Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Erpip 4.4.7.2 Re post-accident Containment Atmosphere Sampling & Erpip 4.4.7.3 Re post-accident Reactor Coolant Sampling
	ML20083M299
Person / Time
Site:	Calvert Cliffs
Issue date:	01/12/1983
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20083M257	List: ML20083M278; ML20083M299;
References
	PROC-830112-01, NUDOCS 8302010126
	Download: ML20083M299 (119)
	v • d • e

.

s ERPIP 4.4.7.1 REY. 9 TITLh.: CONTAINMENT RMS READING VERSUS TIME FOLLOWING ACCDENTS p.

l.0 RESPONSIBLE INDIVIDUAL The Radiological Assessment Director is supported as necessary by the Chemistry Director, Radiation Protection Director, Technical Support Center Director and the Site Emergency Coordiretor. The RAD is responsible for determination of the size of the radioactive release into the containment.

2.0 CONDITIONS AND PREREQUISITES 2.1 Containment Radiation Monitors are operable.

2.2 As directed by the SEC or as necessary to determine the scope of the radiological accident.

3.0 ACTIONS AND LIMITATIONS 3.1 Immediate estimate of core damage.

3.1.1 Determine and record the Containment Radiation Monitor exposure rate (R/h) and the time subsequent to the Reactor Shutdown (t) when the exposure rate was measured on Attachment I.

3.1.2 If the Time After Reactor Shutdown (t',.s 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or less, to estimate core damage, refer to Attachment II, GAMMA EXPOSURE RATES AT CONTAINMENT CENTER.

3.1.2.1 Divide the exposure rate determined from RMS, by the Exposure Rate (R/h) IIsted on Attachment II at the time (h) subsequent to Reactor Shutdown.

- NOTE -

Interpolate, as necessary, recognizing values are not linear.

3.1.2.2 The nondimensioned value determined is the fraction of core Inventory released to the containment atmosphere and is t

thus an approximation of the percent of core damage based on the assumptions listed on Attachment II.

i 3.2 Determination of the size of the radioactive release into the containment.

3.2.1 Use the information recorded in Step 3.1.1 and Attachment III(a plot of Attachment V).

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ERPIP 4.4J.1 REV. 9 3.2.1.1 Plot the point corresponding to Time after Reactor' Shutdown (days) and Containment Exposure Rate (R/h).

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- NOTE -

This point provides a conservative reference from which estimates of release of Coolant ActivPy (Inventory),

Gap Aedvity, and FuelInventory can be made.

3.2.1.2 Read and record the fracdon released of Coolant activity, Gap Activity, and Fue1 Inventory based on the relationship between the plotted point and the Intersection of its day IIne with each of the fraction - released lines.

Fraction Release of Coolant Acdvity :

Fraction Release of Gap Activity Fraction Release of FuelInventory

- NOTE -

All vertical distances are on a Iogarithmic scale. Also, if the release Hne Intersects the day IIne below the plotted point, assume the Information on the release IIne has occurred (If a 100%

7 Line) or has been exceeded Gf a 1% or 10% IIne).

3.2.2 If the Time After Reactor Shutdown (t) is greater than 4 days refer to Attachment V.

- NOTE -

Information presented on Attachment V assumes zero decay time Time (d) = 0 on Attachment II and Attadment III. Therefore, values In the EXPOSURE RATE columns of i

the Table must be decayed based on days since

=Mdant and HAI.F I.IFE (right hand column) of each radionuclide.

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ERPIP 4.4.7.1 REV. 9 3.2.2.1 To calculate 'the activity of specific radionuclides decay the

_P activities usinJ the formula:

A' = A EXP (-0.693)(t/tg, in days {

g Wheres T = Time (in days) after Reactor Shutdown Tg = Half-life Gn days) of the specified Nuclide A, = Activity at Time (T) = 0 A = Activity at Time (T) 3.3 Compare the mimfated values with those obtained in ERPIP 4.4.7.2, containment atmosphere sampling and those of ERPIP 4.4.7.3 or 4.4.7.6, Reactor Coolant Ac:ivity Sampilng.

, 3.4 Based upon results of comparisons and consultation with the CD, RPD and TSC personnel, when necessary revise estimates of core damage, RCS status, then review EALs and advise the SEC of any recommendations to reclassify the emergency.

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ERPIP 4.4.71 REV. 9 ATTACHMENT I O

CONTAINMENT RADIATION MONITOR LOG SHEET Date/T*gne of Ac::ident (T=0) :

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Unit 1 2

MONITOR READINGS (R/h) 1 1

Low Range (10A 10 )

High Rana (10 0 o3)

Tune After RI-5316A RI-5316B RI-5317A RI-5317B Failed Initials Ac=ident (h)

RI-5316C RI-5316D RI-5317C RI-5317D Fuel l

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4 ERPIP 4A.7.1 REV. 9 ATTACHMENT II b

GAMMA EXPOSURE RATES AT CONT /JNMENT CENTER Time (h) after Reactor Exposure Rate (R/h)

Shutdown 6

0 3.3 x 10 6

0.03 (1.3 min) 2.9 x 10 5

0.5 (30 min) 9.3 x 10 0.75 (45 min) 8.7 x 105 5

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8 1.8 x 10 24 4.3 x 10"

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96 1.1 x 10 Assumprions: (1) Power level-2700 Mwt (2) Release at T = 0, (at Reactor Shutdown) 100% of core inventory of noble gases,50% of the iodines (Chemical form of lodine 91% I, 5%

2 particulate bound, 4% organic).

(3) Contamment sprays actuate removing elemental iodine at rate of I

27%/h, and particulate iodine at rate of 43%/h.

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" Predicted Conta1= ment E.r.resure Raess O

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ERPIP 4.4.7.1 REY. 9 ATTACHMENT IV O

PREDICTED CONTAINMENT EXPOSURE RATES VS TIME l

Time 100% RELEASE REACTOR 10% RELEASE 1% RELEASE 100% RELEASE (d)

COOLANT ACTIVITY FUEL INVENTORY FUEL INVENTORY GAP ACTIVITY 0

2.74E+02 1.26E+06 1.26E+05 4.00E+02 1

3.18E+01 6.78E44 6.78E+03 3.66E+02 3

2.07E+01 2.52E+04 2.52E+03 3.07E+02 7

1.21E+01 1.35E+04 1.35E+03 2.15E+02 14 5.16E+00 6.90E+03 6.90E+02 1.16E+02 21 2.22E+00 3.63E+03 3.63E+02 6.26E+01 35 4.47E-01 1.03E+03 1.03E+02 1.86E+01 49 1.05E-01 3.03E+02 3.03E+01 5.59E+00 63 9.05E+01 9.05E+00 1.71E+00 77 2.79E+01 2.79E+00 5.49E-01 91 9.60E+00 9.60E-01 2.05E-01 i

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ATTACilHENT V ACCIDENT BEREASE INSIDE CodTAIMHEWT (DATA)

ACCIDENT RELEASE INSIDE CONTAlletLT DATA

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(PFEDICTED CONTAINHENT EXPSOURE RATES FOLLOWilc0 IMITI AL kt't. EASE OF REACTOR COOLANT ACTIVITY. FUEL INVtWIDRY. AND CAP ACTIVITY)

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100 Pt.kCENT bel. EASE OF BEACTOR C00l ANT ACTIVITY 101 AND 1 I BEIEASE OF FUEL, INVEtrTotL 10')I BElEASE OF CAP b_C_IIVITY ll 7101 F Q 10I F.F. (17 TOTAL RESULTAlff FUEL TOTAL RESULTANT 101 F.F.

11 F. F.

TOTAL RESULTANT ACTIVITY ACTIVITY A1Nos.

EIPOSukE ACTIVITY ATHOS.

EXPOSupE EXPOSURE ACTIVITY A11403.

EXPOSURE RATE RELEASED ACTIVITY' RATE RATE RELEASE 0 ACTIVITY RATE llALFLIFE CONC. NCS RELEASED ACTIVi{Y l

(C1/m )

(t/le)

(Cl)

(C1/m3)

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'(kfl )

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(Ct/m3)

(k/ti)

(J) l Mapl 0NuctIDE (uct/ca )

(Cl)

Esyptun-85m 1.49 Et 00 5.08Et02 8.98E-03 1.06Et0G 1.92Et06 3.39E601 3.98Et03 3.98E402 1.83E-01 Egypton-85 8.85E-On 3.03Et02 5.34E-0) 8.43tD-03 6.09Et04 1.00E600 1.78E400 1.78E-01 1.98E603 3.50E-02 5.79E-02 3.93Et03 Egypton-87 8.10E-01 2.76Et02 4.88E-03 2.57EtOO 3.53E406 6.24,Et91 3.29Et04 3.29Et03 5.28E-02 i

Egyptua-88 2.60Et00 8.87Eth2 1.57E-02 1.22Et02 5.04Et06 8.96Fs01 1.73E405 1.73Et04 1.17 E- 01

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twJina-131 3.97Et00 1.35E403 1.19E-02 3.5tEt00 h47E406

6.60E601 1.96Et04 1.96Et03 7.005604 1.24E400 3.70Et02 8.06Et00 Kenon-13tm 1.4 bet 00 5.05Et02 8.29E-03 2.29E-02 5.27E604 9.31E-01 2.39Etot, 2.39E-01 2.92E402 5.16E-03 1.32E-02 1.18Et01 lodins-132 1.09Et00 3.72E402 3.29E-03 5.89Et00 1.08Et07 9.54E401 1.70E405 1.70Et04 9.58E-02 toJinn-133 5.66600 1.93E403 1.70E-02 7.83E600 1.52Et07, 1.34E602 6.17E404 6.17E+03 8.67E-01 Xenon-133 1.8tEt02 6.17E604 1.09Et00 2.55E401 1.52E407 2.69Et02*

6.33E603 6.33Et02 7.34Et04 1.30Et00 3.04Et01 5.3tEt00 l

luJana-134 6.20'E-01 2.11Et02 1.86E-03 3.29Et00 1.64Et07 1.45E407 2.55Et05 2.55Et04 3.61E-02 toJino-135 2.70Et00 9.21Et02 8.14r-03 1.13E*01 1.41Et07 1.25E402 1.74E405 1.74E404 2.78E-01 Es-135m 3.05E606 5.39E,401 1.825t(14 1.82Et03 1.06E-02 Xa-135 7.53E100 2.57Et03 4.54 E-02 8.77E601 2.65Et06 4.68E401 9.05E603 9.0$E402 3.80E-01 u-138

.60E-01 1.2nt02 2.17E-03 3.45Et00

1. 22E407 2.16Eco2-3.415405 3.41604 9.86E-03 I

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THIS TABLE FRESEllTS THE CALCULATED BADioWUCLIDES l

CotifultuTlHG TO Tus C00lTaltlHEllT A11tOStitERE ACTIVITY lietEDIATELY SUBSEquRNT TO Att ACCIDEttT i

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SUPERVISOR POSRC PLANT SUPERINTENDENT DATE EFU SIG/DATE MTG

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PagQof 4 Rev.

9-CALVERT CLIFFS NUCLEAR POWER PLANT

,A, EMERGENCY RESPONSE PLAN

'J IMPLEMENTATION PROCEDURES

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LIST OF EFFECTIVE PAGES -

ERPIP PAGE REV.

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ERPIP NO.: 4.4.7.2 / Rev.10 TITLE:

POST-ACCIDENT CONTAINMENT ATMOSPHERE SAMPLING h

1.0 RESPONSIBLE INDIVIDUAL The Chemistry Director (CD)is responsible for determining the need for performing post-accident containment atmosphere sampling.

Members of the Liquid Release Monitoring Team are responsible to the CD for obtaining post-accident sample (s) (very high level radioactive sainpies) of l

containment atmosphere and for taking them to the Radiochemistry Laboratory (first priority), Calvert Cliffs Mobile Laboratory No.1 (second priority), or as directed by the CD.

The Liquid Release Monitoring Team Leader is responsible for utilizing the proper sample equipment, protective clothing, etc., and collection methods for obtaining and handling very high level samples, as directed by,the CD.

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The Emergency Reentry Monitoring Team member is responsible to the Radiation Protection Director (RPD) for ens'uring exposure control in accordance with the 2

Emergency Work Permit as s,pecified in this procedure.

2.0 CONDITIONS AND PREREQUISITES 2.1 Containment Radiation Monitering System (RE 5316 (range 10E-4 to 10 R/h);

RE 5317 (range i to IES R/h)) indicat-200 m R/h.

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E R PIP N O.: 4.4.7.2 / Rev.10 2.2 When directed by CD.

4 2.3 Hydrogen analysis samples taken pursuant to this procedure are to be repeated

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on a routine basis as necessary, to determine activity levels and trends.

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2.4 Very high level radioactive samples are so designated, if exposure rate level is greater than 2.0 R/h on contact.

- NOTE -

Lead 11ned gioves, finger rings, lapel samples, plastic hoods, SCBA, and Hign Range gamma exposure rate meter and pocket dosimeter shall be worn to take the RCS samples (Reference EWP #003 ERPIP Exhibit 4.3.1-0).

2.5 Cbtaining a containment atmosphere sample shall be planned to be performed promptly (~one hour) under accident conditions without incurring a radiation exposure to Individual (s) in excess of 3 and 13.75 rem (10 CFR 20) to the whole body or extremities, respectively. Exposures shall not exceed 5 rem and 75 rem (Appendix A,10 CFR 50) to the whole body or extremities,

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respectively.

Q 3.0 ACTIONS AND UMITAT.ONS i

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RPD Name Date Time ERPIP INITIATED 4

1 3.1 Based on anticipated radiation exposure levels or gross area monitor readings (RMS), the RPD shall scecify:

3.1.1 The use of Emergency Work Permit, EWP #003, for post-accident sampling.

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ERPIP NO. 4.4.7.2 / Rev.10 i

e 3.1.2 Entries made for Containment Atmosphere are to be made in l

accordance with ERPIP 4.3.1.

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3.1.3 Alternate routes if necessary.

1 3.1.4 Designated doors to open and shut to retreive samples, existing radiation barriers, and maximum stay times.

3.1.3 Authorized personnel radiation exposure limits for each entry on EWP

003.

3.1.6 Labeling of samples performed prior to entry. Sample data to be.

l recorded on Attachment I," Accident Sample and Analysis Data Sheet."

3.1.7 The collection of the following:

j 3.1.7.1 Accident Sampling Kit (Located in Radiochemistty Laboratory),

3.1.7.2 Lead Pig, and 3.1.7.3 Transport Cart.

3.2 The ERMT member and LRMT member shall icintly carry out monitoring

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and collection of very high ' level sample (s) as follows and document on A.ttachment I, " Accident RCS Sample and Analysis Data Sheet," as appropriate, upon completion of reentry sampling.

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ERPIP NO.: 4.4.7.2 / Rev.10 '

ERMT Memoer LRMT Member r

3 2.2 Upon direction by the RPD, creoare fer reentry according to Emergency Work Permit. EWP

003, as follows:

3.2.2.1 Receive briefing by RPD, per items 3.1.1 thru 3.1.7 above.

3.2.2.2 Read, understand, and sign EWP #003 and receive briefing by the ERMTL as to stay time limitation, protective clothing, specific route to work locations, and radiological conditions expected.

Briefing Conducted:

/

l Initial Date 3.2.2.3 Collect the following material Collect the following materials from the from the Emergency Reentry Radiochemistry Laboratory: (check when Equip. Locker: (check when performed) performed)

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1.

Radiac Monitoring Equip-1.

Key for the PAHAS #75

( )

ment per EWP #003 ( )

2.

Accident Coolant Sampling Kit

( )

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Maps, stop watch, portable 3.

Inventory prior to entry

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radio, air sampler and 4.

Lead Gioves

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dosimeter. ( )

5.

Lead Pig for Sample

()

6.

Transport Cart

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ERMT Name Time LRMT Name Time 3.2.2.4 Prepare map showing route and expected radiological con-ditions - attach to EWP #003 3.2.2.5 Don protective clothing, dosimetry and respiratory protection devices, lapel air samples as l

specified on EWP #003. (Clothing and monitoring equipment located in the Emergency l

Reentry Equipment Locker,69' Aux. Building for preaugmentation use).

ll'3.2.2.6 Ensure personnel monitoring l

equipment and operational l!

radiac instruments are placed on transport cart prior to entry.

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ERPIP NO.: 4.4.7.2 / Rcy.10 j

ERMT Member LRMT Member O

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322 When approved by the RPD, proceed to the Post-Accident Hydrogen Analyzer System access area on the 45' elevation of the Aux. Building west side.

3.2.2.3 Supervise and provide con-tinuous radiation protection coverage for LRMT member, control stay times and use portable radio to notify RPD of procedure steps performed and exposures rates detected.

- CAUTION -

FAILURE TO USE THE LEAD SHIELDING PLACED IN THE HYDROGEN ANALIZER, TO THE FULLEST EXIENT 70SSI3LE, MAT RESULT IN UNDUE RADIATION EX205URE.

- NOTE -

The following sections (3.2.2.9 and 3.2.2.11) of the procedure deal with the operation of the Post Accident Hydrogen Analyzer System. In order to sample the containment atmosphere, the hyd'rogen analyzer must be in service.

Therefore, eye y effort should be made to obtain the required containment atmosphere sample during the hydrogen analysis whenever practical 3.2.2.9 Operation of the Post Accident Hydrogen Analyzer to enable containment atmosphere grab sampling.

i 3.2.2.10 Containment Atmosphere Sample Grab in the Respective Units Chemistry Sample t

Room. Location of the Sample Rooms are shown in Attachments II and III. The sample valve arrangement is shown in Attachment IV.

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Ensure sampling area has Ensure that all sample lines are 9

been prepared as follows:

isolated by turning all the sample s

flow cells OFF except for DI-6450 (PS-169).

1.

Transport cart carrying i

i open lead container and equipment located out-

,4 side of shield wall and easily accessible for receipt of the very high level sample.

2.

PIC-6A and RO-7 (0-20K Perform the following to obtain a R/h scale probe) turned containment atmosphere sample:

l on to high scale and (Ensure sample sink hood ventilation placed on transport cart fan is ON and operating).

behind shield.

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2a.

Provide contiruous moni-Using the remote handling tool CPEN l' l toring coverage during

.the isolation valves to the sample remaining sample steps.

point (See Attachment IV).

Ensure lapel air samplers are turned on.

b) 2b.

Record exposure rates and Permit the sample point to be purged

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time during each step per-a minimum of two minutes. Stand behind formed.

the shield during the purging.

R/h Time i

2c.

R/h Time Quickly, obtain atmosphere sample by placing i

syringe (5 cc) into the sample point and filling.

2d.

R/h Time After filling the syringe, place it in the lead i

container. Close the lid.

2e.

R/h Time Close the Sample Point Isolation Valves.

l Depart with ERMT member and shielder i

sample.

2f.

R/h Time 2g.

R/h Time 2h.

R/h T*une

{

4, 6

?

..,r..-

- ~ ~ e m-."'" m.

- ' ~ ~ " " ' '

ERPIP NO.

4.4.7.2 / Rev.10 ERMT Member LRMT Member J

3.

Promptly exit Sample Room with LRMT member and sample cart and radiac Instrumentation.

3.2.2.11 After containment atmosphere grab sampling has been obtained, place the hydrogen analyzer in STANDBY mode.

a.

Switch the functional selector switch back to STANDBY.

b.

Close all key operated gas sample valves.

c.

Turn all switches on the sequencer to OFF.

d.

Close the containment or plant vent discharge line.

3.2.2.12 EXIT THE AREA AS SOON AS POSSIBLE.

1.

Provide continuous monitoring Deposit sarnple in Chemistry Hot Laboratory coverage during the transport or as directed by CD for analysis in accordance of shield sample to the with Attachment L

. radiochemistry laboratory

()

and minimize radiation exposures by effective use of barriers and minimum stay time.

2.

Ensure personnel exposure Prepare sample tag with the following data, and data has been recorded on and tie to sample collection apparatus container.

EXHIBIT 4.3.1.

a.

Name and type of material

(

)-

b.

Time sample taken

( )

c.

Sample #, if applicable

( )

d.

Location of sample.

( )

i mR/h on contact after sample e.

containment

( )

Leave Attachment I with the sample for l

analysis.

t i: O ll l 4 l :

7 l t l l 1 -

__.-..._,w...-._,_

.-_.m-,.--

~~ ~

E R PIP N O.: 4.4.7.2 [Rev.10 4.0 PROCEDURE

}

4.1 Acoartus 4.1.1 The control panel, IC139, located on the -5' elevation of the Auxiliary Building l

contains all alarm indications, flow meters, and calibration controls.

4.1.2 The control panel, IC101, located on the 45' elevation of the Auxillary Building contaim all of the valve controls and the sample sequences necessary to analyze a l

sample (See Attachment V).

4.2 Method 4.2.1 Proceed to the control panel IC101 on the 45' elevation of the Auxillary Building with key #75 to analyze a sample of containment air for hydrogen content.

4.2.2 Verify that the power is "ON" and the analyzer is in the " STANDBY" mode.

- NOTE -

If the analyzer is not in " STANDBY" or " ANALYZE," then it will be necessary to wait six (6) hours to allow the heater blocks to be at the correct temperature.

g

- NOTE -

If the panelis in an alarm conditon, press the reset button. If it does not reset, reset control to the panel by l

depressing the remote button and push reset button.

l Repeat at least three (3) times. 'If it still does not reset, l,

notify the RPD that entry into the -5 elevation may be i

required to determine the cause'of the alarm.

l 1

g)-

4 4

i

't e - - ~ ~ ~ ~,- - -

ERPIP Nd.: 4.4.7.2 / Rev.10

=

4.3 ' place the purge selector switch to ON.

4.4 To obtain a sample from containment, it will be necessary to open both the inboard and outboard key operated valves of the intended sample point. These are listed on Attachment V. In addition, the inboard and outboard sample key operated valves on the return to U-1 Containment (1-HS-6540G) must also be opened.

4.5 If any other point is to be analyzed, only the sample sequencer switch and the discharge to the plant vent valves must be open.

4.6 Place the Sequencer Switch to manual and purge the system for 15 minutes (minirnum). Remain in a low dose rate area while purging is in progress.

- CAUTION The containment gas pump can only operate for 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months of continuous duty.

, 5.0..

REPORTING 1

.1 5

Report promptly and verbally preliminary data obtained during entry to the CD and RPD. Brief CD and RPD en the following as a minimum.

~

5.1.1 Exposures received by reentry personnel (SRD-type data) 5.1.2 Exposure rates measured enroute to sample room & maximum exposure rates measured within sample room during entry.

5.2 Collect lapel air samples & send to counting laboratory for analysis.

5.3 Report to CD for full debriefing and provide copy of completed data shown on Attachment I.

e O

9

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F***"

--*"*+e"MDN*"

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8 ATTACHMENT I ACCIDENT SAMPLE NND ANALYSIS DATA SHEET C

}

SAMPLE #

SAMPLE LOCATION:

UNIT 1

2 SAMPLE:

DATE:

TIME:

DOSE RATE ON CONTACT:

mrem /hr REMARKS:

t l

SAMPLED BY:

LMRT l

ANALYSIS TO BE PERFORMED:

RESULTS

(

) Gross Bets / Gamma

(

) Gamma Spectrum Analysis

(

) Boron Analysis

(

) Chloride Analysis

(

) Other (Specify) t ANALYSIS P'ERFCRMED BY:

/

LRMT DATE TIME NOTES: (1) Report results to CD as soon as practiczL (2) Retain all samples for future use.

l Storage Location Placed in storage area by:

/

l Date Time REMARKS:

i

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10 1

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REV. 10

.s e

ATTACmfENT IV SAMPLE POINT VALVE ARRANGEMENT PT SI?Tmi.!C-3 O r-h a

u STRDIGE 7

K h

e V

~

^

To THE ETDRCGIN

'FRCM CCNTA_%7 ANALIZE u$' H.I7ATIcN a

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ATTACHMENTV l

I q

KEY OPERATED VALVES

'h

~

SAMPLE POINT INBOARD OUTBOARD CNTMT 1 SOUTH PRIMARY SHIELD 6507B 6540B CNTMT 1 PRESSURIZER 6507C

6540C CNTMT 1137 ELEVATION 6507D 6540D CNTMT 2 NORTH PRIMARY SHIELD 6507A 6540A l

~

l CNTMT 2 WEST 137 ELEVATION 6507E 6540E h

t..

CNTMT 2 DOME 139' ELEVATION 6507F 6540F CNTMT 1 RETURN 6507G 6540G

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- - ERPIP 4.4. '. 2 RE7II'J/ APPROVAL

?OS*I ACODE3'T 001rf*iW A*210S?N SEGL3G EVISION CHANGE REVIEWER SIG/

SUPERVISOR POSRC PLANT SUPERINTENDENT DATE

- EPU SIG/DATE MTG

/DATE h

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Paga l of i,

R v.

10 CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN m

IMPLEMENTATION PROCEDURES L.

..D LIST OF EFFECTIVE PAGES_

d ERPIP PAGE REV.

ERPIP PAGE REV.

I 10 2

10 3

10 4

10 5

10 6

10 7

10 4

10 9

10

.. 10 10 11 10 12 10 13 10 14 10 0

e; i

n, t

PWM NP -

TI

," " ' * * * ~

#* " " " '#"'~

ERPIP NO. 4.4.7.3 / REV. 9 TITLE:

POST-ACCIDENT REACTOR COOLANT SAMPLING 1.0 RESPONSIBLE INDIVIDUAL The Chemistry Director (CD)is responsible for determining the need for performing post-accident reactor coolant sampling.

Members of the Liquid Release Monitoring Team are responsible to the CD for l

obtaining post-accident sample (s) (very high level radioactive samples) of reactor coolant and for taking them to the Radiochemistry Laboratory (first priority),

Calvert Cliffs Mobile Laboratory No.1 (second priority), or as directed by the' CD.

The Liquid Release Monitoring Team Leader is responsible for utilizing the pro,per sample equipment, protective clothing, etc., and collection methods for obtauung and handling very high level samples, as directed by the CD.

l The Emergency Reentry Monitoring Team member is responsible to the Radiation Protection Director (RPD) for ensuring exposure control in accordance with the Emergency Work Permit as specified in this procedure.

-Ntyrz-This procedure is to only applicable if the Post Accident Sampling System is not OPERABLE. If the PASS is in

{}

service, use ERPIP 4.4.7.6.

2.0 CONDITIONS AND PREREQUISITES 2.1 In-line failed-fuel detector (Process Radiation Monitor - R202) (CVCS Control

~

Board IC07 or 2C07) of affected unit under accident conditions gives an Indication of an increased level of Iodine-135 in the reactor coolant system as follows:

5 RI-202-1 Gross Rate Meter-Alert IX10 m

RI-202-2 Linear Rate Meter (Failed Fuel onitor) (Analysis for I-135)

High Alarm - 70% Fuel Scale (Amber Light), and High High Alarm - 90% Fuel Scale (Red Light), or when this monitor is inoperative, under accident conditions.

2.2 When directed by CD.

,2.3 RCS samples taken pursuant to this procedure are to be repeated on a routine basis every hour as necessary, to determine activity levels and trends.

2.4 Very high levelif exposure rate levelis greater than 2.0 R/h on contact.

i (OBSERVE NOTE ON FOLLOWING PAGE)

O 1

N

, i.,~, - ery

,=+w 7%

suropee ' * ~ p - 7 "* * **" " M*t*N -

---'-~""'"**""NT"7 m-..

~

---.._L~

r ERPIP NO.

4.4.7.3*/ REY. 9 3

- NOTE -

8._

Lead lined gloves, finger rings, ! ape! samples, plastic

.)-

hoods, SCBA and High Range gamma exoosure rate meter and pocket dosimeter shall be worn to take the RCS samples.

2.5 Obtaining a reactor coolant sample shall be planned to be performed promptly t

(vone hour) under accident conditions without incurring a radiation exposure to individual (s) in excess of 3 and 13.75 rem (10CFR20) to the whole body or extremities, respectively. Exposures shall not exceed J rem and 75 rem (Appendix A,10CFRJ0) to the whole body or extremities, respectively.

3.0 ACTIONS AND LIMITATIONS

/

CD Name Date Time ERPIP INITIATED l

3.1 Base i on anticipated radation exposure leveis or gross area monitor readngs (RMS), the RPD shall soecify:

i 3.1.1 Tne use of Emergency Work Permit, EWP #003, for post-accident sempling of reactor cociant.

3 l

O 3.1.2 Alternate routes if necessary.

q 3.1.3 Designated doors to open and shut to retrieve samples, existing ~

radiation barriers, and maximum stay times.

l l

3.1.4 Authorized porwoiel radation exposure limits for each entry on EWP

003.

3.1.5 Labeling of samples performed prior to entry. Sample data to be recorded on Attachment L " Accident Coolant Sr.mple and Analysis l

Data Sheet."

j 3.1..' '!he collection of the following:

i l

3.1.6.1 Accident Coolant Sampling Kit (Located in Radochemistry l

Laboratory) l 3.1.6.2 Lead Pig 3.1.6.3 Transport cart 2

l I

i 1

PKFIF NO.a 4.4.7.3 / REW. 9 ERMT Member LRMT Member 3.2 The ERMT member and LRMT member shall jointly carry out monitoring and C',

collection of very high, level sample (s) as follows and document on Attachment I, l

" Accident RCS Coolant Sample and Analysis Data Sheet," as appropriate, upon completion of reentry sampling.

3.2.1 Upon direction by the CD, contact the Control Room and request that the Reactor Coolant Sample Isolation Valve be OPENED.

Control Rm Contacted:

/

Initial Date Time l

3.2.2 Upon direction by the RPD, prepare for reentry according to Emergency Work Permit, EWP

003, as follows:

3.2.2.1 Receive briefing by RPD, per items 3.1.1 thru 3.1.7 above.

3.2.2.2 Read, understand, and sign EWP #003 and receive briefing by the ERMTL as to stay time limitation, protective clothing, specific route to work locations, and radiological conditions expected.

Briefing Conducted:

/

Initial Date Time

( '42.3 Colle t the following material Collect the following materials from the from the Emergency Reentry Radlochemistry Laboratory: (check when Equip. Locker: (check when performed) performed)

1. Radh.c Monitoring Equip.-

1. Key for the HS-5467 (CV-5467)( )

ment per EWP #003 ( )

2. Accident Coolant Sampling Kit ( )

2. Maps, stop watch, portable

3. Inventory prior to entry ( )

radio, air sam dosime:er. ( pler and

4. Lead gloves ( )

)

5. Lead pig for sam

)

6. Transport cart ( ple (

)

i

/

ERMT Name Time LRMT Name Time 3.2.2.4. Prepare map showing route and expected radiological con-ditions - attach to EWP #003 3.2.2.5 Don protective clothing, dosimetry and respiratory protection devices, lapeliair samples as specified on EWP #003. (Clothing and monitoring equipment located in the Emergency Reentry Equipment Locker,69' Aux. Building for preaugmentation use).

C 3

- A ~

~~~ " ~

e ERPIP NO.: 4.4.7.3 / REV,. 9.,

ERMT Memoer l

LRMT Memoer

^

3.2.2.6 Ensure personnel monitoring equipment and operational radiac Instruments are placed on transport cart prior to entry.

/

Inrtial Time 3.2.2.7 Then approved by the RPD, proceed to the affected unit's reactor coolant sample sink access area on the 45' elevation of the Aux. Building west side.

I 3.2.2.3 Supervise and provide con-l tinuous radiation protection i.

coverage for LRMT member, control stay times and use portable radio to notify RPD of procedure steos performed i

(

and exposures mtes detected.

3.2.2.9 Prior to entry into Reactor Coolant Sampling Room, review l

section 3.2.2.10, step i thru 3 with LRMT member.

Q

- CAUTION -

g ymM TO USE LIAD SHIILDING. MIRRORS MD MECHANICAL EZIRIMITT IIIINSIONS 7LACID IN THE SAMPLZ SUE AREA, TO IEE FULLEST r.wM POSSDLI, j

MAY RESULT IN UNDUE RADIATION EXPOSURE.

i l,

,s l

l 3.2.2.10 Ensure sampling area has Ensure that all sample lines are Isolated been prepared as follows:

by turning all the sample flow cells CFF

.I except for DI-6450 (PS-169). Fully OPEN TI-4450.

1. Transport cart carrying open lead container and equipment located out-side of shield wall and easily accessible fer receipt of the very high level coolant sample.

l 4

l x

i

,,,,,.,.n-._.-

E R P IP N O.: 4.4.7.3 / REV. 9

=

s I

ERMT Member LRMT Member s

)

p~'

2.

PIC-6A and RO-7 (0-20K Perform the following to obtain a RCS R/h scale probe) turned Coolant sample:

on to high scale and Turn on the sample hood placed on transport cart ventilation fan.

behind shield. Use 1

Attachments II and III for dose rates observed enroute.

2a. Provide continuous moni Connect the Post-Accident Coolant toring coverage during Sample Collection Apparatus (PASCA) remainmg sample steps.

to make fittings in the RCS sample Ensure lapel air samplers hood. (See Atrachments IV and V for are turned on.

valve connection locations.)

2b. Record exposure rates and OPEN valve labeled " ISOLATION VALVE time during each step per-11/21 PRESSURIZER SAMPLE COLLECTION formed.

APPARATUS and FILTER DOWNSTREAM."

i R/h T*ne u

OPEN valve labeled " ISOLATION VALVE 2c. R/h T*une 11/21 PRESSURIZER SAMPLE COLLECTION APPARATUS DOWNSTREAM."

OPEN valve labeled " ISOLATION VALVE 2d. R/h Time 11/21 PRESSURIZER SAMPLE COLLECTION APPARATUS UPSTREAM."

OPEN valve labeled " ISOLATION VALVE 20.

R/h Time 11/21 PRESSURIZER SAMPLE COLLECTION BY-PASS" only two 360 turns.

, OPEN drag valve labeled " PRESSURIZER 2f.

R/h Time LIQUID HOT LEG."

SHUT the RCS sample hood to t'.e !wel 2g. R/h Time of the top of the sample collection

.,l apparatus.

NOTE -

EXTRBAELY HICH DOSE RATES (1000 R/h) MAY RESULT IN THE HOOD VICINITY FROM REACTOR COOLANT FLOW THROUGH THE SAMPLE COLLECTION APPARATUS WHEN VALVE HS-5467 (CV-5467)

IS OPENED.

{

l

o

~,--,+~,-a--~~~~~R'

-~-

ERPIP NO.: 4.4.7.3 / REV. 9 N

ERMT Member LRMT Member i~.

i I

CPEN key operated valve MS-5467 (CV-54s.7 2h.

R/h Time located on the S/G sample conditioning panei and immediatelv leave the area.

3.

Ensure SRD readings, ex-posure rates are observed and stay times are not exceeded.

-nors-l 00 NOT REP.LNTER THE SAMPLE HCOD AREA UNTIL IT IS NECESSARY l

4.

Return with the LRMT member Allow the sample to recirculate for 30 i

to ingress area of the Con-minutes. Follow ERMT member to low back-trolled Area 69' Elevation ground area during recirculation period l

Aux. Bldg. or other low l

background area designated previously by RPD.

1 5.

While waiting to reenter sampling t

l room per step 6, review steps 7 thru 11 with LRMT member.

l

(.

at Reactor Coolant Sampling Room h

Reenter Controlled Area to arrive at end of 30 minutes recirculation t

f I

time.

R/h Time

]

-verz-

..J l

AVOID EXPOSURE IN UNSHIELDED AREA.

POSSIBLE EXPOSURE RATES OF 1000 R/h (250 mR/s) l 7.

Remain behind shield while LRMT Reenter Sampling Room, SHUT key operated member performs steps 7 thru 9 valve HS-5467 on "S/G Sample Conditioning and commence constant monitor-Panel" to isolate the sample.

h of LRMT memoers anc your own exposure rates and exposure times.

l R/h Time I

I l

l 6

.s~)

l I

l s

ERPIP NO. 4.4.7.3 / REV. 9 ERMT Member LRMT Member O

Enter behind lead shield in R/C

'8.

R/h behind shield, Time Sample Area and observe the sink area by use of instaHed mirror.

s Quickly approach Reactor Coolant 9.

R/h at LRMT Location, Time Sampi::. sink, disconnect the quick release fittings on the sample col-lection apparatus, tilt the apparatus down into the hood sink to drain any remaining 11guid from fittings and return behind shield wall.

10.

Place the sample collection apparatus into lead container. Close container lid.

11. Promptly exit sample room with Depart with ERMT member, taking sample LRMT member and sample cart, and cart and shielded sample.

Radiac Instrumentation. Return to 69' Elevation Controlled Area

/

RPD notified Time Time exited Time o

V - ?.

Provide continuous monitoring Contact Control Room and request V

coverage during the transport that the Reactor Coolant Sample of shield sample to the radio.-

Isolation Valve be SHUT.

chemistry laboratory and min-Imize radiation exposures by Deposit sample in Chemistry Hot effective use of barriers Laboratory or as directed by RPD and minimum stay time, for analysis.'

13. Ensure personnel exposure Prepare sample tag with the following data has been recorded.

data, and tie to sample cc,llection apparatus container.

i a.

Name and type of material

( )

b.

Time sample taken

( )

c.

Sample #,if applicable

( )

d.

Location of sample

( )

e.

mR/h on contact after sample containment

( )

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o

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- - - - - - -. - - ~ ~ -

,e ERPIP NO.: 4.4.7.3,/ REY. 9 *

's LRMT Memcer ERMT Memcer e.

Leave Attachment I with RCS sample

-24.

for use in analysis.

3.3 REPORTING 3.3.1 Report promptly and ver-bally preliminary data ob-tained during entry to the CD and RPD. Brief CD l

and RPD on the following as

)

a minimum.

3.3.1.1 Exposures received by reentiy persennel (SRD-type data) 3.3.1.2 Expa;ure rates i

menstred enroute to sample room &

maximum exposure rates raeasured within sample room during entry.

3.3.1.3

' Dese rate contact with l

1 the Sample.

- c...r.~

s 3.3.2 Collect lapel air samples & -

send to counting laboratory

_ for analysis.

Report to CD fer full de-j 3.3.3 briefing & provide copy of x;'

s

l completed data shown on Attachment I.

l m,

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ERPIP NO. 4.4.7.3 / REV. 9 ATTACHMENT I ACCIDENT SAMPLE AND ANALYSIS DATA SHEET SAMPLE #

SAMPLE LOCATION:

UNIT 1

2 SAMPLE:

DATE:

TIME:

DOSE RATE CN CONTACT:

mrem /hr REMARKS:

SAMPLED BY:

LMRT ANALYSIS TO BE PERFORMED RESULTS

(

) Cross Beta / Gamma

(

) Gamma Spectrum Analysis

-(

) Boron Analysis

(

) Chloride Analysis

( ) Other (Specify) zJ ANALYSIS PERFORMED BY:

/

LRMT DATE TIME NOTES:

(1) Report results to CD as soon as practical (2) Retain all samples for future use.

(

Storage Location Placed in storage area by:

/

l Date Time REMARKS:

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ERPIP 4.4.7.3 RE7IIW/ APPROVAL EEVISION CHANGE REVIEWER SIG/
SUPERVISOR POSRC PLANT-SUPERINTENDENT DATE.C EPU SIC /DATE MTG
/DATE j
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Pag 2' I of 1 Rsv.
'9 CALVERT CLIFFS' NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN IMPLEMENTATION PROCEDURES n
J LIST OF EFFECTIVE PAGES_
ERPIP PAGE REV.
ERPIP PAGE REV.
1.
9 l
2 9'
3 9
4 9~
5 9
6 9
4 7
9 S
9 9
9 10 9
11 9
u 9
13 9
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ERPIP 4.4.7.4 / REV. 9 TITLE: POST ACCIDENT REACTOR COOLANT ANALYSIS 1.0 RESPONSIBLE INDIVIDUALS AND OB3ECTIVES The Chemistry Director (CD)is responsible for determining the need for perferming any post-accident reactor coolant analysis.
The Liquid Release Monitoring Team (LRMT) member is responsible to the CD for assuring that very high level reactor coolant samples are properly analyzed for radiological spectrum and for boren and chloride when directed by the CD.
l The LRMT member is responsible for utilizing the proper chemistry / radio-chemistry equipment, protective clothing and equipment as directed by the Emergency Work Permit..
l Onsite Monitoring Team member is responsible to the RPD for providing continuous radiation protection coverage during the performance of all post-accident reactor coolant samples.
-NOTE-This procedure is only applicable if the Post Accident Sampling System is not OPERABLE. If the PASS is in service, use ERPIP 4.4.7.6.
'.]
2.0 CONDITIONS AND PREREQUISITES 2.1 In-line failed-fuel detector (Process Radiaiten Monitor - R202) (CVCS Control Board IC07 or 2C07) of affected unit under accident conditions gives an indication of an increased level of Iodine-135 in the reactor coolant system as follows:
RI-202-1 Gross Rate Meter-Alarm lxi cpm Alert lx10 cpm RI-202-2 Linear Rate Meter (Failed Fuel Monitor)
(Analysis for I-135)
High Alarm - 70% Fuel Scale (Amber Light)
J High High Alarm - 90% Fuel Scale (Red Light) j or, when this monitor is inoperative, under accident conditions.
2.2 When directed by CD.
j l
2.3 RCS samples analyzed pursuant to this procedure are to be repeated on a
'{
routine basis every hour as necessary, to determine activity levels and trends.
6 2.4 Very high level radioactive samples are so designated, if exposure rate level is greater than 2.0 R/h on contact.
(OBSERVE NOTE ON FOLLOWING PAGE)
I t
i s
ERPl? 4.4.7I/ REV. 9
- NOTE -
Lead lined gloves, lead apron, finger rings, lapel i
samples, plastic hoods, SCSA and High Range gamma exposure ra:e meter and pocket dosimeter shall be utilized :o perform the RCS analysis.
2.5 Analyzing a coolant sample shall be planned to be performed promptly under accident conditions within the following periods from the time a decision is made to take a sample:
2.5.1 Radiological spectrum analysis in less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; 2.5.2 Soren analysis in less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; 2.5.3 Dissolved gases in less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , (measurement of either :otal dissolved gases or H2 gas !s ;decuate); and l
2.5.4 Combined time of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or less for sampling and analysis for steps 2.5.1, 2.5.2, and 2.5.3 above.
2.5.5 Chloride analysis 2.5.5.1 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of sample being taken,(a)if plant coolan:
l water is baywater er brackish wa:er, and (b) if there is only l
a single barrier between primary containment system and
[]
the cooling water.
2.5.5.2 For all other cases, analysis to be completed within 4 days.
2.5.5.3 The chloride analysis does not have :o be done onsite.
l l
2.6 All analysis on very high activi:y samples are to be performed under the exhaus: hood.
2.7 Analyr.ing a reactor coolan: sample shall be olanned to be performed withou:
mcurrmg a radiation exposure :o individual (s)in excess of 3 and 13.75 rem (10 CFR 20) to the whole body or extremities, respec.ively. Excesures shat! no:
exceed 5 rem and 75 rem (Appendix A,10 CFR 50) :o the wnele bocy or extremities, respec ively.
t i
3.0 ACTIONS AND LIMITATIONS i
t 3.1 Based on anticipated radiation exposure levels, the RPD shall soecifv:
I 3.1.1 The use of Emergency Work Permit for pos -acciden:
j sampling of reac or analysis.
3.1.2 Authorized personnel exoosure !imi:s for each analysis.
3.1.3 Labeling of samples and ca:a to oe recorded.
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ERP'P 4.4.7.4 / REV. 9 3.1.4 Specific data to be obtained (form of results). 3.1.5 Persons to whom results must be communicated in addition to the Chemistry Director and Radiation Protection Director. 3.2 Licuid Release Monitoring Team shall carry out very high level reactor coolant analysis as follows and document on Attachment I, " Accident Coolant l Sample and Analysis Data Sheet". 3.2.1 Upon direction by the CD, perform the analysis by priority in steps l 3.3 througn 3.6. -NOTE-STANDARD LA3 ORATORY ANALYSIS PROCEDURES MAY 3E INADEQUATE FOR PROCESSING SAMPLES SU3SEQUE:"I TO GROSS CLADING FAILURE AS LtRGE QUQNTITIES OF NOBLE GASSES OR 01EER VOLATILES AND FISSION PRODUCTS !"AY 3E ? RESENT IN THE SAMPLE MEDIA IN LARGE (mC1/s.l.) CONCENTRATIONS. 3.2.2 Utilize procedures for analysis unless directed otherwise by the CD. l 3.2.3 Follow special handling precautions and disposal techniques as directed by the Onsite Monitoring Team Member. o 3.2.4 Deliver the completed Attachment I with any verbal reports deemed necessary or requested to the individual designated by the Chemistry Director and Radiation Protection Director. 3.2.5 If the local facilities become contaminated or otherwise unusable: 3.2.5.1 Contact the RPD and request notification of the Mobile Laboratory No. I or the offsite labs listed in Section 1.0 and/or a contracted radioactive material shipper, to assist in analysis and snipping. - NOTE - Inform the CD of required schedule for resuits. 3.2.5.2 Containerize the sample in accordance with RCP 3-506 for shipping radioactive samples. i 3.2.5.3 Ship sample and required sample information, shipping documents and required results to the selected offsite lab. 3.3 Raciological Soec rum Analvsis Q
3..".1 Preparation for Analysis 3
l 4 l tws f
ERPl? 4.4.7.4 / REY. 9 3.3.1.1 Read and sign EWP on " Pes:-Accident Reac cr Ccclan: k Analysis". 4 1. Den protec-ive clothing and respira:ory protectien equipment delineated in EWP and this precedure. 2. ONMT member available in labora: cry to provide continuous radiation protec.icn coverage during me performance of analysis on post-accident reac:ce coolant samples. 3.3.1.2 Required equipment 1. Post-accident Reac:x Coolant apparatus (PASCA). (See A::achment II.) 2. Post-accident Sampling apparatus (PASA). (See A::achment m.) 3. 20 mL scintillation vial 4. Gamma Spec cmeter System. 5. Exposure rate measuring system (PIC-6A or RO-1,2,4A, or JA as appropriate). y i 3.3.1.3 Operation of PASCA/PASA (See A :achment E). 1. Install equipmen: and perform belew ac-icns within exhaust hood. Ensure exhaus: fan is en and opera:ing. j 2. Connect the PASCA to de PASA. Ensure da: all .i valves on the PASCA and PASA are SHUT. 3. Connec. the vent rig to de PASCA. 4. OPEN bot:cm valve on PASCA. i 5. OPEN :op valve en PASCA. i -No I-1 HIGH AIRSORNE ACTIVITY MAY OCCUR AT THIS ?O!NT AND EXPOSURE RATES UP TO 1000 mR/h MAY SE PRESENT. j' 6. Place a 20 mL scintillation vial under de burene. i 7. OPEN 2ree-way valve en te ?ASA and allow a se: volume to enter 2e burene as de: ermined previously l by ce CD based on = '"~--'-n of excesure.a e of me .s sampie. q,) Volume: nl. 1 a \\ _m -.3 -y y-- ~~i~~- ^~'~# -f v '7
_...__m._. i ERPIP 4.4.7.4 / REV. 9 8. Drain the specific volume into the vial. O 9. SHUT three-way valve on PASA after the sample has drained into the vial
10. Dilute the vial, if necessary, to 10 mL with demineralized water and cap the vial 3.3.2 Analysis 1.
Place the scintillation vial in a low background area and obtain a dose rate reading at exactly one foot. 2. Report the dose rate reading and the dilution performed to the CD and RPD immediately. 3. Since the gamma ray specometer cannot effdvely count sources with dose rates greater than 30 mR/h (en contact), dilute the sample with demineralized water in a hood to achieve this level 4. Count and analyze the sample in the remote counting geometry (approximately 15 inches off the detector) on the gamma ray spectrometer as per RCP-2-102 or RCP-2-103, 5. For the Nuclear Data System, user #30 will be assigned for emergency plan purpose and on the Tracer Northen System, sequence file #40 will be assigned. 6. These systems will analyze the sample for total dissolved noble gases and for ligild analyses. 3.3.3 Reporting 1. Report results promptly to the CD and RPD and forward a copy of Attachment I to the RPD and CD. 3.4 Boron Anaivsis 3.4.1 Preparation for Analysis 3.4.1.1 Read and sign EWP on " Post-Accident Reactor Coolant Analysis" 1. Don protective clothing and respiratory protection i j equipment delineated on EWP. I i 2. ONMT member available in laboratory to provide continuous radiation protdon coverage during the performance of Boron analysis on post-accident coolant reactor coolant samples. O 3 \\ m-- -e ' ~ ~ ~ -" r=*. 7"**-' " ' ~ ~ '" s
o ER?l? a.4.7I/ REV. 9 3.a,1.2 Required Equipment 1. Pes:-Accident Reac cr C olan: Sample Collection Apparatus (PASCA) Anachment II. 2. Fest-Acciden: Sampling Appara:us (PASA) Anachment III. 3. pH Meter 4. Magnetic stirring apparatus. 5. Burene (5 mL micro with aut:matic fill). 6. 10; mL Beaker 7. Lead bricks (2" x 4" x 3") - 8. Reagents a. Mannitol, ACS Reagen: Grade b. Standard Sodium Hydroxide Solution (dissolve 2g of NaOH (ACS Reagen: Crade)in demineralized wa er and dilute to 1 L.) c. Hydrochleric Acid Solu icn (add I mL of c:ncentra:ed hcl to 999 mL of demineralized water.) r$ 3.4.1.3 Operatien of PACSA/?ASA (Anachmen: III). 1. Connect the PASCA to the PASCA-Ensure that all valves on PASCA and PASA are SHUT. 2. Connect the ven: rig to 2e PASCA. 3. OPEN 2e bottem valve en the PASCA. 4 OPEN de top valve en de PASCA. 1 -NCTE-t HIGH AIRSORNE ACTIVITY MAY OCCUR AT T*-il5 ?CINT AND EXPOSURE RATES UP TO LCCO mR/h MAY SE PRESENT. 5. OPEN 2ree-way valve en PASA and a!!aw I mL :o en:er .i burene. 6. Place a 100 mL beaker, which con ains a -.agr.e:i: s:1--ing bar, under de burene anc drain ne i mL in: ne :eaxer. 7. SHUT ce cree-way valve en ce PASA ='--- - - sample (d ^ has drained into ce beaker. 6 I x - 7_- '"**'?.*T""' __s _-g I ww,
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ERPIP 4.4.7.4 / REV. 9 8. Remove the beaker to the boron stand behind the lead O bricks located within the hooe. 3.4.2 Analysis -NOTE-THE ADDITION OF MANITOL TO THE COOLANT SAMPLE WILL LIBERATE RADIOACTIVE IODINE LNTO THE AIR, PROPER PRECAUTIONS SHALL BE OBSERVED. SCBA MUST BE WORN PRIOR TO ADDITION OF MANITOL. 1. Dilute the sample with 25 mL of demineralized water. 2. Stir sample continuously throughout the analysis. 3. Add I scoop (+ 2g) of mannitol to the sample such that some undissolved mannitol remains in the beaker while the solution is stirring. Insert the pH probes into the breaker and.itrated with NaOH to a pH of 8.0. 5. Continue the titration until a pH of exactly 3.5 is obtained. 6. Record the quantity of NaOH required for the titra, tion as mL NaOH (B). 7. Determine the ppm boron using the following equation: ppm B = mL NaOH(B) N KAP 54.055 mL NaOH OW) mL of sample - NOTE - This assumes that the KAP has already been determined for the day. In the event this must be determined refer to RCP-1-903. 3.4.3 Reporting l 1. Report results promptly to RPD and forward a copy of Attachment I to the RPD. { 3.5 Chloride Analysis I i i 3.5.1 Preparation for analysis. e,'% j 7 \\ l --,7 u. **8"3
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I . =. ERPIP 4.2.7.4 / R$V. 9 m l 3.3.1.1 Read and sign EWP on " Post-Accident Reactor C0 clan: "f i Analysis." 1. Ocn protec-dve clothing and respira:Ory protec.icn i equipment delineated in ETF 1 2. ONMT member available in laboratory to provide continuous radiation protec.icn coverage during the performance of chieride analysis en post-accident react:r coolant samcles. l 3.5.1.2 Required equipmen: 1. Post-Accident Reac:ce Coolant Collec.icn Appara:us (PASCA) A::achment II. l 2. Pcst-Accident Sameling Accara us (PASA) (See A::achmen: III). { 3. Two (2) 40 mm cells l l 4 Kle: -Summersen Photeelectric Colerimeter l 5. Filter, //42 l l 6. Reagents g a. Ferric Alum Solutien b. Mercuric Thiccyanate 3.5.1.3 Opera:icn of PASCA/PASA. See Anachmen:III. ll 1 1. Connec: the PASCA to the PASA. Ensure that all valves i en PASCA are SHUT. i j 2. Connec: the ven: rig o :he PASCA. 3. OPEN the bo:: m valve en the PASCA. 4 OPEN the : p valve en :he PASCA. s -NOTI-HIGH AIRSORNE ACTIVITY MAY OCCUR AT THIS POINT. l EXPOSURE RATES UP TO 5000 meem/h MAY SE PRESENT. 5. OPEN three-way valve on -he ?ASA and allow 5 mL :: ente-the burene. l 3 g 35 h 4"-e I
o ERPIP 4.4.7.4 / REV. 9 { 6. Place a 40 mm cell which contains 45 mL of demineralized water,10 mL of ferric alum solution, and 5 mL of mercuric thiocyanote solution under the burette and drain the 5 mL reactor coolant into the cell. 7. SHUT the three-way valve on the PASA after the sample has drained into the cell. 8. Place the cell behind the lead bricks to minimize exposure. 3.5.2 Analysis 1. Prepare a reagent blank for the chloride analysis using 50 mL cf demineralized water,10 ml of ferric alum solutitn, and 5 mL of mercuric thiocyanote solution. Mix and let stand for 10 minutes. 2. Zero the Klett-Summerson Colorimeter by using demineralized water. 3. Measure the intensity of the color of the reagent blank with a
42 filter. Record this as Reagent Blank Reading.
4. Measure the intensity of the color of the sample with a #42 filter after it has been allowed to stand for ten minutes. Record this as the Sample Reading. -) 5. Determine the chloride reading from the " working" curve using the following equation: Klett Reading = Sample Reading - Reagent Blank Reading 3.5.3 Reporting 1. Report results promptly to CD and RPD and forward Attachment I to the CD and RPD. l i l i Y l 3J I 9 ~ --- --- -n-m- - - ~s r - -- v -. 3 4-
i ERPIP 4.4.7.4 / REY. 9 O ^T'^c""5N7 ' ACCIDENT SAMPLE AND ANALYSIS DATA SHEET SAMPLE # SAMPLE LOCATION: UNIT 1 2 SAMPLE: DATE: TIME: DOSE RATE ON CONTACT: mrem /hr REMARKS: SAMPLED BY: LMRT ANALYSIS TO BE PERFORMED RESULTS ( ) Gross Beta / Gamma ( ) Camma Spectrum Analysis ( ) Boron Analysis ( ) Chloride Analysis ( ) Other (Spe<J-fy) 4 ANALYSIS PERFORMED BY: / / LRMT DATE EME NOTES: (1) Report results to CD as soon as practical (2) Retain all samples for future use. Storage Location Placed in storage area by. / Date L REMARKS: i I mO s 4 l 10 i f s _ _..., _,_ _. _ a.--_ .. _ c,
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ERFI? 4.4.7.4 Rev. 9 i s AITACEMENT III This Attachment will be issued at a later date. rm. 3 G' O t 4 i 6 t f i 1 -4 l.' I 4 4 .T.n. \\ m ) . w o m wwm - _ _ mo m_ww- ...go.-e , m..y,..,,s, ._n,_. .,y,
\\ 5 .O l ERPIP 4.4.7.4 REVIEW / APPROVAL ! REVISION CHANGE REVIEWE3 SIG/ SUPERVISOR POSRC PLANT SUPERINTENDENT .,D ATE '._ EPU SIG/DATE MTG /DATE ej .a ~ / / / t t 1 )> S e I 1 -_M C \\ g

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.._. ~ -... _ nPI?'4.4.,7./.'.- Page 1 of 1, Rev. 9 CALVERT CLIFFS NUCLEAR POWER PLANT ^ EMERGENCY RESPONSE PLAN IMPLEMENTATION PROCEDURES LIST OF EFFECTIVE PAGES_ ERPIP PAGE REY. ERPIP PAGE REV. 1 9 2 9 3 .9 4 9 5 9 i 6 9 7 9 i 8 9 9 9 10 9 11 9 12 9 i . - ~.. _ -.. t i 1 i ,-m \\' s N --~mpa -m m.- mw;-~--- ~.
E R PIP N O.: 4.4.7.3 / REY.1 ' TLE: POST-ACCIDENT HYDROGEN ANALYSIS TI i ~O t.0 asseossiete tNDiviDuAt The Chemistry Director (CD) is responsible for determining the need for performing post-accident hydrogen analysis. Members of the Liquid Release Monitoring Team are re;ponsible to the CD for measuring hydrogen in various systems using the Post-Accident Hydrogen Analyzer - System (PAHAS). The Liquid Release Monitoring Team Leader is responsible for utilizing the proper sample equipment, protective clothing, etc., and collection methods for obtaining and handling very high level samples, as directed by the CD. l i The Emergency Reentry Monitoring Team member is responsible to the Radiation Protection Director (RPD) for ensuring exposure controlIn accordance with the Emergency Work Permit as specified in this procedure. V f 2.0 CONDITIONS AND PREREO' ISTTES U 2.1 In-line failed-fuel detector (Process Radiation Monitor - R202) (CVCS Control Board IC07 or 2C07) of affected unit under accident conditions gives an i indication of an increased level of Iodine-135 in the reactor coolant system as 5 l RI-202-1 Gross Rate Meter-Alert IX10 cpm RI-202 2 Linear Rate Meter (Falled Fuel Monitor) (Analysis for I-135) High Alarm - 70% Fuel Scale (Amber Light), and High High Alarm - 90% Fuel Scale (Red Light), or when this monitor is inoperative, under accident conditions. O 1 1 t ~ Y Y ? "' ~M l e-v =
t w ear o v.s v.w.i.a i u v. s 2.2 When directed by CD. ^. 2.3 Hydrogen analysis samples taken pursuant to this procedure are to be repeated -^ on a routine basis as necessary, to determine trends. 1 2.4 While utilizing the Post-Accident Hydrogen Analyzer, the Hydrogen Analysis shall be planned to be performed promptly ( one hour) under accident conditions without incurring a radiation exposure to individual (s) In excess of 3 and 13.75 rem (ICCFR20) to the whole body or extremities, respectively. Exposures shall not exceed 5 rem and 75 rem (Appendix A,10CFR50) to the whole body or extremities, respectively. 3.0 ACTIONS AND UMITATIONS I '/ / RPD Name Date Time ERPIP INITIATED 3.1 Based on anticipated radiation exposure levels or gross area monitor readings OtMS), the RPD shall soecifv: C 3.u The use of Emer3ener or* Permit. EwP #003, ror post-accieent (D w
sampling, 3.1.2 Entries made'for Hydrogen Analysis are to be made In accordance with ERPIP 4.3.1.
3.1.3 Alternate routes If necessary. j 3.1.4 Designated doors to open and shut during access and egress, existing radiation barriers, and maximum stay times. l 3.1.5 Authorized personnel radiation exposure limits for each entry on EWP l
003.
i ll 3.2 The ERMT member and LRMT member shall icintly carry out monitoring and hydrogen analysis ac*dvities. I I ~) 2 { j s m-- y.--, n-.-
ERPIP NO.: 4.4.7.5 / REY.1 O-ERMT Memeer LRMT Member 3.2.1 Upon direction by the RPD, prepare for reentry according to Emergency Work permit. EWP
003, as follows:
3.2.1.1 Receive briefing by RPD, per items 3.1.1 thru 3.1.3 above. 3.2.1.2 Read, understand, and sign EWP #003 and receive briefing by the ERMTL as to stay time limitation, protective clothing, specific route to work locations, and radiological conditions expected. Briefing Conducted: / LRMT Initial Date 3.2.1.3 Collect the following material Collect the following materiais from the from the Emergency Reentry Radiochemistry Laboratory: (check when Equip. Locker: (check when performed) performed) 1. Radiac Monitoring Equip-
1. Key for the PAHAS #73
( ) ment per EWP #003 ( ) 2. Maps, stop watch, portable radio, air sampler and dosimeter. ( ) g /- f/ ERMT Name Time LRMT Name Time 3.2.1.4 Prepare map showing route and expected radiological con-ditions - attach to EWP #003 4 3.2.1.5 Don protecti,e clothing, dosimetry and respiratory protection devices, tapel air samples as specified on EWP #003. (Clothing and monitoring equipment located in the Emergency i Reentry Equipment Locker, 69' Aux. Building for preaugmentation use), i 3.2.1.6 When approved by the RFD, proceed to the Post-Accident Hydrogen Analyzer System access { area on the 45' elevation of the Aux. Building west side. 3.2.1.7 Supervise and provide con-Follow directions of ERMT member to I tinuous radiation protection ensure your exposure is treintained ALARA. l coverage for LRMT member, control stay times and use portable radio to notify RPD l of procedure steps performed and exposures rates detected. } ' O 3 I 0 w
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- CAUBON - m FAILURE TO USE THE PEM!ANCIT SHIILDUIG PLACZD Di TEE PAHAS, TO TEE FULLIST ^
u uiT POSSI3LZ,.MAY RESULT ti UNDUE '4ADIATICN EXPOSURE.
s j 4.0 PROCEDURE 4.1 Aeoartus 4.1.1 The control panels, IC139 and IC140, located on the -7 elevation of the Auxillary Building contains all alarm indications, flow meters, ~ calibration gases, and flow controls. 4.1.2 The control panels, IC101 and IC102, located on the 47 elevation of the Auxillary Building contains all of the valve controls and the i l sample sequences necessary to analyze a sample. 4.2 Method 4.2.1 Proceed to the control panel IC101 and IC102 located on the 47 l elevation of the Auxillary building. 4.2.2 Verify that the power Is "ON" and the Control Modual Is In the l " STANDBY' mode on both IC101 and IC102. C D ~ 1 - NOTE - If the analyzer Is not In " STANDBY" or analyze, then It will be ne'cessary to wait six (6) hours to allow the heater blocks to be at the correct temperature. l 1 l1 l l%\\ l a \\ - ~ .,,.. y - w - - v..... ~~~-~--r,- \\
ERPIP NO.s 4.4.7.5 / REY.1 - NOTE - If the panel is in an alarm condition, press the reset button. If it does not reset, reser establish control to the panel by depressing the remote selector button and then push the reset button. If necessary, repeat at least three (3) times. If it still does not reset, notify the RPD and CD that entry into the -5 elevation will be required to determine the cause of the alarm. 4.2.3 Check the response of the hydrogen monitor by the following steps (Record all response data on Attachment 1): 4.2.3.1 On the H S 2 equencer Panels place the purge selector switch to "ON". 4.2.3.2 Using the key #73 open the discharge plant vent valves O-SV-6313 and 0-SV-6522 on control panels IC101 and IC102, respectively. nJ 4.2.3.3 On the H Control Moduals 2 (a) Verify H dual range switch is at 0-10% range 2 (b), Set function selector switch to,zero (c) Adjust control switch-from " STANDBY" to " ANALYZE" i i - NOTE - At this time the IIght indicators for the sequencer and the H 2 Control Module should light. If the function selector switch and indicator do not agree, press the REMOTE SELECTOR to gain control. Also press the reset alarm button to clear any alarms. i l i b Q. I s l 1
E R P IP N o.: 4.4.7.5 / REV.1 l 4.2.3.4 Egress from the area and allow the instrument to stabilize l for 10 minutes minimum. 7 ^ 4.2.3.5 Return to the control panels and record the hydrogen meter values. 4.2.3.6 Adjust the function selector for "ZERC" to " SPAN". NOTE - The high Hydrogen alarm will alarm at 4% After span check is complete, set function selector to zero, reseat alarm and continue with the procedure. ~ 4.2.3.7 Egress from the area and allow the instrument to stabilize for 10 minutes minimum. 4.2.33 Return to the control panels and record the hydrogen meter valves. - NOTE The zero and span should have read 0 and 1 10%, respectively f,1% If the values p~ observed were outside the tolerance, the (9 ~ Instruments should be considered as being out of calibration. If this condition exists, report to the RPD the data recorded. 4.2.4 On the H2 Control Module adjust the function selector. to " STANDBY". 4.2.5 Cn the H sequencers adjust the purge selector to "OFF". 2 4.2.6- " SHUT" the main vent key operated discharge valves C-SV-4513 and 0-SV-6322. l 4.2.7 Unit #1 Containment Samole Valve I.ine-Uo (See attachment #2). 4.17.1 Unless otherwise directed, "CPEN" all the key operated in board and out board valves listed below. l l
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'( 3 G ERPIP NO.: 4.4.7.5 / REV.1 PANEL IC101 Containment #1 S. Primary Shield 6507 B/6540 B s Containment #1 Pressurize Compartment 6507 C/6540 C Containment #1 E. [35" EL. 6507 D/6540 D Containment 61 H Sample Return 6507 G/6540 G 2 PANEL ICIO2 Containment #! N. Primary Sheild 6507 A/6540 A Containment #1 W.137 EL. 6507 E/6540 E Containment #1 DOME 189" EL. 6507 F/6540 F 4.2.7.2 Position the Sequencer Sample points listed below in the " AUTO-ON" position. PANEL IC10,1, Sample #5 U-1 Conttinment E.137 EL. Sample #6 U-1 Containment Pressurizer Sample #7 U-1 Containment S. Primary Sheild Q ~# PANEL IC102 Sample #5 U-1 Corftainment N. Primary Shield Sample #6 U-1 Containment W.137 dL. Sample #7 U-1 Containment DOME 189' EL. 4.2.8 Unit #2 Containment Samole Valve Line-UP (See attachment # 3). 4.2.8.1 Unless otherwise directed, "OPEN" all the key coerated in j board and out board valves listed below. PANEL IC101 Containment #2 North Primary Shield 6507 A/6540 A Containment #2 W.137 EL. 6507 E/6540 E Containmnet #2 DOME 189' Ef.. 6507 F/6540 F i '7 el m _w r--e-. -sep+-*w-***-*' m*
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l. ~ ERPIP NO.: 4.4.7.5 / REY.1 PANEL IC102 Containmnet #2 S. Primary Shield' 6507 B/6540 B 6507 C/6540 B Containment #2 Pressurizer Compartment Containment #2 E.135' EL. 6507 D/6540 D Containmnet #2 H Sample Return 6507 G/6540 G 2 4.2.3.2 Position the sequencer sample points listed below in the " AUTO-CN" position. PANEL IC101 Sample #8 U-2 Containment DOME 159' EL. Sample #9 U-2 Containment 7.135' EL. l Sample #10 U-2 Containment N. Primary Shield PANEL IC102 Sample #8 U-2 Containmnet S. Primary Shield Sample #9 U-2 Containment Pressurizer Sample #10 U-2 Containment E.135' EL. O e 4.2.9 On the H2 Control Modules adjust the control from " STANDBY" t " ANALYZE". Control Module (s) adjust the function selector to " SAMPLE" and 4.2.10 Cn the H2 egress the area as soon as possible. t - NOTE - i If necessary, clear the communication alarri i Indication before leaving the area by pressing I the alarm-reset button. The sequencer will ~ not function if the purge selection is in the "ON" position. A nu .p= .m_ ,7..
ERPIP NO.s 4.4.7.5 / REV.1 - NOTE - If the selector is placed in Auto-On, then the h sequencer will purge and sample for fifteen (15) minutes and proceed to the next point. If the selector is placed in manual, then the l sequencer will hold on that point when the l seque..cer advances to that point. The Control room recorders will provide the data printout of the H analyzer results. 2 - CAUTION - Operation of the containment gas pump greater than 200 hours say necessitate i pump maintenance. 4.2.11 When the CD no longer requires hydrogen analysis place the unit in l " STANDBY" mode. Record all steps on Attachment 1. (a) Switch the functional selector switch on the H Control 2 Module back to " STANDBY". (b) Close all key operated gas sample valves. 3 (c) Turn all switches on the sequencer to "OFF". 4.2.12 Close the cc ent or plant vent discharge line. Egress the area as soon as practical. 1 5.0 ' REPORTING 5.1 Report promptly and verbally preliminary data obtained during entry to the RPD. Brief RPD on the following as a minimum. 5.1.1 Exposures received by reentry personnel (SRD-type data) 5.1.2 Exposure rates measured enroute to sample room & maximum { exposure rates measured within sample room during entry. { 5.1.3 Initial H measurements. 2 5.2 Collect lapel air samples & send to counting laboratory for analysis. 5.3 Report to RPD and CD for full debriefing and provide espy of completed data l shown on Attachment 1. 5.4 If the control room recorders are not functioning manual data collection may be requested. Manual data should be recorded on attachment #4. h-O 9 i i x '~. _ - - ~ ~~. em e m --m.-e.w w e p.-- - -. . v n-r-ver- ~ ~ -
ERPIP NO. 4.4.7.5 / REV.1 ATTACHMENT 1 O^I. Hydrogen Monitor Resoonse Check INITIALS / TIME j 1. Purge Selecter Placed "ON" / 2. Open Valve 0-SV-6313 and 0-SV-6322 / 3. Place Hydrogen Analyzer Selector to 0-10% range: IC101 1C102 Zero Value as found / Span Value as found / II. Placing the Hydrogen Analyzer in STANDBY Mode after Samoling. ~ .1 1. Switch Functional Selector Switch / to STANDBY 2. Close all key operated valves / 3. Close the Containment or / Plant Vent Discharge Lines Comments: , q_ 9 e l i PERFORMED BY / Signature Date i 10 -.-----v-w--+ em in'*.--'.-*' .,g._
ERPIP NO. 4.4.7.5 / REV.1 ATTACHMENT 2 O; UNIT #1 o VALVE LINE UP CHECX LIST l Key Coerated Valves l SAMPLE POINT INBOARD OUTBOARD i CNTMT # SOUTH PRIMARY SHIELD 6507B 6540B IC101 CNTMT # PRESSURIZER 6507C 6540C CNTMT # 135' ELEVATION 6507D 65400 1 1 i CNTMT # NORTH PRIMARY SHIELD 6507A 6540A 1 l IC102 CNTMT # WEST 135' ELEVATION 6507E 6540E CNTMT # DOME 189' ELEVATION 6507F 6540F Sequecer Line-Ups (Auto-ON) Samples 5 Samples 6 on IC101 AND IC102 f Samples 7 s. f Initials Time /Date i .s t 8 l 0- .n i i l i l i s I .7;
~ ~ ERPIP NO. 4.4.7.5 / REV.1 ATTACHMENT 3 UNIT #2 O-VALVE LINE UP CHECK LIST Key Ooerated Valves SAMPLE FCINT INBOARD OUD50ARD CNTMT # SOUTH PRIMARY SHIELD 6507B 65408 - IC101 CNTMT # PRESSURIZER 6507C 6540C CNTMT # 135' ELEVATION 6507D 6540D H SX RETURN 6507G 6540G 2 CNTMT # NORTH PRIMARY SHIELD 6507A 6540A IC102 CNTMT # WEST 135' ELEVATION 6507E 6540E CNTMT # DOME 189' ELEVATION 6507F 6540F Sequecer Line-Ups (Auto-ON) r. Sampies 8 v ~ Samples 9 on IC101 AND IC102 Samples 10 Initials Time /Date s / t C. 12 3 .-.,n ,., ew ~,,n ew- ~ _.. x.,w m.
E R PIP N O.: 4.4.7.5 / REY.1 ATTACHMENT 4 SEQUENCER SAMPLE POINTS POINT # SAMPLE POINT HYDROGEN READING INITIAL / TIME 1 RC Monitor Tank #1. / ~ '2 RC Receiver Tank #12 / 3 RC Monitor Tank #12 / 4 RC Receiver Tank #11 / 5 U-1 CNTMT 135' El / 6 U-1 CNTMT PRZR / 7 U-1 CNTMT South / Primary Shield 8 U-2 CNTMT Dome / 189' El ~ n 9 U-2 CNTMT West / I 10 .U-2 CNTMT North / Primary Shield 4 PERFORMED BY: / Signature Date i l i 1 1 4 i 13 N _.,_ w m m_ m~m q wmv ~ c - - M *w "* v ~***' 4:
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ERPIP 4.,4.7..,5 Pag 2 1 cf 1. Rev. 1 CALVERT CLIFFS NUCLEAR POWER PLNNT EMERGENCY RESPONSE PLAN IMPLEMENTATION PROCEDURES i LIST OF EFFECTIVE PAGES_ ERPIP PAGE REV. ERPIP PAGE REV. i i 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 1 13 1 O N _--- - ~ w w w-m w .p p. . _,,.,. w mp onen._ 1.
~.. _. _. ERPIP 4.4.7.6 Rev.1 TITLE: POST-A'CCIDENT SAMPLING SYSTEM AND ANALYSIS 1.0 RESPONSIBLE INDIVIDUAL The Chemistry Director (CD) is responsible insuring proper plant and site samples are drawn and analyzed to support operational, environmental and material concerns following an accident. Members of the Liquid Release Monitoring Team are responsible to the CD for . obtainmg post-accident sample (s) as directed by the CD. These samples may include very highly radioactive reactor coolant samples. The LRMT is responsible for sampling and analysis via the Post Accident Sampling System (PASS), The Liquid Release Monitoring Team Leader is responsible for utilizing the proper J sample equipment, protective clothing, etc., and collec?lon methods for obtaining and handling very high level samples, as directed by the CD and the Radiation Protection Director (RPD). The Emergency Reentry Monitoring Team member is responsible to the RPD for i l ensuring exposure control in accordance with the Emergency Work Permit as
'I specified in this procedure.
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ERPIP 4.tr.7.6 Rsv.1 ~ h 2.0 CONDITIONS AND PREREOUISITES 2.1 In-line failed-fuel detector (Process Radiation Monitor - R202) (CVCS Control Board IC07 or 2C07) of affected unit under accident conditions gives an indication of an increased level of Iodine-135 in the reactor coolant system as l foJIows: 5 RI-202-1 Gross Rate Meter-Alert IX10 cpm RI-202-2 Linear Rate Meter (Failed Fuel Monitor) (Analysis for I-135) High Alarm - 70% Fuel Scale (Amber Light), and High High Alarm - 90% Fuel Scale (Red Light), or when this monitor is inoperative, under accident conditions. 2.2 RCS samples taken pursuant to this procedure are to be repeated on a routine basis every hour as necessary, to determine activity levels and trends. 2.3 Very high level radioactive samples are so designated, if exposure rate level is greater than 2.0R/h on contact. li 2.4 Obtaining a reactor coolant sample shall be planned to be performed promptly as directed by the Plant Superintendent. i l i <h... j 1 i ' s -- -- - n y 7--m,me-e - 1
..m___.. _._.:.. x.r. 1 ERPIP 4.4.7.6 Rev.1 O 3.0 ACTIONS AND LIMITATIONS O 3.1 The ERMT member and LRMT member shall icintly carry out monitoring and collection of very high, level sample (s) as follows and document on, " Accident Sample and Analysis Data Sheet," as appropriate, upon completion of reentry sampling. i e >n -(... i 1 O 3- _ _ --....- -.- ee-- e m y.e-e- ~
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._= ERPIP 4.4.7.6' Rev.1 pJ ~ ERMT Memoer LRMT Member - y 3.1.1 Upon direction by the RPD, contact the Control Room and request that the Post Accident System Reactor Coolant Sample Isolation Valves be OPENED. (PS-519/PS-320 for Unit I and PS-323/PS-524 for Unit 2). Request the Containment Sainple Return Line Isolation Valves be opened. Control Rm Contacted: / / Initial Date Time 3.1.2 Upon direction by the RPD, preoare for reentry according to Emergency Work Permit, EWP
003, as follows:
3.1.2.1 Receive briefing by RPD, per items 3.1.1 thru 3.1.7 above. 3.1.2.2 Read, understand, and sign EWP #003 and receive briefing by the ERMTL as to stay time limitation, protective clothing, specific route to work locations, and radiological conditions expected. Briefing Conducted: / Initial Date 3.1.2.3-Collect the following material Collect the following materials from the from the Emerge:acy Reentry Radlochemistry Laboratory: (check when Equip. Locker: (check when performed) performed)
1. Radiac Monitoring Equip-

1. Keys for the PASS RCS & H System
( ) 2 ment per EWP #003 ( )
2. Accident Coolant Sampling Kit
( ) l
2. Maps, stop watch, portable

3. Inventory prior to entry
( ) radio, air sampler and
4. Lead gloves
( ) dosimeter. ( )
5. Lead pig for sample
( ) l
6. Transport cart
(~) i ! l ' / / ERMT Name Time LRMT Name Time t i .D Q) l 1 I .. ;my = ~.
ERPIP 4.4.7.6 Rcv.1 ERMT Member LRMT Member 3.1.2.4 Prepare map showing route and expected radiological con-ditiens - attach to EWP #003 3.1.2.5 Don protective clothing, dosimetry and respiratory protection devices, lapel air samples as specified on EWP #003. (Clothing and monitoring equipment located in the Emergency Reentry Equipment Locker, 69' Aux. Building for preaugmentation use). 3.1.2.6 Ensure personnel monitoring equipment and operational radiac instruments are placed on transport cart prior to entry. / Initial Time 3.1.2.7 When approved by the RPD, proceed to the sample location (Post Accidenc Sar:ple System access area on the 45' elevation of the Aux. Building west side.) 3.1.2.8 Supervise and provide con-O tinuous radiation protection coverage for LRMT member, control stay times and use portable radio to notify RPD of procedure steps performed and exposures rates detected. ~ 3.1.2 9 Prior to entry into the Post Accident Sampling area, review section 3.1.2.10, step 1 thru 3 with LRMT member. I -CAUTION-j l PERMANENT LEAD SHIELDING MAS BEEN PLACED IN THE PASS AREA. MAXIMUM EFFORT SHOULD BE MADE BY THE INDIVIDUAL PERFORMING THE SAMPLING TO UTH32F 1NIS SHIELDING TO REDUCE HIS RADIATION EXPOSURE. DO NOT ENTER AREAS BEHIND THE SHIELDS. 3.L2.10 Ensure sampling area has 1. Verifying that the system is energized been prepared as follows: by checking the control panel circuit breakers (CV)1-19 are in the "ON" I position. ! O i I i i j, L -.,__-_m.m,-,.._---,,---m . yn, msc - l
ERPIP 4.4.7.6 Rev.1 ~ ERMT Memoer LRMT Member 1. Transport cart carrying 2. Verify that the valve switch positions open lead container and and manual valves are in " NORMAL" line-up equipment located out-positons and energized per Attachment 2. side of shleid wall and easily accessible for receipt of the very high. level coolant sample. 2. Perform continuous 3. Perform Sample Analysis and obtain l monitoring during all steps samples as per Section 4.0. of the procedure. PIC-6A and RO-7 (0-20 R/h Scale Probe) turned to high scale and placed between the shield wall and the PASS Control Panel 3. Ensue that Lapel Air Samplers are turned on. 4.0 PASS OPERATING PROCEDURES O-NOTE: , Sections 4.1 - 4.3 are operational checks of the sy' stem. 4.1 Nitrogen Purge and F111 of the Gas Samole Vessel 4.1.1 Open CV-5015, CV-5018, and CV-5023 at the PASS control panel. 4.1.2 Open CV-5002 (rotate and push the switch), CV-5026, CV-5010, and position CV-5013 to GAS SAMPLE position. 4.1.3 Open CV-5030, CV-5025, and slowly open CV-5044 (via PS-125 nitrogen regulator supply on the control panel). Verify pressure indication on PI-5025, then continue to open CV-5044 until a i pressure of 5 psig on PI-5025 is obtained. 4.1.4 Turn the Sample Circulation Pump "ON" to purge and establish a nitrogen blanket for this portion of the system. 4.1.5 Verify flow indication on FI-5019, then continue to open CV-5044 until flow rate of 0.6 to 0.3 cfm (as read on FI-5019) is obtained. v ., ~m rn ~, s-
b ERPIP 4.4.7.6 Rev.1 4.1.6 Purge system for 2 to 3 minutes, then open CV-5014, CV-5016, and close CV-5015. 4.1.7 Verify flow as above (4.1.6). 4.1.3 After five minutes of purge flow, switch the sample circulation pump "OFF" and close CV-5044. Position PS-519/PS-520 (for Unit 1) or PS-523/PS-524 (for Unit 2) to BOTH VALVES SHUT position and slowly reopen PI-5044 to obtain 5 to 10 psig on PI-5025. 4.1.9 Close CV-5014 and CV-5015. The Gas Sample Vessel is now charged. 4.1.10 Verify that all valves controlled from the control panel are returned to their normal line-up positions given in Attachment 2. 4.2 Demineralized Water Purge and Fill of the Reactor Coolant Liould Sample Path 4.2.1 Open the liquid return line valves to the containment. Open 1-SV-6529 (for Unit 1) or 2-SV-6329 (for Unit 2) CV-5011, CV-5010, and fully open CV-5012. 4.2.2 Open CV-5005 and slowly open CV-5033. Verify flow indication s ' on FI-50ll. then, continue to open CV-5033 until a flow rate of I gpm on FI-50ll demineralized water flow is established for purging. 4.2.3 After approximately 2 minutes, open CV-5029 and then close CV-3011. Adjust CV-5033 as necessary to maintain 1 gpm (as read on FI-5011) for demineralized water flushing of the pH and boron meters. , NOTE - If radiciostopic analyses are to be conducted, an energy calibration check of the system should be conducted at this time. The 2-minute purge will be extended long enough to conduct the calibration as detailed in RCP 2-105. 4.2.4 After approximately 2 minutes, close CV-5029, CV-5012, and CV-5010. Then close CV-5033. I l t 3
ERPIP 4.4.7I Rcy.1 C - NOTE - g, If levels are observed on LI-5031 or LI-5023, d skip the following sections 4.3 and 4.4, respectively, return all valves to normal line-up (Attachment 2) and proceed to 4.5. i 4 4.2.3 Close the liquid return line to the containment. Close 1-SV-6329 (for Unit 1) or 2-SV-6329 (for Unit 2). - 4.3 Demineralized Water Fill of the Looo Seal and Burette 4.3.1 Vent the Surge Vessel by slowly opening PS-108 (located below funnel at the left rear side of the sample station). j 4.3.2 From the control panel, slowly open CV-5031 to fill the loop seal and the burette to a level of between 0 and 5% as read on U-5031. Then close CV-5031. 1 - NOTE - i If the level as read on LI-5031 is greater than 5%, operate CV-5036 to lower the burette levelinto the acceptable range (0-5%). ~ - NOTE - If no level is observed on LI-5023, (Depressurized Liquid Sample Vessel), proceed to Section 4.4. 4.3.3 Close PS-108. t i I s
I
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j ERPIP 4.4.7.6 Rev.1 ] - NOTE - If a level is observed, then verify that all valves are positioned to their Normal Valve Line-up and proceed to Section 4.5. 4.4 Demineralized Water Fill of the Depressurized Liquid Sample Vessel 4.4.1 Position CV-5028 to SAMPLE FLASK position and slowly open CV-5006 to fill the Depressurized Liquid Sample Vessel to a level of 20% (as read on LI-5023). 4.4.2 Fosition CV-5023 to SAMPLE PATH position and op-n CV-5032 to vent the vessel (LI 5028 will stabilize af ter satisfactory vendng). 4.4.3 On the control panel, close CV-5032 and CV-5006. 4.4.4 Close PS-108 (located below the funnel at the left rear side of the _s
~ ~'
sample station). - NOTE - Return all valves to the normal line-up as given in Attachment 2 before proceeding to Section 4.5. THF. SYSTEM IS NOW READY FOR OPERATION. i 4.5 Reactor Coolant Samole (RCS) Purging i i 4 4.5.1 Ensure that all valves are in there normal line-up as given in Attachment 2. O 9-s y,m -. -.- en. n m y e g_, ___..,qn,.m g-,_..
~ ERPIP 4.4.7.'6-Rcv.1 - - CAUTION (A) - y) If during sampling, PIC-5004 high pressure alarm occurs, verify that CV-5004 cfoses (light on control panel), isolate liquic-sampling inlet lines, check U-5032 level to determine if relief valves PS-127 and/or PS-129 have lifted. Pump down the Surge Vessel if necessary by opening CV-5033, CV-5034 and running the Surge Vessex Pump. Correct the cause of high pressura conditon prior to attempting to sample. - CAUTION (B) - If during sampling, PS-504 high pressure alarm occurs, verify that CV-5002 closes Olght control panel), isolate IIquid sampling Inlet lines, check LI-5032 level to determine if PS-123 has lifted. Pump down the Surge Vessel if necessary by opening CV-5033, CV-5034 and running the (- Surge Yessel Pump. Correct the cause of .m v the high pressure condition prior to attempting to sample. - CAUTION (C)- Discharge liquid sample return line 1-SV-6529 or 2-SV-6529 must be open prior to opening 1-HS-5105 or 1-SV-5107 (for Unit 1); or 1-HS-5105 or 2-SV-5107 (for Unit 2). 4.5.2 Open 1-SV-6529 (for Unit 1) or I-SV-6529 (for Unit 2). 4.5.3 Open CV-5001 and open CV-5003 to approximately midpositen. i. 4.5.4 To sample RCS hot leg, position 1-HS-5105/1-CV-5105 (for Unit 1) or 2-HS-5105/2-CV-5105 (for Unit 2) switch to PASS SYS. ~'o sample the 4 LPSI pump discharge, open 1-SV-5107 (for Unit 1) or 2-SV-5107 (for Unit 2). S E NOTE ON NE r PAGZ M i ! x m. ~w
4 ERPIP 4.4.7.6 Rev.I h NOTE - a If RCS pressure observed in the Control Room is greater than 200 psig, a sample can be taken from the RCS hot leg, otherwise, a sample is taken from the LPSI pump discharge. 4.5.5 Fully open CV-5033. Open CV-5011, CV-5040, CV-5007, and CV-5004 (rotate and push switch). Contract the Con,rol Room to open the containment RCS hot leg valves (or start the LFSI pump). 4.5.6 Slowly throttle open CV-5012 to obtain a purge flow of I gpm (as read on FI-5011 and slowly adjust CV-5003 as required to keep TI-5001 at 1200 F (maximum).. 4.5.7 Purge liquid in this inanner for approximately five minutes prior to proceeding to analyses procedures. 4.6 Total Gas Concentration Analysis NOTE - Procedure 4.5 is a prerequisite to this analysis. 4.6.1 Close CV-5012, CV-5011, and cv-5004 to trap a pressurized sample. 4.6.2 Close CV-5040 and open CV-5039 to depressurize upstream tubing. l 4.6.3 Open CV-5010. NOTE-Maintain cooling water to the Sample Vessel / Heat Exchanger to ensure that any gas bubbles (high total gas samples) are cooled j prior to opening CV-5031. l 4.6.4 Record burette pressure from PI-5031 (PRCS)* 0 4.6.5 Verify tha TI-5001 reads less than 120 F, then slowly crack open CV-5031. Open CV-5002 (rotate and push switch), and CV-5026. 4.6.6 Fully open CV-5031. O \\ .----.-.-,$r,- or,,.. .p.,.. ,<7.-,,.,.. m 9
ERP@ 4.4.7.6 Rsv.1 o g - =s - The burette level may initially rise and then .s decrease in the event of high total gas concentrations due to high temperature gas bubble collapse. Allow the level to stabilize before proceeding. - NOTE - If the burette level approaches 100% (as read on LI-5031) close CV-5031 and thus record on the burette level (LI-5031L Drain the burette, to a level of between 0 and 5% by opening Cv-5036. Close CV-5036 and record the burette level Then reopen CV-5031, allow burette level to stabill2e and again record the burette level (initial level) on. If the burette level ever exceeds 100%, a new purge must be initiated (4.5) and the TGC procedure restarted. 4.6.7 Record on Attachment 3 the burette level LI-5031 (initial) and pressure PI-5031 (P )- b O - soTa - t If PI-5031 reading increases to greater than 0.3 psig, open CV-5034, check open CV-5033 and start the Surge Vessel Pump to pump down the Surge Vessel and lower the PI-5031 reading s to between 0 and 0.5 rsig. (Do not pump the Surge Vessel down below a level of 5% as read on LI-5032. Stop the Surge Vessel Pump and close CV-5034 when PI-5031 reads as required. Record the new PI-5031 (P ) value b on Attachment 3. 4.6.3 Close CV-5031. Start the Sample Circulation Pump and run it for 1 minute. Then, stop the pump. 4.6.9 Repeat steps 4.6.6, 4.6.7, and 4.6.3 until burette level does not 4 change. Then record the LI-5031 (final) level and the TI-5001 (final) temperature on Attachment 3. l l t, N l _,. 3 -,w -. I
ERPIP 4.4.7.6 Rcv.1 - NOTE - Using the recorded information listed below the Tctal Gas Concentration can be calculated (see Calculations Section 5.1). 1. Initial Burette Level, % 2. Final Burette Level, % f 3. PRCS, psig li B 4. P, psig 5. Final Temperature, OF i 4.7 Dissolved H and O2 Analyses 2 - NOTE - i Procedures 4.5 and 4.6 are prerequisites to l these analyses. 4.7.1 Adjust CV-5013 to GAS SAMPLE position. ..j Open CV-5015 and CV-5017 and select the high sclae on AI-5001 4.7.2 i and AI-5002. 4.7.3 Start the Sample Circulation Pump. f Reselect the lower scale of AI-5001 or AI-5002 if the reading f alls 4.7.4 l within the lower scale range. 't 4.7.5 Allow H and O2 gas concentrations (volume %) as read on AI-5001 2 and AI-3002, respectively, to stabilize. Record these % readings on. 4.7.6 Shut off the Sample Circulation Pump. O , __ Q,_ __ _,.
ERPI,P 4.4.7.6' Rsv.1 C - NOTE - With the information above H % and 0 %, the 2 2 T (final), P(B) and V from 5.1 the cc/kg concentration of each gas can be calculated following the procedures listed in Section 5.2. 4.7.7 If sample analysis is complete, proceed to Section 4.13. 4.3 Cas Samole Dilution Prior to Grab Samolinit for Radioisotooe Analysis - NOTE - Procedures 4.5, 4.6, and 4.7 are prerequisites to this dilution. The number of dilutions should be' calculated " prior to conducting the a procedures below. 4.3.1 Open CV-5014, CV-5016, CV-5025, and close CV-5015. Open or check l open CV-5017 and adjust CV-5013 in the GAS SAMPLE position. (h 4.3.2 Run the Sample Circulation Pump for three minutes to dilute the gas sample with nitrogen. 4.3.3 Stop the Sample Circulation Pump and record pressure at Pi-5025 (P,) on Attachment 4. g 4.8.4 If it is determined by the initial sample taken following an accident, ~ I that further dilution is required Ior subsequent samples, this can be accomplished by performing the following steps: l l - CAUTION - DO NOT ATTEMPT THESE STEPS IF CONTAINMENT PRESSURE IS GREATER I l THAN 30 PSIG. l l '9 l - s .y. 7, +
ERPIP 4.4.7.6 e Rev.1 if not already open, (a) From the Control Room position PS-519/PS-520 (for Unit 1) or PS-523/PS-524 (for Unit 2) to PASS SYS position. (b) If PI-5025 reading is greater than 0 psig, open CV-5018 and start the Containment Sample Pump and open Cv-5023. Close CV-5018 and stop the Containment Sample Pump when PI-5025 pressure reaches O psig. Close CV-5023. (c) Check open CV-5030 and slowly open CV-5044 to obtain a PI-5025 reading of 10 psig. Then close CV-5044. (d) Run the Sample Circulation Pump for three minutes to mix the added nitrogen with the sample. Stop the . pump. Record PI-5025 (PGs) reading. (e) Repeat above steps (b), (c), and (d) until desired dilution is obtained. Each time these steps are performed the dilution factor in step 4.8.5 below is multiplied by PI-5025 reading of above (psig) + 14.7 14.7 (f) Close Cv-5030 and position PS-519/PS-520 (For Unit 1) or PS-523/PS-524 (For Unit 2) to NORM SYS position. 4.8.5 Close CV-5014 and CV-5016. The Gas Sample Vessel now contains a il nitrogen diluted sample. The dilution factor is calculated using the '1 equation in above Section 4.8.4.(e), and the calculations in Section 5.4 P l NOR-The sample should nc c be withdrawn until the remainder of the system is purged following the completed reactor coolant sampling evolutions. s ae _ ,%*e e ep**t~ efwyg -o w ' - ---.;---JMMM,-e"*******N* ~ m - a
~ l ERPIP 4.4.7.6' Rcy.1 -'D 4.3.6 Close CV-5025, CV-5002, CV-5026', CV-5010, and position CV-5013 to m ~y the Total Gas flow path. 7 t l - NOTE - If the analyses are complete and no system purge is required, return all valves to their normal valve line-up per Attachment 2. I 4.9 oH and Boron Concentration Analyses - NOTE - Procedure 4.5 is a prerequisite to these analyses. 4.9.1 Check closed or close CV-5039 and check open or open CV-5040. 4.9.2 Verify that cooling water is flowing through the Sample Vessel / Heat 0 Exchanger by observing TI-5001 to be 120 F. l 4.9.3 open CV-5030 and CV-5045. Slowly open CV-5044 to obtain pressure reading of 15 psig on PI-5025. Y 4.9.4 Open CV-5004 and CV-5011. Fully open CV-5033. h 4.9.5 Slowly thre.tle open CV-5012 'and slowly throttle down on CV-5033 (in small sec';ential steps) to obtain a flow of.2 gym (as read on.FI-5011) and a p' essure reading onPf-5004 of between 40 psig and 30 psig and at least 20 psig greater than containment pressure. Between the incremental steps of adjusting these valves, adjust CV-5044 and CV-5003 as required to keep PI-5025 reading 2 psig higher than PI-5004 0 reading; adjust TI-5001 at 120 F (or other desired nominal ope-ating 0 0 temperature not to exceed 150 F)g10 F. 4.9.6 Open CV-5029 and then close CV-5011. 4.9.7 Adjust CV-5044 and CV-5003 as required to mr.intain PI-5025 reading 2 psig higher than PI-5004 reading and TI-5001 reading at the desired nominal operating temperature. i i i ..s j ..v - ;w- ~ --- y, m-- -m;.---,,-. .,.,,,~y
ERPIP 4A.7.6 Rsv.1 'I 4.9.8 Allow the boron concentration (A-502) and pH (AI-5004) readings to stabilize. Then, record the readings of A-502, AI-5004, and TI-5001 on Attachment 3. - NOTE - Temperature must be maintained nearly constant ior 15 minutes prior to obtaining i A-502 (boron meter) reading. - NOTE - If containment sump water is being recirculated through the reactor coolant I system, the pH additives which may be present i in the sump for chemistry control and iodine removal have a significant affect on the boron meter reading. Correlations are provided for <1 I the pH additives sodium hydroxide (NaOH) and l. trisodium phosphate (Na3POg.12 H O). (See t 2 1 Section 5.3). I i 4.10 Radioisotooe Analysis via Germanium Detector System - NOTE - An energy calibration procedure is conducted t prior to sample analysis. The calibration shall be initiated in Section 4.2, " Demineralized i l Water Purge and Fili of the Reactor Coolant Liquid Sample Path" (See Section 4.2.3). The operation of the reactor coolant detector should be initiated with 4.10.1 the PASS aligned to conduct pH and Boron analyses as detailed in Section 4.9. Specifically during the stabilization purge, step 4.9.7, the proper conditior.s exist to conduct the required radioistopic analysis as per RCP 2-105. The PASS RCS sample parameters at step 4.9.7 are listed below: 0, \\ i e~'- -w- -.-#,ew_.- _, mm.
ERPIP 4.4.7.6* Rev.1 ('- 0 4.10.1.1 Temperature: 120 F j] 4.10.1.2 Pressure: 40 to 80 psig 4.10.1.3 Flow: 0.2 gpm l 4.11 Liould Sample Dilution Prior to Grab Samolinst for Radioisotooe and Back-uo Boron Analysis l - NOTE - Procedures 4.2 thru 4.5, and 4.9 are prerequisites to this dilution. 4.11.1 Close CV-5004, CV-5001, and CV-5003. 4.11.2 C1cse CV-5040 and open CV-5039 to depressurize upstream tubing. 4.11.3 Close CV-5030, CV-5044, and CV-5045, and open CV-5046 to vent the electrolyte storage vessel. If PIC-5004 pressure is greater than 5 psig, open CV-5031, CV-5045, and slowly open CV-5044 to obtain a pressure reading on PI-5025 of 2 psig higher than on PIC-5004. Then h , close CV-5031, CV-5045, and CV-5044. - NOTE - The pressure on the Electrolyte Storage Vessel l should be maintained slightly higher than - t r line pressure until process line pressure is depressurized to approximately atmospheric conditions. This is required to prevent back leakage of post-accident fluid into the electrolyte storage vessel I j e z O>
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ERPIP 4.4.7.6 Rsv.I 4.11.4 Position CV-5023 to SAMPLE FLASK position and open CV-5032. p This will drop 4.7 ml of sample fluid into the depressurized liquid sample vessel which is initially approximately 20% filled with demineralized water. 4.11.5 Add more demineralized water in incremental level changesd (as read si LI-5028) by performing the following steps: (a) Close CV-5032 and open CV-5006 to obtain a change in LI-5028 level not to exceed 20% increments. (b) Close CV-5028 to SAMPLE PATH position when item (a) change is obtained. (c) Open CV-5032 to vent the vessel (LI-5023 will stabilize after satisfactory venting). l (d) Close CV-5032 and CV-5006. Repeat the above steps until the desired dilution of the sample is achieved. . provides the " volume" in the vessel versus LI-5028. level % The Depressurized Liquid Sample Vessel now contains a diluted liquid sample. The i dj " dilution fictor" is calculated using the following equation: Volume in the Vessel i 4.7 ml 4 l - NOTE - For the initial sample taken following an I accident, the Depressurized Liquid Sample I on this sample, subsequent samples with Vessel should be completely filled. Based either more or less dilution may be reuqired for efficient counting during radioisotope analysis. If further dilution is required, this can be accomplished by performing the following steps: 0 i x =-. .v. _. _.._ -.,7 ~ - -
.. _z.-.- -.- zz -...-. ERPIP 4.4.7I Rsv.1 O (1) Open CV-5032 and slowly open CV-5037 Q to drain to a desired level (LI-5023) for j further dilution. (2) Close CV-5037. (3) Fill the vessel to the desired level on U-5323 by the method employed in the above step 4.11.5. Record final U-5023 level on Arncunent 3. (4) Dilution factor in step 5.12.5 is then multiplied by the volume determined from Attachment 3 for the U-5023 reading in above step (3) diviced by the volume determined from Attachment 8 for the U-5023 reading In above step (1). NOTE - During the incremental filling procedure, if P!-5031 reading exceeds 3 psig fci' ewing g ienting of the vessel, pump the surge vessel down mtli PI-5031 reading is reduced to between 0.5 and 3 psig by opming CV-5034, checking open CV-5033 and rucning the Surge Vessel Pump. (Do not pump the surge vessel down below a level of 5% as read on E 5032). Stop the Surge Vessel Pump and close CV-5034 when PI-503l reads as required. NOTE - This sample should not be withdrawn until the ,tj reniainder of the system is purged following i the completed reactor coolant sampling a i evolutions. l .) i ! \\
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ERPIP 4.4.7.6 Rsv.1 4.12 Partial System Purge and Diluted St ate Withdrawl 4.12.1 Isolation of Liquid Sample Inlet Path - NOTE - Procedures 4.4 and 4.5 are prerequisites to this isolation. (a) Close CV-5033, CV-5029, CV-5012, CV-5008, and CV-5039. (b) if RCS hot leg is sampled, position 1-HS-5015/1-CV-5105 (for Unit 1) or 2-HS-3015/2-CV-5105 (for Unit 2) to NORM SYS. If LPSI pump discharge was { sampled, close 1-SV-5107 (for Unit 1) or 2-SV-5107 (for Unit 2). 4.12.2 Partial System Purging Prior to Diluted Sample Withdraw! ..O . NOn - Steps 4.1, 4.8, 4.9, and 4.11 are prerequisites to this purging. If not already open, (a) From the Control Room position PS-517/ PS-518 (f or Unit 1) or PS-521/PS-522 (for Unit 2) to NORM SYS positon and close CV-5024. (b) Check CV-5013 in the TOTAL GAS position, open CV-5025, CV-5015, CV-5018, and CV-5023. 'I l 0 l 1 i u . 21 - s {
ERPIP 4.4.7.$ RGv.1 O-(c) Open CV-5030 and slowly open CV-5044 _s until a flow rate of 0.6 and 0.3 cfm (as read on FI-5019) is obtained to purge this path with N - 2 (d) After 'two minutes, dose CV-5015 and open CV-5017 to purge this branch for thirty seconds. (e) Close CV-5044, CV-3017, and CV-5023. (f) Purge the inlet line to the sample station and back-flush the strainer by opening Cv-5039, CV-5008, CV-5004 (rotate and push switch) CV-5010, and CV-5005. Purge demineralized water in this manner for twa minutes. (g) Fully open CV-5033, open CV-3011, dose CV-5004, and slowly open CV-5012 to obtain a flow of I gym (as read on FI-O 501 o.. 0 (h) After one minute, open CV-5029 and dose CV-5011 to purge the pH and boron meter line. Adjust CV-5012 as necessary to maintain 1 gpm (on FI-5011) for a period of two minutes. G) Close CV-5010, fully open CV-5031 to purge the burette. The Surge Vessel will begin to fill. Pump down the Surge Vessel while purging as necessary (level on LI-5032 should not exceed 90%) by i opening Cv-5034 and running the Surge f Vessel Pump. Purge in this manner for two minutes. Then dose CV-5005 and CV-5031. Turn off the Surge Vessel Pump and dose CV-5034 h i ~ q" 4.12.3 Diluted Sample Withdrawl N r < r: -v""~* "m 9_- , ;J., mjQ-- -L,.
ERP!P 4.4.7.6 Rev.1 ERMT Member LRMT Member i (a) Record dose rate (a) This portion of the procedure addresses in sample area prior the withdrawl of the " diluted" reactor to shield port removal coolant gas sample obtained in step 4.3 and the "dilutec" reactor coolant liquid sample obtained in step 4.11. The Dose Rate = R/h required materials for diluted sample withdrawl are three syringes (capacity of 5 ml (each) minimum and of length Date/ Time / such that sample vessels can be sampled through the shield wall). (b) Dose rate at Sample Port (b) Remove the shield wall access ports and insert syringes through system R/hr plugs. Operate the syringe to remove the sample (s) of interest. The location Date/ Time / of the samples are as follows: the upper left hand port is for the Dose Rate of Sample Gas Sample Vessel; the upper right hand port is for the Cor. alnment Sample R/hr Vessel; the lower port is for Depressurized Liquid Sample Vessel. (c) Dose rate on outside (c) Place the sample into lead container. of shield. Close container lid. R/hr li l l 1 1 f -D- _. _.. _ = _,. _. _. ~ _ ..-___..m,_,___.~.__.
-~ ~ ~.. _.. ' ERFIP 4.4.7.*6 Rsv.1'. m ERMT Member LRMT Memcer ')/ (d) Promptly axit sample room (d) Depart with ERMT member, taking with LRMT member and sample sample cart and shielded sample cart, and Radiac Instrumentation. Return to 69' Controlled Area. / / RPD N died Tune Time exited Time i (e) Provide c::ntinuous (d) Contact Control Room and request that monitoring coverage during the PASS Sample Isolation Valves are the transport of shield SHUT. sample to the radlochemistry laboratory and minimize Deposit sample in' Chemistry ilot radiation exposures by Laborat6ry or as directed by CD for s effective use of barrie</s and
analysis, minimum stay time.
g (f) Ensure personnel exposure (f) Prepare sample tag with the following data has been recorded. data, and tie to sample collection ? I apparatus container. a. Name and type of material () b. Time sample taken () c. Sample #,if applicable () d. Location of sample () e. mR/h on contact after sample containment () t l Leave Attachment I with samples for use in analysis. s , g -,- - -.-,.. _, - -. - - -....
i ERPIP 4.4.7.6 Rev.1 " 23 ""' "i"" *" d " * '" tt"" **** **" S** ' ** O This procedure is performed between sampling evolutions. Complete purging should be perf ormed as specified below. NOTE - This purging should not be attempted unless containment building pressure is less than 10 psig. 4.13.1 Perform Sections 4.1 through 4.4. 4.13.2 Verify that Section 4.12.2, steps (f) through (i) have been completed. 4.13.3 Drain and flush the Depressurized Liquid Sample Vessel as follows: (a) Open CV-5037 and CV-5032 to drain the sample vessel to a level of between 0 and 5% as read on LI-5028. Close CV-5037. (b) Position CV-5028 to SAMPLE FLASK position. (c) Fill the vessel to a level of 80% on LI-5028 by the method employed in Section 4.11.5. Then, slowly open CV-5037 and CV-5006 to initiate flush of the vessel Adjust CV-5006 and CV-5037 to maintain a level of between 60% and 80% on E ( 3028 during this flushing. (d) Pump down the surge vessel as necessary to prevent exceeding 90% level on LI-5032 by fully op(.-ning CV-5033 and opening CV-5034 and running the Surge Vessel Pump. - NOTE - Do not allow surge vessellevel to decrease 1 below 20% (as read on LI-5032). (e) Purge in this manner for five minutes. Then close CV-5006 and CV-5037. (f) Slowly reopen CV-5037 and CV-5032 to drain the liquid sample vessel down to a level of 20% (as read on LI-5023). Then close CV-5037 and CV-5032 and position CV-5023 to Q SAMPLE PATH position. - s New op = enw vam-
m
--gm.g. e ye e eg,, p. p .pe -, 4 . y 9 9 9 9,.
ERPIP 4.4.7.6' Ray.1 4.13.4 Drain the burette by opening CV-5036 until a level of between 0 and 5% 's y is obtained (as read on LI-5023). Close CV-5036. v 4.13.5 Return all control panel valves to the position given in Attachment 2 " Normal Valve Line-Up." 4.13.6 THE SYSTEM IS NOT READY FOR COLLECTING AND ANALYZING A NEW SAMPLE. a 3 1 l i l { ) 26 - 4 - ~ ~, -
l ERPIP 4.4.7.6 Rev.1 o O 5.0 CALCULATION PROCEDURES 3.1 Total Gas Concentration Calculation 5.1.1 Calculate change in burette level as foHows: (a) Using Attachment 9, cetermine the initial volume (ml) in burette based on initial burette level on LI-5023. (b) Using Attachment 9, determine the final volume (ml) in burette based on final burette level on LI-5023. (c) Calculate change in burette level as foHows: A V = final ml - initial ml - NOTE - If burette level approached or reached 100% during sampling resulting in burette drain, the A V is calculated by adding the change for the intial rise in level to the change in level foHowing the drain. 5.1.2 Using the recorded reactor coolant system values obtained in Section 4.6, calculate the total gas concentration as fonows: g + 14.) [ 492 {y, (pRCS x Vg3xCy B+ P + (Vg3j TG = 14.7 ) (T + 460j .9 Where: Total Gas Concentration :(cc/kg @ STP) TG = Final TI-5001 Temperature,(O ) F T = Change in burette level-from above step 5.1.1. (c). ( ml) AV = i RCS Pressure of reactor coolant system at sample time (psig) l P = Vg3 Volume of isolated sample = 580 ml = Decompression of water from ele rated pressure = 3.2 x 10-6 C, = Final PI-5031 pressure (psig) P 4 B O m 27 - s ,w.e e= wt-*-"*-* N***" -' % M "
N' N ~
~
... ~.-........ ERPIP 4.%7.6' Rsv.1 5.2 Hydrogen (H,) and Oxygen (0 ) Concentration Calculations 7 5.2.1 Calculate the hydrogen and oxygen concentrations (cc/kg at STP) as follows: H (cc/kg at STP) 5.2.1.1 2 9 TG+[Pg + 14.7 [ 492 V 1000) = %M7 x Fx 100 ( 14.7 ) {T+ 460f (Vy3 ) L 0 (cc/kg at STP) 5.2.1.2 2 )(V fl000\\ g+14.7) I x Fx TG + P 492 = %0 7 g 100 ( 14.7 (T+ 460 (Vy3) 4 j Where: ~ t %H = M-500L reading (Volume % H ) 2 2 %C = M-3002 reading (Volume % O ) 2 2 C Hie rmai G-ract-F = If V Step 5.1.1.(c) 611 ml, F = 1.0 if V Step 5.1.1.(c) 611 ml, F = AV 611 TG = Total Gas Concentration - from Step 5.1.2 (ce/kg STP) g PI-5031 Pressure (psig) P = TI-3001 Temperature ('F) T = Volume of Gas initially in the system = 1310 ml V = g g3 = Volume of Isolated Sample = 580 ml V I 1 l ") - N .n- <m , y. , www~ - --w-
ERPIP 4.4.7.6 Rsv.1 D Boron Meter Corrections for pH Additives O 5.3 The procedures below provide calculation corrections of the A-502 Boron Mete in the event of a sump containing pH additives, sodium hydrozied (NaOH) or
12 H O). Presently Calvert Cliffs has Na3 POg trisodium phosphate (Na3 POg 2

12 H O for a pH control.
POg
12 H O is used for sump pH control, correction is made as 2
5.3.1 If Na3 2 follows: (a) Use Attachment 6 to obtain the ration of ppm NA POg
12 3
H O to ppm boron based on boron meter (A-502) and pH 2 meter (AI-5004) readings. (b) Using the A-502 reading and the ratio obtained from, calculate (ppm Boron ) as follows): e A-502 reading ppm Boronc = 1 + (0.265 x ratio) (c) If the above corrected boron concentration is within 50 ppm of the original A-502 reading, record this value as the corrected boron concentration. Otherwise, proceed with the following steps. (d) Using the above corrected value arid the (AI-5004) readings, obtain a new ratio from Attachment 6. (e) Using the new ratio, calculate a new corrected bc4on concentration using the equation in above step (b). (f) If the new corrected boron concentration is within 50 ppm of the previous Iteration, record this value as the corrected boron concentration. Otherwise, using the new corrected l boron concentration and AI-5004 reading, obtain a new ratio l from Attachment 6 and then return to step (e). If NaOH is used for sump pH control, correction is made as follows: 5.3.2 (a) Use Attachment 7 to obtain the ratio of ppm NaOH to ppm Boron based on boron meter (AI-5004) readings. O i I s
~. _.____ _.. ERPII? 4.4.7 6' R cv. 1 O (b) Using A-5r2 reading and the ratio obtained from _I ,, calculate a corrected boron concentration (ppm Baron ) as follows: e A-502 reading ppm Boron e = (0.34078 x ratio) i+ (c) If the above corrected boron concentration is within 50 ppm of the original A-502 reading, record this value as the corrected boren concentration. Otherwise, proceed with the following steps. (d) Using the above corrected value and the AI-5004 reading, obtain a new ratio from Attachment 7. (e) Using the new ratio, calculate a new corrected bcron concentration us'z te equation in above (f) If the new corrected boron concentration is within 50 ppm of the previous iteration, record this value as the new corrected boron concentration and AI-5004 reading, obtain a h new ratio from Attachment 7 and then return to above step (e). 9 l i i e 9 j .m e ew*m. _ eq _, e+. -,7-- 3___
ERPIP 4.4.7.6 Rsv.1 'b,, ; 5.4 Gas Samole Dilution Factor of Grab Sameles for Radioisotooe Analysis 5.4.1 Dilution Factor = ( Pm + 14.7\\ [ 492 h [VGS + YDG + AV) xF 74.7 / \\ T + 460 ) \\ / vg Where: GS PI-5025 Pressure Recorded in Step 4.8.3 (psig) P = TI-5001 Temperature Recorded in Step 4.6.7 (OF) T = g3 Volume of Gas Sample Vessel = 12,5'J0 ml V = Volume of Gas initially in the system including Gas Sample V = DG Vessel Branches = 1,345 mi Changes in burette level calculated in Step 5.1.1.(c). (ml) aV = High Total Gas Factor calculated in SMp 5.2.1 F = g3 Volume of Isolated Sample = 580 ml V = s 4 4 1 I h ' IM
-a
t ERPIP 4.4.'7.6 i Rsv.1 ) m 6.0 REPORTING .y 6.1 Report promptly and verbahy preliminary data obtained during entry to the RPD and CD. Brief RPD and CD on the following as a minimum: 6.1.1 Exposures received by reentry personnel (SRD= type data) 6.1.2 Exposure rates measured enroute to sample room and maximum exposure i rates measured within sample room during entry. 6.2 Collect lapel air samples and send to counting laboratory for analysis. Report to CD and RPD for full debriefing and provide copy of completed data 6.3 shown on Attachmem. I. O O t 4 i 4 1 .y ;
32
I -.- -,s j s. - - .r. ^ 2 ~~ -2
~ ERPIP 4.4.7.6 Rev.1 ATTACHMENT I 'O ACCIDENT SAMPLE AND ANALYSIS DATA SHEET SAMPLE # SAMPLE LOCATION: UNIT 1 2 SAMRE: DAM ME: 1 -- DOSE RATE ON CONTACT: mrem /hr REMARKS: SAMPLED BY: LMRT ANALYSIS TO BE PERFORMED: RESULTS ( ) Gross Beta / Gamma ( ) Gamma Spectrum Analysis I ( ) Boron Analysis ( ) Chloride Analy' sis ( ) Other (Specify) t I ANALYSIS PERFORMED BY: / / LRMT DATE TIME NOTES: (1) Report results to CD as soon as practical. (2) Retain all samples for future use. i Storage Location Placed in storage area by: / Date Time REMARKS: to s x ~ ~~ n * *swM~,y"* e n - - m en --m ~rw w. - n
= -_.. = ERPIP 4.'4.7.5 I Rev.1 I' ATTACHMENT 2 t .l PASS NORMAL VALVE LINE-UP Valve Position Valve Position Valve Position
PS-100 OPEN CV-5005 CLOSED CV-5040 CLOSED i

PS-101 OPEN CV-5006 CLOSED CV-3041 CLOSED

PS-102 OPEN CV-5007 CLOSED

PS-103 OPEN CV-5008 CLOSED CV-5044 CLOSED

PS-108 CLOSED CV-5010 CLOSED CV-5045 CLOSED CV-5011 CLOSED CV-5046 CLOSED CV-5012 CLOSED

PS-119 OPEN CV-5013 TOTAL GAS 1-HS-5105 NRML SYS

PS-120 OPEN CV-5014 CLOSED 1-CV-5105

PS-121 OPEN CV-5015 CLOSED 2-HS-5105 NRML SYS l
+PS-122 OPEN CV-5016 CLOSED 2-CV-5105
PS-123 OPEN CV-5017 CLOSED
- *PS-124 OPEN CV-5018 CLOSED 1-SV-5107 CLnSED
PS-130 CLOSED CV-5021 CLOSED 2-SV-5107 CLOSED
'PS-131 CLOSED CV-5022 TOTAL GAS 1-SV-6329 CLOSED
PS-132 CLOSED CV-5023 CLOSED 2-SV-6529 NRML SYS l

PS-133 CLOSED CV-5024 CLOSED

PS-134 OPEN CVeJ025 CLOSED PS-517/PS-518 NRML SYS CV-5026 CLOSED PS-523/PS 524 NRML SYS h
.O CV-3028 SMPL PATH ~~ 1-HS-5105 NRML SYS CV-5029 CLOSED PS-519/PS-520 NRML SYS 1-CV-5105 CV-5030 CLOSED PS-523/PS-524 NRML SYS CV-5031 CLOSED CV-5001 CLOSED CV-5032 CLOSED 1-CV-5016 CLOSED CV-5002 CLOSED CV-5033 CLOSED 0-CV-5005A CLOSED - CV-5003 CLOSED. CV-5034 CLOSED 0-CV-5043 CLOSED CV-5004 CLOSED CV-5036 CLOSED 0-HS-5100 CLOSED CV-5037 CLOSED 0-SV-5042 CLOSED CV-5038 CLOSED CV-5039 CLOSED + Manual valves located in Sample Station. i 1'l i f 9 '*8 e 4 4 9
i ERPIP 4.4.7.6 R6v.1 .m ATTACHMENT 3 CALCULATION FORM I ~_ TOTAL GAS CONCENTRATION AND GAS ANALYSIS DATA SHEET DATE/ TIME: / / ANALYST: 1. RCS Burette Pressure (PI-5031) psig 2. Initial Burette Levels (LI-5031) l. ,) 3. P Burette Pressure (PI-5031) psig b 4. Final Burette Level (LI-5031) 5. Final Temperature (TI-5001) 0F 6. Hydrogen (AI-5001) i 7. Oxygen (AI-5002) i i 4
., 3,,
7-,__,___
4 ERPIP 4.4.7.6 Rsv. I m O' ATTACHMENT 4 CALCULATION FORM II GAS SMAPLE DILUTION - - ' ~ ' - ~ DATE/ TIME: / / ANALYST: 1. PGs (PI-5025) psig 2. PGs (PI-3025) psig e 3. PGs (PI-5025) psig 4 PGs @!.5025)
g 5.
PGs (PI-3025) psig 6. PGs (PI-5025) psig COMMENTS: i a l 1 = - ---- - -- l I
6
m

4 ERPIP 4.4.7.6 Rsv.1 ATTACHMENT 5
/ O' CALCULATION FORM M i pH & BORON ANALYSIS DATA SHEET DATE/ TIME: / / ANALYST: 0 1. Initial Temperature (TI-5001) F i - 2. pH (AI-3004) -(,) 3. Baron (A-502) ppm 0F 4. Final Temperature (TI-5001) 5. Final Volume (I.IL-5023) t i i 37 - \\ y.,____,, , g _,,y_,. g _,,,,. ..y O
._.aa ERPIP 4.4.7.6 Rev.1 ATTACEMENT 6 3 Ogl2 H2 vs ppm Boron, pH Relationship PF" # Ratio ppm Boron 13.. pH 12.. S.O . _ ' ' ~ _ ' _ y. g. g .e.. M.m ... m..... N m. m m..e e i 1I i '[Q. e ? 6
== C J. f i, e -g N m.. M C .6 o i .=- w .y-2
s. 4,,.
.n
g. 7 a
C. _. ~... a o 5 .-s-.. M e. s 4 Of. y. s. .A 0 i / 4 3 .5 e a i i_. 4 i __ I 3 ,6 m ~ Mm 6 6 e._ ..M m m.mme = m f' 7.5 / f./ 1. M MN .me f _ e 6 6 MM M ._6 m ~ i A_ g o tooo zoco acom 4 coo seco_ g ppm Boron N em. y -,- _ - ;.. yn., m- , g., -n ., - ~ - -..
ii.M+ ERPIP 4.4.7.6 ATIACHEiT 7 Rsv. 1,, ],$.. Ratio ppm NaOH vs ppm Boren, pH Ralationship g,g ppm Boren PR m, 1.1.. / 1.6. .8 .1.5..
1. 4...
6 /
1. 3..

1. L..
i.i. .,, 4
1. 0.
.t g, -g o.s.. C L' c C 2". 'G
8. 0
( a :! 0.8. $1 c. C 0.7 = = 7.8 6.6 e,5 .U I 1'S ' li O.4 i t I<
0. 3 0.1 g
0.1 0 we
ERPIP 4.4.7.6 Rev. 1 ATTACEMENT 8 Deoressurized I.iouid Samole vessel Volume vs Leve.l._. e c ...... _.... _................... =.............. ._.3.-..__ .....__.__..t.. __. _. _ s.___ ._,_.4.. __--1__._._r_-....... _. . -,.c .-.__.. _ _ c_.. _...... _.s. ._.. _. _...__..t _._. _.e A_______.__._._.._. _.......__i. _ _u. -1.... _.___.._.s....__. = ..c - __.4._...__.. _.m _t.w_.._.i_.._..._..4...._ = =.. _ _.. __....__e...._._ .. _.__.t._....__._,.
w..__
_ ___s ._3_ _. _. _ .e c . _... _ _. _ _ _. _., _ _,. _.. _. _... o_. _. _ =.. - .__._.____..._._..t_._..=4_.__. ._.._s.__. .'e i -e n ,n, . _.=. _ -. _ -._.. _ _.....__t._.._.._... m .e c r---n..~.__._.,_.. ..;.=.. s t . m. _g ep4 e i __ __. r...._._
J
.. _..- =_ m, s t=__....._;_..._. .__. s _ _. _..... _ a__ m i_....._.m._...._._s.__._..__..... n 7 . _ _.. _.. = e l .e e=:_..... _. - -r a w _. = y ___..r-___.._.-. ..__.__..s___-__.._. _ __..... _.........._.z._.._ ._._..a_. ._._. e _.....r..._..- _...... -. m ... _ _. _.,. _ = _ - - . =... .....,__m... .4.._..._ ..._g._.. e. i ,_._..,_.=..3_.._...._J"._... _C w. .._4_..__-..e...__..._. _.. _ _. .. N I _.__._._2.-,......._.--............. _.. ._._.4 T. __ l ......._4 . _. ~... _..e. . _.:.= t"." :.. _..... ......_..3.._. ._....J..... __. g . _.. _..._...m ...._4..... ........._...4__-....._...._.... _..f.___ O 4 a g ...4 e .. I n ~ o as a r r m n e (s.mTI) aumtoA pTnbTI tassaa ~ ~ ~ 40, \\ -e, wa. *. *% __e e.gg.&e p. .e ,.,_ w 73g.,ppy .+ere.e.-we.-,.g_... g e.n._..e v v
_ _ - _ _ _... _ ~ ERPIP 4.4.7.6 Rev. 1 ATTACEMENT 9 Bureece volume vs Level =. _ _... _.. _... _ e .e ,/ v.. . r. _.. _ _. _.... _ _ _.... _..... .. s .__ s e _ - = e ---_s ___._.... _.. =: __ _..s_ a__.. = i _......(--- = .._ _:._.__. x._ ._ 3.__.._i.... g r, __.(_._.... .. _= __.t.. x_._ e ._... +. _ _ e . _.. _ _...... t_. _..... .i A_.._.._... . O e a 2 ,n, e. e ..._ _...__..4__.._..... _.m _.... an ._.._.u.._._ _.c s x _ _ _. _ =. _... ao e ._. _.. _ _. _. = - - m = _. 4 r m. l en 7 r.._.._.... t. .. _....__ a ._._.t_...a._..._ n u_...... 1 __ -3.. m.- c _= ......_4. \\. i ,s. --+
n..,
a__..__.._ .i. _. l _e. _ _. _e. e. ...m .. N e c e. (ssas1:T) aantoo. 32 sung l 41 of 41 ' l ..w.m. .i. .,,--v,. Y' p f
v. f
,s .e . m..
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9 =>.;
.......s .:=..e. 7 .,.s.. ...,..s,. s .3.;. j,,. ..g..::. e ...u.. n . u- "1'~." nPU 4.4.7.6 ' REVIEW / APPROVAL ( ~ . n' 'a POST ACOG Crr.SAMPL UG SYSTEf AND ANALYS"'S MISION CHANGE REVIEWER SIC / SUPERVISCR POSRC PLANT SUPERINTENDENT DATE EPU SIG/DATE MTG /DATE W WY4k. M 124 0.RNLj/ 9-cM2 O 18$L# dCdFFN'a sa z9 G 6 % nhsh I a y r y e p. b b e k I I I t. I I' 4 4 a 0 e g I
y. -
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. =,
-_.....=. - -. ~ Pcg2 '1 ' of 1' Rev. 1 O CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN Aj IMPLEMENTATION PROCEDURES LIST OF EFFECTIVE PAGES_ ERPIP PAGE REV. ERPIP PAGE REY. 1 1 26 1 2 1 27 1 3 1 3 1 4 1 29 1 5 1 30 1 6 1 31 1 i 7 1 32 1 33 1 8 I l 9 1 34 1 10 1 35 1 ~ 11 1 36 1 12 1 37 1 38 1 . g' Q '13 1 14 1 39 1 40 1 13 1 41 1 16 1 17 1 18 1 19 1 20 1 21 1 l D 1 l 23 1 24 1 25 1 0 O ~ \\ i < ; - m;r - ~ R y, - ' ~~ ? ; .. ~
ERPIP NO. 4.6 Rev. 9 O TITLE: AD TO AFFECTED PERSONNEL CONTENTS-Section ProcedJre 4.6.1 EMERGENCY PERSONNEL RADIATION EXPOSURES 4.6.2 FIRST AID AND MEDICAL CARE (EFADT) i 4.6.3 HEALTH PHYSICS ASSISTANCE AT CALVERT MEMORIAL .J. HOSPITAL, .r. i.x i. - ~ 4.6.4 GUID ANCE FOR FIRST AID AND MEDICAL PERSONNEL AND HEALTH PHYSICIST IN INITIAL M AN AGEMENT OF IRRADIATED OR RADIO ACTIVELY CONTAMINATED .~ PERSONNEL.
u. nw
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' FARM DEMONSTRATION BUILDING DECONTAMINATION FACILITY - .s. .s.. O des A m e e dA-9 -= .,.?* i e i 1 i s% '/ ~- t 4.6-1 _m -==.= wp use rewee mme a= -= _ - ~. . vt s . s. - 7--
.
y,,
ERPIP 4.6.5 Rev. O O TITtE: r^au DeuosSTnaTros sottDisc oeCOsr^=rs^Tros r^Ct'iry RESPONSIBLE INDIVIDUAL: Any individuai qualified to perform Personnei Decontamination. CONDITIONS: Personnel decontamination is required .aS. Controlled Area Medical Treat:nant Room use is prevented. ACTIONS f Signatura Data Farm Demonstration Tank No. i permits sewage to enter the septic drainfield l (conventional filtration of the sewage waste into the environment). Failure to isolate Tank No. i as specified may result in radioactive materiais entering the environment.
i. AT the Farm Demonstration garage, REMOVE the valve Action Complete pit grating cover. (see Attachment i.)
4 2. CLOSE Waste System Tank No. i isolation valve WS-1. Action Complete t 3. OPEN Waste System Tank No. 2 isolation valve WS-2. Action Complete 1 i< 4 REPLACE the valve pit grating cover. Action Complete l 1 O l l
4. 6.5-1 x
c. .. r ~ ~ -
__.m ERP!P 4.6.5 Rev. 0 5. TAG Tank No. 2 Cleanout (Attachment #1) with a Action Complete caution-radioactive materials tag (or equivalent). Tag must require Chemistry to be contacted prior to opening. 6. SET UP bathroom as a Radiciogical Control Area. Action Complete Must include a step off pad at the door, personnel monitor (RM-14 or equivalent), bags for contaminated waste and decontamination supplies. i 7. NOTIFY Chemistry Director and Radiation Protection Action Complete Director that: ' facility is prepared to receive contaminated personnel ~ Tank No. 2 requires sampling and monitoring prior to pump-ing out. 8. FORWARD this checklist and all records related to this emergency response to the Supervisor-Emergency Planning. p' l I 4 4.6.5-2 \\ t _,-,-~,,---,e ~ - -~~y-~~--- 4
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2. N
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