ML20052A516

to Procedure 0120032, Excessive RCS Activity.

ML20052A516
Person / Time
Site:	Saint Lucie
Issue date:	03/15/1982
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20052A500	List: ML20052A499 ML20052A503 ML20052A512 ML20052A516
References
0120032, 120032, NUDOCS 8204280414
Download: ML20052A516 (7)

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TYPE OR PROCEDURE PROCEDURE NO.

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TITLE OF PROCEDURE /I // .[ 7 9 }~

REVISION No. 13 DATE SIGNED: h h h,[f /

PAGES AFFECTED / p* A-6 8-6

. REVISION NO. 14 DATE SIGNED: 3 PAGES AFFECTED N-b REVISION No. 15 gg g. ,

PAGES AFFECTED 1 through 3 A-8, B-8, C-1, 7, 9 REVISION NO. 16 DATE SIGNED: \

PAGES AFFECTED: ALL REVISION 17 ,;j .

PAGES AFFECTED ,H [ PS 12 uf 'u 77eh H.

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REVISION 18 DATE SIGNED: / - J 6- T#

PAGES AFFECTED M-5 D-8 B-1 b REVISION 19

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147.SX terrning gear motor running but nos 111RNINr: OtAR ttoroR engaged. CWn F M ov F.pl.DA fi/ TUR R IHF.

2. (a) Hot i f y electr'ical department (Fero eteed

2. Turning gear Irwllcat ione S1orrFD (h) Reset breaker, attempt to log eurntng relay) gegr D-41 (c) If turbine shaft la bot, sefer to turbine 74 Relay technical marneal for actions I. (a) Indlcatea motor overinad t. (a) Pump tripa Thermal SFAI. Oll. 2. (a) Hydenten ayatem alarm panel alare if CWD

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DOCUMENT FILE NUMBER Ol~2CO2?

DCCUIENT REVISION NUMBER 1 DOCUMENT DIS'"RI30TED ON 3'Ib ..

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COPY TRANSMITTAL COPY TPANSMITT.'C NO. DOCUMENT HOLDER RETUR!ED NO. DOCUMENT HOLDER RETURNED MASTER UNCONTROLLED COPIIS 1

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Page 1 of 3 '

FIBRIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY /0FF-NORMAL PROCEDURE 0120032 REVISION 3 ,

1.0 Title EXCESSIVE REACIOR COOLANT SYSTEM ACTIVITY 2.0 Review and Approval:

Reviewed by Plant Nuclear Safety Committee July 14, 197_55 Approved by K N. Harris Plant Manager July 17 19]_5, 5 Revision 3 Reviewed by Facility Review Group #fa e c /2 198_2.

Approved by #g/g//k Plant Manager 3 - /w 19FL wn---

3.0 Purpose and Discussion:

3.1 This procedure provides instructions for the action to be taken in the event reactor coolant activity becomes excessive.

3.2 Discussion

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A crud burst, failed fuel element, or demineralizer resin exliaustion

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may cause' reactor coolant activity to increase. An increase to levels requiring the reactor to be shut down, howe' vbr, can only be caused by the activity release associated with significant fuel element failure.

4.0 Symptoms

4.1 Reactor coolant letdown monitor R-202 high activity alarm.

4.2 An increase in che fission producc inventory as indicated by an increase in one or more of the following radiochemical analyses:

4.2.1 Iodine 131, 133 values 4.2.2 Gross beta-gamma 4.2.3 Tritium

, 4.2.4 Reactor coolant gamma spectrum

.i FOR INFORMATION ONLY TMs documet i -9 e.** chd. Before use, l verify information with a coni:clied downente

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Pcge 2 of 3 f EMERGENCY /0FF-NORMAL PROCEDURE 0120032 REVISION 3 EXCESSIVE REACTOR COOLANT SYSTEM ACTIVITY I

5.0 Instructions c

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5.1 Immediate Automatic Action: [

, None 1 5.2 Immediate Operator Action:

5.2.1 If the reactor coolant letdown monitor high activity alarm

has energized or if chemical analysis has indicated high RCS activity, perform the following

5 . 2 .1.1 Insure that the alarm was caused by a high radiation condition by source checking channel R-202 or run back up radiochemical analysis as applicable.

! 5.2.1.2 Survey the VCT for any significant increases of radiation levels 5.2.1.3 Increase the letdown flowrate to maximum.

5.2.1.4 Place at least one mixed demineralizer in service.

5.3 Subsequent Action:

5.3.1 Notify Operations Supervisor and Chemistry Supervisor and arrange additional persbanel as necessary. .

5.3.2 Determine RCS gross activity as soon as possible af ter .

verification of alarm I 5.3.3 If reactor coolant activity is significantly greater than the previous week's average

( 5.3.3.1 Perform a radiochemical analysis of the reactor l+ coolant to determine the cause of the increase in j, odivity.

1.

l} 5.3.3.2 Check inservice mixed bed demine alizer D/F, if exhausted. shift to standby demineralizer.

5.3.4 If it is determined that the increase in reactor coolant activity has been caused by a fuel element f ailure:

1 5.3.4.1 Perform the 100/E computation to determine the

Technical Specification limits for reactor coolant

,; activity. based on the current inventory of nuclides

'{ present in the reactor coolant, j 5.3.4.2 Insure dose equivalent Iodine is < 1.0 uci/ gram.

1:

l 5.3.4.3 Increase the frequency of reactor coolant sampling l~

as specified by the Chemistry Department Supervisor.

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Page 3 of 3 >

EMERGENCY /OFF-NORMAL PROCEDURE 012 0 03 2L , REVISION 3 EXCESSIVE REACTOR COOLANT SYSTEM ACTIVITY l

5.0 Instructions

(continued) 5.3 (continued)

, 5.3.5 If reactor coolant activity approaches the Technical hadI Specification limits. perform the following:

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j 5.3.5.1 Reduce power as required by Figure 3.4-1 in Technical Specifications 5.3.5.2 Increase the reactor coolant sampling frequency as necessary based on the rate of change of reactor coolant activity.

5.3.6 If reactor coolant activity reaches the Technical Specification limits below, take action specified:

I 5.3.6.1 When > 1.0 uci/gm Dose Equivalent I 131 but within limits of graph (Fig. 3.4-1 Technical Specifications) may continue operations up to 100 hrs. if operations do not exceed 10% of yearly operating time.

5.3.6.2 Tf > 1.0 inci/gm for > 100 hrs. or greater than limits of Fig. 3.4-1 or, greater than 100/E uci/gm be in mode 3 with Tave < 500F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

5.3.7 Implement the emergency plan as necessary in accordance with ,

EPIP 3100021E, " Duties of the Emergency Coordinator". /R3

[! 5.3.8 Continue sampling as necessary to determine reactor coolant 4 activity trends.

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5.3.9 Health Physics personnel conduct radiation surveys in the auxiliary building and post areas as necessary.

3.3.10 Continue purific uion a. .equired.

5.3.11 Periodically check the inservice mixed bed demineralizer for j resin exhaustion by calculating a decontamination factor.

, 6.0

References:

it i 6.1 FSAR, Chapter 11, Section 11.4 " Process Radiation Monitor".

l' 6.2 Technical Specifications, App. "A" Section 3.48.

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- 6.3 FSAR, Chapter 9, Section 9.3 "CVCS System".

,i 7.0 Records, Reports & Notifications:

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1 7.1 Entry in Plant Log.

! 7.2 Nuclear Plant Supervisor shall ensure that an evaluation is made to 1: determine if a Licensee Event Report is required per Section 3.4.8 l of App. "A" Technical Specifications.

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