98A GK HIS-98 CLOSED OK HZ-983 GK HIS-98 CLOSED

~]

GK HZ-194A GK HIS-184 CLOSED GK HZ-lS4B GK HIS-184 CLOSED GK HZ-184C GK HIS-184 CLOSED GK HZ-184D GK HIS-184 CLOSED GK HZ-184E GK HIS-184 CLOSED GK HZ-123A GK HIS-123 CLOSED GK HZ-123B GK HIS-123 CLOSED GK HZ-123C GK HIS-123 CLOSED GK HZ-122A GK HIS-122 CLOSED GK HZ-122B GK HIS-122 CLOSED

))

GK HZ-175A/B GK HIS-175 C.LOS ED

~~

GK HZ-173A/B GK HIS-173 CLOSED 5.2.30 Slowly decrease the pulse generator output frequency.until the High Alarm just resets.

{-_

5.2.31 In the Control Room, verify that Annunciator A61, PROCESS RAD HIHI, has extinguished.

{-

5.2.32 Record the values indicated on the RM-ll Printer and the counter in the ACTIVITY RESET spaces of TEST DATA TABLE 2.

{_-

\\ NOTE:

If the RESET value is less than 31500 CPM + 9000 CPM, treat the situation as a malfunction and

  • .a refer to Step 2.1.

If the AS FOUND data is within tolerance, l

record in the AS LEFT space of TABLE 2.

STS IC-2753 Rev. 2 I

O O LYPage 11 of 15 4

w 5.2.33 Verify that GRID 1 on the RM-ll indicates

[]

yellow on Channel GT G3 3 3.

5.2.34 Decrease the pulse generator output frequency to ZERO, disconnect the test cable, and re-connect the signal cable to preamplifier input J-1.

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5.2.35 At the RM-23P, set Channel Item 016 to 000

((]

and then back to 001.

5.2.36 Verify that the RM-80 LOSS OF COUNTS LED extinguishes.

h2]

5.2.37 Verify that the Control Room Annunciator Windows A61 and B61 are extinguished.

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5.2.38 At the RM-ll, verify that Channel GTG333 is in the NORMAL status.

{[

5.2.39 Remove the RM-23P from the RM-80 at

((

GTRE33.

5.2.40 Verify that the RM-23P EXIT message is logged at the RM-ll and on the printer.

((]

5.3 Completion Coordination INIT/DATE 5.3.1 At GTRIC33, enter the Channel Item values for the. Gas Channel of GTRE33 into the RM-80 Data Base as shown in Test Data Table 3.

{[]

TEST DATA TABLE 3 ITEM ITEM ITEM ITEM 009 010 011 012 GAS

/

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2nd 5.3.2 At GTRIC33, interrogate the Particulate, j Iodine and Gas activities and verify that they are below the alarm points.

Phrticulate

{}

Iodine

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Gas STS IC-275B Rev. 2 Page 12 of 15 INF0 ONLY

v INIT/DATE 5.3.3 At GTRIC33, place the Supervisor Key into the OPERATE position and remove the key.

/

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/

2nd 5.3.4 Request the Reactor Operator to reset the CPIS and CRVIS using approved plant operating procedures.

{ NOTE: This step may be performed concurruntly with the remaining portion of thir procedure. 5.3.5 Request the Reactor Operator to START-the Control Building Supply Air Fan SGK02 using Control Switch GK HIS-E in RP068. ([] SGK02 RUN 5.3.6 Inform the Reactor Operator that the Control Building liVAC System (GK) and the Containment Air Purification and Cleanup System (GT) may be aligned as required for the current plant conditions. p 5.3.7 Verify Control Room Annunciator Windows A61, B61 and C61 are cleared. {[ 5.3.8 Verify that all test equipment has been removed from GTRE33 and that the monitor is operating normally. {[ 5.3.9 At Radiation Monitor GTRE33, place the following switches to the indicated positions. DB LOAD (S9) ON CONTR. (S10) ON ~~ DB ALTER (Sll) ON )) 6.0 'RESTORAisON, G.1 Termination 6.1.1 Notify the Reactor Operator of the completion of testing. (( STS IC-275B Rev. 2 INF0 ONLY" ? .., a...

v 6.1.2 Test Performer's Comments: \\;W.R. Number 6.1.3 Test Complete Test Performer il Date STS IC-275B Rev. 2 Page 14 of 15 INFO ONLY

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o KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION WOLF CREEK EVENT REPORT 85-Io3 WCE No. Date: 8-7-85

Title:

Containment Vent to Atmosphere Event

Description:

(Use additional pages if required) STS-IC-275A ~and 8 open GT-H2-4, 5, 6, 7, 8, 9, 11 and 12 to verify that they close when GTRE32 or 33 detects HI Rad. while STS-IC-275A was being performed on 7-26-85. The R0 noticed that containment press'ure had decreased to atmospheric. It was found that opening the atcve listed valves effectively vents containment through the containment shutdown and mini-purge supply fans and containment mini-purge exhaust fans. Upstream and down-stream dampers do not have specific-leak-rate criteria.(Cont) Immediate Corrective Action Taken: (Use additional pages if required) J P 3 1 t :l:k -AN5k a , 63 -. 1 ADM 01-063 J' Pcge 1 of 2 Rev. 3 F t" 7'[8 .77 Page 4 of 5 y S . a i i.as _g _- u u m b

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.s_ o m. .... -~..

l O-s an analysis of containment atmosphere samples obtined shortly after this incident showed no detectable radioactive noble gases, radioiodines or radioactive particulates in the containment atmosphere. A review of the installed radiation monitor trends showed no increase levels during the incident. + t O 'l i ) 4 I 9 l N M eh g, -, -, -. ~.

\\ Cause of the Event: Personnel Material Installation Design Other: Procedure Development Error Recommended and/or Final Corrective Action to Prevent Recurrence: (Use additional pages if required) Tech Spec 4.6.3.2 - c required a functional test of valve closure on an 18 month cycle. STS-KJ-001A and B comply with this. Therefore, valve cycling in STS-IC-275A and B and STS-IC-475A and B is not required. Unnecessary steps in these procedures will be removed prior to next performance. Corrective Action: l_~l IOPD # l_-l Work Request # 9 9 r Prepared by: h h-8-738 Reviewed by: Date L/V (Plant Manager'or designee) .j PSRC Review Required: Yes No NSRC Review Required: Yes_ No _ '.T -l , 63-1 Pcge 2 of 2 ADM 01-063 Rev. 3 dl , e "M)w,,. 3 .f . Page 5 of 5. c-,

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-s .g' z E aNEE osee Event ' Report and Written Report Conpleted: No. Date f -A~ ns Taken: Assignee:~ Da _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _te Ti:ne V. PLANT MANAGER LER and Written Report Coupleted: Date Defect / Deficiency Closed Out: [ YES NO PSRC ' Review Conplete: Date s Plant Manager: Date i 1 1 4 \\ I I 1 1 ttachment 033 1

, 5- - 2 cf 2 AEM 01_033

( Rev. 13 Page 32 of 89 -, -. _.. _ _ ~, _,., _...,, _. -... _..

,. s 1 i' CHECKLIST FOR tCTIFICATION i l nt Notification i y of Notification Event Time and Zone I , Region IV Date / / Call Back No. M D Y Facility: Kansas Gas and Electric Conpany, Wolf Creek Generating Station In:lividual making notifications: Individual receiving notification: Event Classification t Alert Transportation Event Site Area Emergency General' Emergency 50.72 (Non-Lt.e:gency Urplanned Release Physical Security / Safeguards Notification of Unusual Event Po c r Prior to Event Power at Time of Report Resident Inspector NQtified i Rx Trip Initiating Signal Safety Injection or ECCS Initiating Signal ESF Actuation ICO Action Statement l Evrnt Description /Cause: + t i. i! l i t Radiorctive Relecses (Quantify): i I Othnr Major Problems: i I } Plcnned Actions / Press Releases: i Ootside Agency or Personnel Notified by Licensee:. ' State Local cr \\*

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CAIL BACK WITH ANY CHANGES OR ADDITIONAL INFORiATION ! Attrchment 933-2 ] Page 1'of 1 ACH 01-033 Rev. l4

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REPCRTABOLDTV EVALUAT0@98 I K. R. Ellison Recuest Date: August 5, 1985 Recuested By: Phone No: 2563 Air Flow Through Containment Purge From ContaL' ment to Environment Without a Release Permit - Defect / Deficiency Report. Z-105 Descr10tton of Event or Situation: On July 26/1985 at 1800 Cpr, it was noted that containment pressure had decreased since the previous reading. W e most probable cause was the performance of STS-IC-275B in which the containment purge ~ isolation valves are opened for testing of Gr-Rr-33. Subsequent investigations indicatx1 that air leakage had occurred through the flowpath created by these open valves and leaky exhaust dampers. (Cont'd on next page) Summary of Evaluat;0n: An analysis of containment atmosphere performed subsequent to the release confirmed that no Technical Specification or 10 CFR 20 release limits were exceeded. Technical Specification Surveillance Requirement 4.11.2.1.1 states that "We dose rate due to noble gases in gaseous effluents shall be determined to be within above limits in accordance with the methodology and parameters-in the ODCM." Wis criterion was met because radiation monitor Gr-Rr-22 was ins ~ervice with its setpoint set in accordance with the ODC4. GT-Rr-22 was capable of initiating a Containment Purge Isolation and a Control Rom Ventilation Isolation had radiation levels reached its setpoint. @is event is not reportable per the criteria of 10 CFR 50.72 or 50.73, but it is reportable per Technical Specification 6.9.1.7, " Semiannual Radioactive Effluent Release Report", in which a list and description of all unplanned releases shall be included. Reoortabilltv: Rep 0rtable? YES x N0 If YES, rep 0rtable to what requirements? rechnical Sreci fica tion 6. 9.1. 7, " Semiannual Radioactive Effluent Release Ronort" If YES, rep 0rtable when? March 1. 1986 b EVALUATION BY MdMdAd N4h Date elb/8T ( 0 I/

e Description of Event or Situation (continued) It was also subsequently determined that the redundant containment purge radiation [ monitor, GT-RT-22, was operable throughout this time pericd and could shut the containment purge isolation valves if ra:!iation levels reached the CPIS setpoint. STS-IC-275B is being revised to provide an alternate method of testing GT-RE-33 to eliminate the need for having these valves open. 9 0 we 4 0

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