ML18044A964: Difference between revisions

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*------ -----.---------------'----------------'-=--**-~--'---------'"'--->
*------ -----.---------------'----------------'-=--**-~--'---------'"'--->
PALISt\OES NUCLEAR PLANT                                                                                      PROG tlOEI8-6 EMERGENCY IMPLEMENTATION PROCEDURE PAGE 2              OF        3
PALISt\OES NUCLEAR PLANT                                                                                      PROG tlOEI8-6 EMERGENCY IMPLEMENTATION PROCEDURE PAGE 2              OF        3 cunsum~r.> P!n'!ar TITLE~                  SAMPLING AND ANALYSIS OF HIGH ACTIVITY REACTOR COOLL\NT REVISION O DATE 4/24/80
                                                                                                                                                                                                                    -<*"*
    . '
cunsum~r.> P!n'!ar TITLE~                  SAMPLING AND ANALYSIS OF HIGH ACTIVITY REACTOR COOLL\NT REVISION O DATE 4/24/80
( .L l1. 7        When not being handled, store samples in a shielded location (lead brick barrier is sufficient) to shield personnel from unnecessary radiation exposure.
( .L l1. 7        When not being handled, store samples in a shielded location (lead brick barrier is sufficient) to shield personnel from unnecessary radiation exposure.
4.8        Use a filtered laboratory ventilation hood when uncapping, pipetting or other handling of' unseal1~d samples.
4.8        Use a filtered laboratory ventilation hood when uncapping, pipetting or other handling of' unseal1~d samples.
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                                                               ~  . * ... .
                                                               ~  . * ... .
IJ..e.!.:G.
IJ..e.!.:G.
                                                                                  .
l:l near containment access, traverse the area as quickly as                                                                                                              .._ __
l:l near containment access, traverse the area as quickly as                                                                                                              .._ __
possible and continue to survey the sample rciom.
possible and continue to survey the sample rciom.
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* t'l-!e *e:.q:>cs:.i--:-=. r2t= ::::.=.st::=-~e.=-=s c-~tc:..:-'..2d en* i~it:lal e~-~ry*,
* t'l-!e *e:.q:>cs:.i--:-=. r2t= ::::.=.st::=-~e.=-=s c-~tc:..:-'..2d en* i~it:lal e~-~ry*,
calculate stay time.                                                    Time the second_ entry.
calculate stay time.                                                    Time the second_ entry.
                      ... . *    .    -          ._ **--              -    ..
: b.      Enter sample room to take- sample (sampl_e point SX:-.T023} *...
: b.      Enter sample room to take- sample (sampl_e point SX:-.T023} *...
c~      Obtain a 5 ml sample at the appropriate sample point: Cap and bag sample _container and place it in shielded sampie *carrier*. (available from Radiation Protect:*ion -equipment* s.torage cage)... .                                                                                                    *
c~      Obtain a 5 ml sample at the appropriate sample point: Cap and bag sample _container and place it in shielded sampie *carrier*. (available from Radiation Protect:*ion -equipment* s.torage cage)... .                                                                                                    *
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           ~  -.;:'*': j*~.,:_ :"
           ~  -.;:'*': j*~.,:_ :"
            ..      ,*_ *.*    *
                                              *
                 -*-----~-----*---------------'------*---------.----
                 -*-----~-----*---------------'------*---------.----
PALI SADES NUCLEAF'. PLAi\JT                                                                                            .PPAROGCE          1103._ EIOSF-:- 63 c..:w                            EMERGENCY IlfPLENENTATION PROCEDURE u        /*
PALI SADES NUCLEAF'. PLAi\JT                                                                                            .PPAROGCE          1103._ EIOSF-:- 63 c..:w                            EMERGENCY IlfPLENENTATION PROCEDURE u        /*
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5.3.3              Report results to Chemistry Supervisor or his designated representati-..e.
5.3.3              Report results to Chemistry Supervisor or his designated representati-..e.
l
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                                                                                                                                                                                                                        ...
                                                                                                                                                                                                                                **
                                                                                                                                                                                                                                 ~I i-t:
                                                                                                                                                                                                                                 ~I i-t:
:-_. .. !
                                                                                                                                                                                                                                 ~
                                                                                                                                                                                                                                 ~
                                                                                                                                     ~ ', T*~J!i'~-~~ ;~      i\ '-f~'.~~\9.
                                                                                                                                     ~ ', T*~J!i'~-~~ ;~      i\ '-f~'.~~\9.
                                                                                                                                     -** \-;. (~; ~ ~'~~t-~*! ~ 1:;_i~~~}}
                                                                                                                                     -** \-;. (~; ~ ~'~~t-~*! ~ 1:;_i~~~}}

Latest revision as of 14:31, 3 February 2020

Sampling & Analysis of High Activity Reactor Coolant.
ML18044A964
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/24/1980
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18044A959 List:
References
EI8-6, NUDOCS 8006040320
Download: ML18044A964 (3)


Text

..

e* * ....... *: .................................................. .--**-**""'""*~""*****

PALISADES NUCLE/\R PLANT PROC t!O EI8-6 EMERGENCY INPLcr!ENTATION PROCEDURE PAGE 1 OF 3 TITLE i SA.}{PLING AND ANALYSIS OF HIGH ACTIVITY REVISION 0 REACTOR COOLl\NT 1.0 ruRPOSE To provide methods and radiological precautions for sampling and analysis of highly radioactive reactor coolant during accident conditions.

2.0 REFERENCES

2.1 . NUREG-0578;

  • THI-2 Lessons Learned Task Force Status Report and Short-Term Reconunendations 2.. 2 Chemistry Procedure F3.l, Primary Coolant Syste!!l Sampling.

2.3 Chemistry Procedure Fl*. 3 Boron Analysis 3.0 PRY.REQUISITES None.

I i

(~

I. 4.0 PRECAUTIONS AND LDE!ATIOi:~S 4.1 In addition to routine dosimetry provisions, extremity dosimetry for the hands and a high.range pocket dosimeter shall be.provided to personnel involved in sampling and analysis.

4.2 Radiological conditions (radiation levels, air samp1ing as appropriate) shall be as:;essed in the vicinity of and concurrently wi*:h sampling and analysis activities to assure each individual's radiatio~1 exposure sl{all be less than 3 rems per quarter or less.

t*. 3 Personnel perforrilirig *sampling and analysis shall he equipped with a .

  • p9rtable survey instrument (Eberline "telctector", P6112 or equivalent)

. ~:to monitor actual. radiation levels during sampling and' analysis activities.

4.4 Attempts*to obtain a reactor coola1't sample shall be aborted i f general area

- radia.t:i._on fields ex.ceed .100 R/hour . . u* exposur~ rates exceed 50 R/hr sampling should be performed by different. individuals:-... .

  • 4.5 Anti...:.contamination clot.Il-ing and respir. a.t.ory proteet:ion equipment:: shall
  • be worn as radiological conditions warrant.

4.6 Avoid handling samples 'clirectly with the hands. Use remote handling tools (available in the. hot chemistry laboratory or the back up laboratory location in the Feed\:i'ater Purity Building). When handling samples with the hands cannot be avoided, do so at arms length. *

( .__ .

  • ------ -----.---------------'----------------'-=--**-~--'---------'"'--->

PALISt\OES NUCLEAR PLANT PROG tlOEI8-6 EMERGENCY IMPLEMENTATION PROCEDURE PAGE 2 OF 3 cunsum~r.> P!n'!ar TITLE~ SAMPLING AND ANALYSIS OF HIGH ACTIVITY REACTOR COOLL\NT REVISION O DATE 4/24/80

( .L l1. 7 When not being handled, store samples in a shielded location (lead brick barrier is sufficient) to shield personnel from unnecessary radiation exposure.

4.8 Use a filtered laboratory ventilation hood when uncapping, pipetting or other handling of' unseal1~d samples.

5.0 PROCEDURE 5.1 Reactor Coolant Samp~

5.1.1 Conduct a presample survey of the cold chemistry laboratory to determine if radiation levels are acceptable. Exposure rates greater than 3 R/hr in the coid chemistry laboratory are indicative of inaccessible radiation levels in the sample room.

5.1. 2 a. Using a high-range portable survey instrument, monitor radiation levels in route to sample room.

NOTE: A high radiation field may be encountered in the yicinity of the cont:ain...'TI2nt access* h.:tch. This mav not be indicati*Te of

  • r:ne

~ . * ... .

IJ..e.!.:G.

l:l near containment access, traverse the area as quickly as .._ __

possible and continue to survey the sample rciom.

b. Access the sample room and initiate flushing of the sample, P991'1P.
c. Exit the sample room* when flushing has started. *.Note that increased airborne radioactivity can be anticipated when flushing. and sampling .

is occurring.

5.1. 3 a. E..:.scd o~

  • t'l-!e *e:.q:>cs:.i--:-=. r2t= ::::.=.st::=-~e.=-=s c-~tc:..:-'..2d en* i~it:lal e~-~ry*,

calculate stay time. Time the second_ entry.

b. Enter sample room to take- sample (sampl_e point SX:-.T023} *...

c~ Obtain a 5 ml sample at the appropriate sample point: Cap and bag sample _container and place it in shielded sampie *carrier*. (available from Radiation Protect:*ion -equipment* s.torage cage)... . *

. ~ -* ....-: _-: **--:*."' *.- .. . . . . . . - - .. . . *-.* . . .. ~. ' - . .. - . .. . . : . -- . :** .. . *. - *. . - -::- .. .. ;- .- .

d. Secure.sample line and: transport shielded.sample carrier .to hot chemistry* laboratory. *.

5.2 Sample Dilution and Preparation 5.2.1 Prepare aliquots for_ a boron and gamma spectrum analysis.

5.2.2 For Tadiation exposure purposes, the boron sample should be prepared using )

the smallest volume of the reactor coolant sample that will ensure accurate analytical results. Approximately 2-3 ml of reactor coolant sample diluted to a volume required to perform the analysis should be adequate.

=~~- ~-;7 :r:.~;~'.*J .;~ r~~:~.;~

~ -.;:'*': j*~.,:_ :"

-*-----~-----*---------------'------*---------.----

PALI SADES NUCLEAF'. PLAi\JT .PPAROGCE 1103._ EIOSF-:- 63 c..:w EMERGENCY IlfPLENENTATION PROCEDURE u /*

-.:;~. TITLE. SAMPLING .AND ANALYSIS OF HIGH ACTIVITY

  • REVIS!Oi'I O camrnm~rs PO'!!Rf 'REACTOR COOU,NT DATE 4/211/80 5.2.3 Prepare a diluted reactor coolant sample for ga1mna spectrum analysis. The purpose of sample diluti.on is to .decrease the radioactivity concentration 1 of the sample and thus to limit counting dead time of the spectrum analysis equipment .and :.:-educe radiat:lon exposure to t'!'ie individual performing the analysis. For highly radioactive samples, perform a l.OE+4 to 1 dilution of the reactor coolant sample to prepare the radiological sample.

5.2.4 1-ihen the samples are diluted, perform the analyses in the hot laboratory*

and adjacent counting room. If these areas cannot be used for analysis, perform the boron analysis in the f eeclwater purity building back up laboratory and the gamma analysis in the low level counting*room. DO NOT TRANSFER mnHLUTED SAMPLES TO THESE AREAS.

5.3 Sample Analysis 5.3.1 The methods and precautions giv;.!n in this procedure to reduce personnel radiation exposure should be ob:;erved *when performing boron ar.alysis (reference 3) and gar!'....'!la spectrum analysis.

I

(! 5.3.2 hot laboratory sink. If the laboratory is not accessible, waste samples should be collected irt a shielded liquid waste container. A poly bottle shielded on all exposed sides by'lead walls is adequate for temporary Bample waste dispo~al *

. :..:~~::_t*.-......  : ..:.:.. ...:i.:>.:.;.:;.". ~ ..... *:~ ... (~ . . ~: ... -..:>. ::.:;..* . : .. ; .L.:...:i.:..;."l.:.:.:."* .* ~~-... ::: ... * .. :..:-

5.3.3 Report results to Chemistry Supervisor or his designated representati-..e.

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