ML20090B574

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Rev 3 to Procedure 1-PT-46.2A, Condenser Air Ejector Radiation Monitor Alarm Setpoint Calculation
ML20090B574
Person / Time
Site: Ginna Constellation icon.png
Issue date: 10/02/1987
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20090B375 List:
References
FOIA-91-106 1-PT-46.2A, NUDOCS 9203030467
Download: ML20090B574 (8)
v • d • e


Text

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l RIQUEST TO CHANGE PROCEDURE arm-5.4 NORTH ANNA POVER STATION Attachment 3 71RGINIA P0kTR Page 1 of 1

, 07-09-87 I. ATPERVISOR RESPONSIBLE NR POLLOVING PROCDURE: 1 O ABNORMAL O CURVE B00E O OPERATING O kTLDING O ADMINISTRATIVE O EMERGENCY $ PERIODIC TEST O O ANNUNCIAICR O IN-SERVICE INSPECTION O HEALTE PHYSICS g O CALIBRATION O MAINTENANCE O SPECIAL TEST O O CnDfISTRY O NON-DESTRUCTIVE TEST O START-UP TEST O PROCEDURE NO: / - g ,. 2 UNIT No: 3 RTVISION DATE: ypp pg, -

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CHANGES REQUESTG: (GITI STEP NUMBER, EIACI SUGCESTED WORDING AND LIST RIPERENCES. STAPLE '

COPY OP PROCIDURE WITH SUGGESTED CHANGES MAREED TO THIS PORM.)

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P 2 cc r o u R tE .

RETERENCES:

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RAASON POR CHANGES: 7 A

7 GE REQUESTED ST:

8 DATE: 9

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ACTION TAKIN:

  • 10 XES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN TEP. UFSARr' C YES 3 NO DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS / O TES 3 NO DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEVED SATITY QUESTION /- O TIS 3.NO IP ALL "NO", NO "$ATETT ANALYSIS" IS REQUIRED. IP ANY "TES", A " SAFETY ANALYSIS" IS REQUIRID.

(10CTR50.59) APPROVED COPY TO BE PROVIDED TO LICENSING COORD. POR INCLUSTON IN ANhTAL REPORT.

RECO. WINDED ACTION: ~

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M PROVED O DISAPPROVED DOES THIS PROCEDURE CREATE A QA DOCUMENT / TES S NO-C BT (COGNIZANT SUPERVISOB) 12 DATE: 13 REVIEkT.D ST QUALITT ASSURANCE:

CHANGES MADE TES O NO O - 14 BY:

7g M cehw F*@ 15 DATE ,

10 REVIEWED Y TATION NUCLEAR SAitu AND OPERATING COMMITTEE: 17 APPROVED O DISAPPROVED O APPROVED AS MODIPIED BY CC.WITTEE 1 4RMAN SIGNATURE: 18 DATE: /p 19 NEW PROCEDURE REVISION DATE: '  ;

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ACTION CCKPLETED BY: 21 DATE: ' 22 9203030467 910819 .

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PDR FOIA ._ o 7 ;m "/ '

WILLIAM 91-IO6 PDR '/'Uj v 'i"/

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'1 PERIODIC TEST CRITIOUE

, NORTH ANNA POWER STATION VIRGINIA POVDL Periodic Test No 1 Io be Performed By: 2 Unit No J 1-PT-46.2A SRIFT TECHNICAL ADVISOR , _1 , ,

1 Test Titles 4 CONDENSER AIR EJECTOR RADIATION HONITOR ALARM SETPOINT CALCUIATION 3 i

Tei.t frequency: 5

$PECIAL Unit Conditions Requiring Tests . 6 MODE 1 s

Test Performed By: 7 Date Started: 8A Data Completed: 88 Test Results (To be completed by performer of test and Cognizant 9 Supervisor (s)):

1. / _ / Satisfactory / / Unsatisfactc,7 / / Partial Procedure ,
2. The following problem (s) was encountered (use back of sheet for additional space):
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3. Corrective actii..t taken or initiated:
4. Work Order No.: Dated:

Porvard to Cognizant Supervisor i Test Reviewed and Approved By Cognizant Supervisor (s) or Designee: 10 Dates Reactor Engineer Dates Supervisor, Sury. 6 Test Consents:

Forward To Performance Engineer Comment (s) of Performance Engineer: 11 Stamps 12 l

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. 1-PT-46.2A Page 1 of 4 00-00-00 l

VIRGINIA POWER PERIODICTESTPROCED$.EPORNORTHANNAPOVERSTATIONUNITNO.: 1 TITLE: CONDENSER AIR EJECTOR RADIATION MONITOR ALARM SETPOINT CALCULATION

REFERENCES:

l

1. 1-PT-46. 2
2. Calculational Basis for PT-46.2A, approved 10/1/87 (See Rev. 0)
3. Letter to the NRC, 9/15/87 (serial no. 87-474A)

REVISION RECORD: APPROVED CRAIRMAN STATION NUCLEAR SAFETY

,RIV. NO. PAGZ(S) DATE AND OPERATING COMMITTEE l

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i i RECOMMENDED APPROVAL:~

l APPROVED BY:

1 CHAIRMAN STATION NUCLEAR SAFETY AND OPERATING COMMITTEI DATE:

SUPERINTENDFNT TECHNICAL SERVICES 1

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1-PT-46.2A Page 2 of 4 00-00-00 Initials 1.0 Purpose To determine the Condenser Air Ejector Radiation Monitor (1-RM-SV-121)

"HIGH" alarm setpoint, based on primary-to-secondary leakage, omamme 2.0 Initial conditions NOTE: If this is an initial startup, then previous pts may not be available.

2.1 The trend of the condenser air ejector radiation nordtor count rate from 1-PT-46.2 is available.

NOTE: If this is an initial startup, or a restart following a steam generator tube plugging outage, the initial leak rate is assumed to be 0 spd. ,

2.2 The S/G 1eak rate data from 1-PT-46.2 is available.

3.0 Precautions and Limitations 3.1 This trocedure must be performed prior .to entering Modo 1.

3.2 For an initial sta'rtup, or a plant startup following a S/G tube plugging outage, the previous S/C leak rate is assumed to be 0 spd.

3.3 For a plant startup, estimate the RCS gas activity, for 30% power, or any power level that the plant is arpect4d to operate at for an extended period, whichever is less.

3.4 To recalculate the air ejector radiation monitor (1-RM-SV-121,)

"HIGH" alarm setpoint, use the most recent measured RCS gas activity isotopics, if possible, or applicable. Otherwise estimate the RCS gas activity isotopics based on previous measured data and power history.

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1-PT-46.2A Page 3 of 4

. 00-00-00 .

3.5 To recalculate the air ejector radiation monitor (1-RM-SV-121)

"HIGH" alarm setpoint, use the most recent leak rate calculations based on 1-RM-SV-121. Several leak rate results may be averaged to better ascertain the primary-to-secondary leak rate.

4.0 Instructions 4.1 Record the most recent psimary-to-secondary leak rate data (based on 1-RM-SV-121) from 1-PT-46.2 on Attachment 6.1. If this is a startup af ter a S/G tube inapection outage, record 0 spd total leakage on Attachment 6.1.

4.2 Estimate the RCS gas activity based upon previous measured data and the power history. Use 1-PT-46.2 (Atta'chmen't 6.10) for guidance. Record the estimated RCS gas activity on Attachment 6.1.

4.3 Recy$ rd the previous "HIGH" alarm setpoint for 1-RM-SV-121 on y

A;t'achment 6.1.

4.4 Record the current total Condenser Air Ejector Flow Rate on Attachment 6.1.

4.5 Record the current count rate for 1-RM-SV-121 on Attachment 6.1.

4.6 Calculate the new *HIGH" alarm sstpoint for 1-RM-SV-121 using the equations at the Sottom of Attachment 6.1.

4.7 Immediately notify the Shif t Supervisor of the new alare setpoint.

4.8 Complete Attachment 6.2 and forward a copy to the Health Physics Shitt Supervisor.

l 4.9 Verify that the new setpoint has been implemented.

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1-PT-46.2A Page 4 of 4 00-00-00 4.10 Post an Operator Aid (ADM-19.27) next to 1-PJi-SV-121 stating the new setpoint in both cpe and gpd.

$.0 Acceptance Criteria ,

5.1 The new setpoint has been implemented and an Operator Aid has been posted.

6.0 A*.tachments 6.1 1-RM-SV-121 "HIGH" Alarm Setpoint Calculation 6.2 Memo to change the "High" alarm setpoint for 1-RM-SV-121.

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I 1-PT-46.2A Attachment 6.1 Page 1 of 1 00-00-00 1-EM-SV-121 *EIGH" Alarm Setpoint Calculation Recent Primary-toSecondary Leak Rate Data Based on 1-RM-SV-121 (from 1-PT-46.2):

Date(s): , Leak Rate (s):

Averages gpd RCS Gas Activity (uci/ gram)

Hessured: Date: Times Powers  %

Xe-135: Kr-87: Ar-41:

Estimated Fort Date Times Powers  %

Xe-13$: KR-87: Ar-41:

Total Condenser Air Ejector Flow Rate SCFH Current Count Rate for 1-RM-SV-121: cpm Previous "RIGH" Alarm Setpoint s cpa This corresponds tot gpd ,

e New "HIGH" Alarm Setpoints eps This corresponds tot gpd e

If 1-RM-CV-121 is less than or equal to 80 cpm Setpoint (cpm) = 80 + (20 rpo) (Ke-135 + Kr-87 + AR-41)

(2.92 x 10~4)(Air Ejector Flow Rate) -

e If 1-RM-SV-21 is greater than or equal to 80 cpa Setpoint (eps) = 80 + (leak rate + 10 rpd)(Xe-135 + Kr-87 + Ar-41 (2.92 x 10"#)(Air Ejector Flow Rate)

PREPARED BY: DATE:

.__._______-_-m__m, _ - - - - - - -_--_-_- - - - - - - - - - - - - - - - - - - - " - - - - - - - - - - - - - - " ' ' ~ - - - - - " - - - ' - - - - - - - - - - - - - ' - - - - - - - - - - - - - - - - - - ' ~ -

1-PI-46.2A

. Attachnent 6.2

. Page 1 of 1 00-00-00 MDO TO CHANGE THE *HICH" ALLEM SETPOINT TO 1-RM-SV-121 TO: Health Physics Shif t Supervisor North Anna Power Station PROM Shif t Technical Advisor Date Please immediately update the "HIGH" alarm setpoint to the Unit 1 Condenser Air Ejector Radiation Monitor (1-PJi-SV-121) as soon as possible, as follows:

Setpoint = cpm -

This corresponds tot gpd 1

Date Shilt Technical Advisor

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