ML20063M672

Public Version of Revision 6 to Emergency Plan Implementing Procedure HNP-4825, Emergency Sampling of Primary Coolant & Revision 4 to HNP-4829, Primary Coolant Analysis During Post-Accident Conditions

ML20063M672
Person / Time
Site:	Hatch
Issue date:	08/06/1982
From:	Thomas Greene, Nix H GEORGIA POWER CO.
To:
Shared Package
ML20063M670	List: ML20063M671 ML20063M672
References
PROC-820806-01, NUDOCS 8209150398
Download: ML20063M672 (16)

Text

. . . . _ _. . _ __

e GEORGI A POWER COMP ANY

- HATCH NUCLEAR PLANT .

PROCEDURC .

• Emeraency Sampling Of Primary Coolant PROCEDURE TITLE HNP-4825 PROCEDURE NUMBER .

Lab RESPONSIBLE SECTION NON_ SAFETY RELATED ( )

SAFETY RELATED ( X )

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APPROVED APPROV.ED DEPT. PLANT DATE 4

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EMERCENCY SAMPLING OF PRIMARY COOLANT I

A. PURPOSE ,

To provide a procedure for sampling primary coolant using the Jet Pump instrument rack as sample location for Units I and II.

Sampling will be done with the assumptions of a fuel cladding failure accident of the worse degree possible.

. B. SAFETY Observe Radiation Protection Procedures.

C. PRECAUTIONS .

s;. Due to the high dose rates and contamination levels which are to

be expected with this kind of an accident, extreme care and good -

. sampling techniques must be adhered to and followed.

3',

~

Laboratory supervision shall be consulted on all activities associated with sampling and counting any material dbtained for pcst-accident analysis. _ _

All attempts to get samples will be followed with the most restrictive H.P. practices. Constant H.P. monitoring will be provided and adhered to. A minimum of two persons will be

- ~

required while getting the sample.

. NOTE l

l At no time during sampling will personnel be allowed to receive-

! more than 1.25 R unless a lab l^ Supervisor or his designee signs l FORM 2 of HNP-8002, Authorization to Exceed Administrative Exposure l

l Guides.

D. EGUIPMENT

1. High range survey meter (PIC-6A, Teletector, or equivalent)

2. Count rate instrument (E-120, or equivalent)

3. High range dosimeter (LOR) and TLD's #

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6. Lead shield on wheels

7. Remote handling tools with various attachments

< 8. Self-contained breathing air (SCBA)

9. Finger ring T.L.D.'s ,

10. 75 mi sample bomb l-1. Remote sampling equipment control panel

, 12. Key 1P33 P3OO (For Unit 1 Control Box) or 2P33 P3OO (For Unit 2 Control Box) from " Remote Emergency Handling Tool" Box. ,

13. Absorbant material to be used in case of~ spill.

, 7, NOTE p._v' .

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The equipment referenced in

~

Section D may not be adequate to perform the sampling requirements.

All considerations must be given though prior to actual sampling.

A.R.M. read outs located in either control room will be read prior to entry into the Reactor Building.

Dose rates will be taken while

. enroute to the sampling station.

Air samples will also be taken while getting samples.

While enroute to the sampling station if the whole body dose rate of 10 R/hr is exceeded, 1

retreat (10 R/hr = 166.5 mr/ min).

E. LOCATION l

Unit I l

l Sample will be taken off the jet pump instrument rack located on the 130' elevation southside of the reactor l

building.

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The temporary sampling system will be used until the permanent sampling system is installed and operabl

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• gency sampling system (s) are located on the reactor building 164' elevation on the westside by ~

the stairway.

Unit II

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Sample will be taken off the jet pump instrument rack locate 6 on the 130' olevation northside of the reactor building.

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NOTE ,

' ' ~ The control panels for the

• emergency sampling system (s) are located on the reactor building 164' elevation on the westside by the stairway.

F. SAMPLING (PRESSURIZED VESSEL)

An R.W.P. will be initiated to get a sample. While sample' is being gotten the dose rates will be taken continuously on the sample bomb and other associated equipment.

, NOTE Call Control Room to check and assure that valves 831-FOl9 and 831-F020 are open before proceeding.

1. Connections

a. Place sample bomb in lead cash and place lead brick on shield top to make a sealed cask.

b. Open stem valves on sample bomb (outside of cask) two valves to be opened.

c.

Connect flex tubing to sample bomb (two connections to

• ~ be made outside the cask).

- 2. Flushina Through Domb YE

a. Open manual valve (1821 NO33C TVI for Uni k#We

@dbes are

• NO330 TVI for Unit 2) on jet pump rac %i%1*o ust ,

painted red and are usually in the op pg

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check to make sure the valve is open.

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b. Open valve F306 (chiller water, demin) on control box.

Refer to Figure 1. l Chiller water will return to CRW.

c. Open valves F3OO, F302, and F304 on control box and flush system for 10 minutes. Sample may now be taken.

3. Takino Sample

a. Close valve F3OO, F302, and F304 on control box.

~

b '. Purge sample lines using demin water using Section H.

c. Close manual valves on sample bomb (two valves to be closed) using remote handling tools if dose rates .

require it.

d. Disconnect flex tubing from sample' bomb (two

'7b '

disconnections to be made).

-3' NOTE Any water which may have been dripped when the disconnection was made must be covered up or cleaned up as soon as possible.

e. After survey of the lead cask has been done, the sample is returned to the lab or other area as required by Lab Supervisor to await shipment to an outside vendor for analysis.

NOTE Upon the discretion of a lab Supervisor, the sample may be analyzed in the Hatch Lab if dose rates are low enough.

G. SAMPLING (DEPRESSURIZED VESSEL)

NOTE

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An R.W.P. willWhile be initiated to sample is get a sample.

- being gotten, the dose rates will be taken continuously on the sample bomb and other associated equipment.

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NOTE Call Control Room to check and assure valves B31-F019 and 831-FOBO are open before proceeding.

Connections

1. I

a. Place sample bomb in lead cash and place lead brick on shield top to make a sealed cask.

Open stem valves on sample bomb. (outside of cask two b.

valves to be opened)

c. Connect flex tubing to sample bomb. (two connections to be made outside.of case) s r.

2. Flushino Through Bomb 55 a. Open manual valve (1921 NO33C TVI for Unit 1 or 2821 are NO33C TVI for Unit 2) on jet pump rack. The valves Must painted red and are usually in the open position.

check to make sure the valve is open.

Open valve F306 (chiller water), F3OO, F301, F302 and F304 on control panel. Flush system for 10 minutes, b.

Refer to Figure 1. l sample may now be taken.

3. Takino Sample ,

s. Close valves F3OO, F301, F302, and F304 on control box.

b. Purge sample lines with demin water using Section H.

c. Close manual valves on sample bomb (two valves to be closed) using remote handling tool is required by dose rate.

d. Disconnect flex tubing.from sample bomb (two disconnections to be made)

NOTE

., Any water which may have been dripped when the disconnection was made must be cleaned up or covered as soon as possible.

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e. After survey of the lead cask has been done, the sample l

• and cask are returned to the lab or other area as required by Lab Supervisor to await shipment to an outside vendor for analysis. - ,

8 NOTE Upon the discretion of a lab Supervisor, the sample may be analyzed in the Hatch Lab if dose rates are low

- enough.

H. SYSTEMS FLUSHING Systems will be flushe'd upon tal.<ing a sample to, lower the dose rates in the local area. Flushing time will depend upon the s f- amount of crud stuck in the tubing lines and valves and dose rate

. In the area (Background).

~ 5 '- 1. Open valve F305, F301, and F303 and flush for 15 minutes or

' until Lab Supervision specifies otherwise. ,

2. Close valves F301 and flush through pressure regulator for 30 minutes or until Lab Supervision specifies otherwise.

3. Close velve F305 and F303; this returns system to a l ready-to-sample system.

NOTE Systems flushing (Section H above) l may be used to demonstrate skills in sample taking.

NOTE Recommended route is through the railroad airlock, around the CSTs and in through T-16.

NOTE l

i After obtaining the sample, refer to HNP-4828 " Transferring Primary Coolant from 75 ml Bomb" and HNP-4829 " Analysis of Primary Coolant."

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT .

PROCEDURE Primary Coolant Analysis

.. During Post-Accident Condition PROCEDURE TITLE HNP-4829 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED (X) NON-SAFETY RELATED ( )

APPROVED kPPROVED REV. DESCRIPTION DEPT. PLANT DATE

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^ See Title Pace 1 of 5 h PRIMARY COOLANT ANALYSIS DURING POST-ACCIDENT CONDITION A. PURPOSE To provide a procedure for the analysis to be performed on the primary coolant during post-accident condition. (Fuel cladding failure.) .

B. SAFETY Observe Radiation Protection Procedures'.

C. PR.ECAUTIONS

1. Due to the high dose rates and contaminati,on levels which are to be expected with this kind of a sample, extreme care and good sampling technique must be adhered to and followed.

," 2. Laboratory Supervision shall be consulted on all activities

_  ;,, associated with analysis and counting any material obtained for post-accident analysis.

3. All attempts to analyze _ samples will be followed with the most restrictive Health Physics practices. Constant H.P.

monitoring will be provided and adhered to. A minimum of two persons will be required to analyze the sample.

4. Samples greater than 100 R/hr will be shipped tc an outside vendor for analysis. See HNP-8016 for Radioactive Shi_gment

- procedure. (100 R/hr/ liter = approximately 10 mci /cc).

NOTE At no time during analysis will personnel be allowed to receive more than 1.25 R unless a Lab Supervisor or his designee signs FORM 2 of HNP-8002 Authorization to Exceed Administrative Exposure Guides._

D. EGUIPMENT

1. High range survey meter (P1C-6A, teletector or equivalent)

2. Count rate instrument (E-120 or equivalent)

3. High range dosimeter (10R) and TLD's

4. Full PC's pd b 5. .,: Remote handling tools with various attachmert45 (QVQ de

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• 2 of 5 See Title Paan ,

6. Finger ring TLD's ,

E. ANALYSIS NOTE All equipment must be placed behind lead shielding when performing the analysis. At no time will the liquid waste be allowed to enter the radwaste system.

. NOTE Steps E.2, E. 3, E.4, E.5, and E.6 all need to be performed in the sample hood whenever possible.

The following analy'ses are to be performed on the primary.

. s ;. coolant sample:

.'- (1) D.O. HNP-7225

- }. (2) pH HNP-7202 or 7203 .

(3) Conductivity HNP-7204 or 7205 (4) Chlorides HNP-7004 (5) Iodine Separation .HNP-7110 (6) Borons HNP-7003 ~

(7) Gross Alpha (8) Isotopic The analysis will be performed while the technicians are -

fully dressed out. Working time will limited to dose received. High range (LOR or 20R) dosimeter and finger rings will be worn in addition to normal dosimeters. Prior l

to analysis, be sure to sign in on a blanket R.W.P.

l l 1. D.O.

1 1 The D.O. probe will have to 'e b placed in line after the 75 mi sample bomb has been taken or prior to taking the sample.

a. Place D.O. probe into sample line using quick disconnects and follow procedure HNP-4825 for valve l

i manipulation.

NOTE The center connection of the D.O. probe is the inlet and the farsided connection

- is the outlet. Read D.O. directly on meter face. The D.O. meter will be used with a P 50 foot remote cable. # g, 1 i: I s . ,--va.% /* manal set

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3 of 5

2. pli With remote tools, pour enough sample in a 100 ml graduated cylinder and perform pH. Pour sample back into original flask when pH is finished.,

3. Conductivity, With remote tools, pour enough sample into a 100 ml beaker

, and perform conductivity. Pour sample back into original

- flask when conductivity has been performed. Clean up equipment when finished.

4. Chlorides Pour 25 mis of sample into a beaker and perform chlorides as

<M. per HNP-7004. Clean up all equipment when finished. Allow

' - no waste to enter the rad waste system.

- i' . NOTE Using a remote pipetter, pipet 1 ml of the sample into a one liter poly bottle filled with 999 mis of demin water. Close bottle and shake. Pipet 1 ml of diluted sample into 999 mis of domin water, close, and shake.

Dilution ratio is now after diluting two times 1:1x10'. , l

5. Iodine Sap _aration -

Perform iodine separation in normal manner as per HNP-7131, using a diluted sample from Section E.4

6. Boron l

Perform borons in normal manner and as per HNP-7003, using a diluted sample from Section E.4 Prepare 2 more diluted samples as per Section E.4.

7. Gross Alp,ha j Perform gross alpha analysis as per HNP-7131 Section H.4.

. vt l 8. Isotonie g g. t g 1 .s % fq o I .s , Wrap a one literpolybottleofdilutedwatpyYodQ# form

's . .' isotopic as per HNP-7131 and HNP-7215 anpjayipr9 F of G this 4#

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F. COUNTING NOTE The counting room must be h'abitable for counting samples. If it is not, refer to HNP-7251 for procedure for mobilizing the counting room.

1. Open Ge(Li) shield and place sample on the first shelf of the sample holder and close Ge(Li) shield door.

2. Press the collect button on the MCA and observe the % dead time (%DT) meter. If % DT is greater than 20%, stop collecting spectra by pressing the collect button again and redilute sample until it reads less than 1 mr/hr. If %DT is less than 20% acquire spectra for 1000 sec*onds or as directed by the Counting Room Foreman.

3. When 1000 second5 or count time is finished, the light

, ;, behind the collect button will go out. Check calibration to

1. ' see if it has drifted.

4. Remove sample from Ge(Li) shield and retain for other analysis as may be required later.

G. ANALYZING SPECTRA NOTE Refer to HNP-7215 Ge(Li) systems for additional .

information on counter system.

1. Transfer spectra from MCA to 9845 computer using computer program "CI-8100" or "OR7010."

2. After spectra has been transferred completely, run computer program "RWIDNE" and answer question as required by computer display. Submit printout to Counting Room Foreman for approval and review.

3. Run program " RAP" on the same spectrum if required by Laboratory Foreman. Store spectrum in computer memory for later analysis.

4. Program "RWIDNE" generates data and information on the following:

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5 of 5

a. E Gamma MEV/ DIS

b. E Beta MEV/ DIS .

c. E Total MEV/ DIS 131 -

d. D.E.I

~

131, 132, 133, 134, 135 .

. e. I uci/ml 131

f. Percent of Tech Spec limit for D.E.I. '

NOTE

' ~

3 Computer libraries are not listed in this .

. procedure because of the many different

- }' . isotopes which may need to be identified -

in the sample.

,- H. SPECTRA INTERPRETATION .

NOTE Details of information shall not be released by anyone other than persons allowed to as directed by Plant Management. All samples and spectrums will be stored for review later.

I. DISPOSAL OF HOT SAMPLES NOTE

. Keep sample bomb and all samples in the fume hood I behind lead bricks until proper disposal methods are arranged.

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=,., Georgia Power d ..m ~o See Title Page 8 of 8 TABLE _6 PASGUILL F EIUD SPEED DDSE RATE PER RELEASE RATE (REM SEC)

• Mi/HR __

Ci - HR

. NOBLE GASES IODINE 4 STACK VENT . STACK VENT R/GNs R/GNv R/GIs R/GIv e

O 8.2 E - 3 4.4 E O 7.4 E O 3.9 E + 3 1 4.0 E - 3 2.15 E O 4.0 E O 2.15 E + 3 2 2.1 E - 3 1.2 E O 2.2 E O 1.15 E + 3 3 1.35 E - 3 7.5 E - 1 1.45 E O 7.4 E + 2 4 1.0 E - 3 5.4 E - 1 1.05 E O 5.6 E + 2 5 7.4 E - 4 4.4 E - 1 8.0 E - 1 4.4 E + 2 6 6.7 E - 4 3.6 E - 1 6.7 E'- 1 3.7 E + 2 7 5.7 E - 4 3.05 E - 1 5.7 E - 1 3.1 E t 2

. 8 4.9 E - 4 2.65 E - 1 5.0 E - 1 2.7 E t 2 9 4.3 E - 4 2.35 E - 1 4.4 E - 1 2.45 E + 2 10 3.9 E - 4 2.1 E - 1 3.9 E - 1 2.2 E t 2 11 3.55 E - 4 1.95 E - 1 3.6 E - 1 1.98 E + 2 12 3.29 E - 4 1.79 E - 1 3.3 E - 1 1.8 E + 2 13 3.05 E - 4 1.65 E - 1 3.05 E - 1 1.69 E + 2 14 2. 8E-4 1.52 E - 1 2.81 E - 1 1.55 E + 2 15 2.65 E - 4 1.44 E - 1 2.65 E - 1. 1.45 E + 2 16 2.5 E '- 4 1.35 E - 1 2.5 E - 1 1.38 E + 2 17 2.35 E - 4 1.27 E - 1 2.35 E - 1 1.3 E + 2 18 2.2 E - 4 1.20 E - 1 2.24 E - 1 1.21 E + 2 19 2.1 E - 4 1.14 E - 1 2.12 E - 1 1.16 E + 2 20 2.0 E - 4 1.08 E - 1 2.0 E - 1 1.1 E + 2 21 1.9E 4 1.02 E - 1 1.92 E - 1 1.05 E + 2 22 1.8 E - 4 9.8 E - 2 1.85 E - 1 1.0 E + 2 23 1.75 E - 4 9.4 E - 3 1.77 E - 1 9.5 E + 1 24 1.65 E - 4 9.0 E - 3 1.7 E - 1 9.0 E + 1 25 1.6 E - 4 8.6 E - 3 1.6 E - 1 8.8 E + 1 26 1.52 E - 4 8.2 E - 3 1.55 E - 1 8.4 E + 1

, 27 1.48 E - 4 7.9 E - 3 1.50 E - 1 8.1 E .- 1

! 28 1.4 E - 4 7.6 E - 3 1.45 E - 1 7.8 E + 1 b

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