ML20093D488

Public Version of Revised Emergency Plan Implementing Procedures,Including HNP-4858, Naturally Occurring Phenomenon & HNP-8108, Pocket Dosimeter Use & Performance Test. W/831031 & 840709 Release Memo

ML20093D488
Person / Time
Site:	Hatch
Issue date:	10/31/1983
From:	Greene J, Nix H GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
GM-83-1062, PROC-831031, NUDOCS 8407170027
Download: ML20093D488 (63)

Text

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y GEORG1A POWER COMPANY 6

• HATCH NUCLEAR PLANT g PROCEDURE Naturally Occurring Phenomenon PROCEDURE TITtE HNP-4858 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD F' R Page 1,2,6,9 & 10 1

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• PROCgC;gnE REVIGION REGUGGT h fh-) '

PROCEDURE NO. HNP- Nb SHEET 1 OF I i i l

Revision No. 3 __

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___ ___.._..__ __ DEPARTMEljT WEAO_6PPRO'jM.

REGUESTED OY Date: n- .:

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REVISION CHANGES (

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) Yes OF CPERATION (X) No GR INTENT AS DESC CHANGE INVOLVES: ( ) Tech. Specs. ( M Neither-( ) An unreviewed Safety Guestion (See back f or- Safety Evaluation if required).

Gafety Related (>O Non-Safety Related .( )

PRESENT STATUS:

The above Safetymon-Safety Status has changed ( ) Yes to _ _ _ _ .

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Attach marhed up copy of procedure to this form.

REASON FOP REGUEST: '

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SAFETY EVALUATION .. - - - - - - - - - - - -

!. tion as explained This revision does not cons _titute an unreiidwed safety ques -- _ .

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below. . -,_

N The probabil..ity of occurrence and the consequences of an accident or i

ip.a.lfunc. tion _of_ equipment impor_ tant to safety are not increased above those analyJze_d_ in the FSAR du_e to this revision because the revision

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t-do.,e.5 not change'the pur_p_ose oi performance of the systa.. _

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s 2___ TheJossibility of an accident or malfunction of a different type T,han anal.yled in the FSAR does not result from this revision because the weem_ responds an'd is operated as before the revision. - _

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'_.h. The marqin q of safety,_as defined in the Technical Specifications is reduced due to this revision because the revision does not change - . . - _ _

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_any limited _ safety system settings which would allow a safety limit -

..t.o. be exceeded or allow a limiting condition for operations to bc

. exceeded as stated in.Te.c.hnical Specifications.

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e APPROVAL PROCEDUHt NO E. l. HATCH NUCLEAR PLANT HNP-4858 See Title Page " Eve *

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4 q Q\ See Title Page Georgia Power 1 of 11 NATURALLY OCCURRING PHENOMENON NOTE (This procedure supersedes: HNP-43OO, Revision 4 approved 7/25/80; HNP-43Ol, Revision 4 approved 9/18/79; HNP-4302, Revision 1 approved 9/18/79.)

A. CONDITION: EARTHOUAME The plant accelerographs indicate: seismic activity, and ground motion is felt, or outside sources report ground motion.

B. OPERATOR ACTIONS

1. For a seismic shock with only annunciator DO76 (Seismic' Instrumentation Triggered) in panel H11-P657 and the RED INDICATOR LIGHT (L51-DSOO1) on the TIME HISTORY ACCELERGRAPH (LS1-R600) in panel H11-P701 which is less than OBE (0.08g),

continue to operate and proceed with plant inspection.

Follow Figure 1. Declare a NOTIFICATION OF UNUSUAL EVENT

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EMERGENCY and refer to procedures HNP-4420, 4422, 4423 er 4430 for the appropriate response.

2. For a seismic shock with annunciation as stated in B-1 and any of the following:

a. Unit I (1) Seismic peak shock recorder high G level alarms.

(DO70 in panel H11-PG57 is set to actuate when 100% OGE of 0.08g vertical has been exceeded).

. NOTE One or more amber lights on peak shock annunciator panel (L51-R620 on panel H11-P701) will be on. These annunciator lights are set for 100% 08E level at 4 frequencies and 3 directions (North /

South, East / West, Vertical). This info will be recorded in C.1.A.

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b. Unit II l

(1) Seismic peak shock recorder high G level alarms.

I r~T (DO68 in panel 2H11-P657 is set to actuate when l (l 100% OBE (.08g) vertical has been.ezceeded. -

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APPHQvAL PROC (DURLNQ E.1. HATCH NUCLEAR PLANT HNP-4858 See Title Page a" * * *o ort _.

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See Title Page 2 of 11 NOTE One or more red lights on peak shock annunciator panel (L51-R620 on panel H11-P701) will be on. These annunciators are set for 100% OBE level for 4 frequen-cies by 3 directions (12 total) (North /

South, East / West, Vertical) This info will be recorded in C.1.A.

(2) " Seismic switch tripped" alarm (DO69 on panel 2H11-P657) which is set at OBE level of .08g.

Shut down the affected unit (s) and declare an " Alert" emergency. Follow Figure 1. Refer to procedures HNP-4520, 4522, 4523 or 4530 for appropriate response. s NOTE If any of the situations in section 2 occur, the operator should play back the Time History Recorder tapes to

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determine the actual maximum g acceleration magnitude.

instructions on retrieval of seismic data, see HNP-1-3980 M

- section G.2.)

(For (3) For a seismic shock with annunciation as stated in B.1 and B.2 above and the maximum g level measured by the time / history accellograph recorders is greater than DBE levels (0.15g), shut down the affected unit (s) and declare a site area emergency. Follow Figure 1. Refer to procedures HNP-4620, 4622, 4623 or 4630 for appropriate response.

. (4) For a seismic shock resulting in massive damage to the ECCS system, refer to procedures HNP-4720, 4722, 4723 or 4730 for appropriate response.

(5) Notify Plant Management.

C. SUBSEGUENT OPERATOR ACTION

1. A post earthquake instrumentation review will be conducted as follows:

l a. Record the Peak Acceleration recorder lights (Red and j Yellow) on Data Package 1. Have three qualified operators verify the lights before resetting the panel.

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b. Check the feedwater to steam flow for a mismatch 7~ vi

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See Title Pace 3 of 11

c. Check the applicable neutron range monitors for abnormal readings.

d. Check all systems for abnormal power changes.

e. Check the drywell for temperatures, humidity, pressure and the sample system for abnormal activity levels.

f. Check the drywell sumps for high level and/or flow.

q. Check all other equipment drains and sumps for high level and/or high flow rates.

h. Check the torus water level recorder for high or low level.

i. Check all area radiation monitors for excessive activity levels.

j. Check the 4160 volt and 600 volt auxilliary equipment for trips.

() k. Check the turbine generator instrumentation.

2. Notify the Test Shop to do each of the following as required by Figure 1.

a. Retrieve record plates from the Peak Shock Recorder (L51-N105) per HNP 1-5631 and record data. Install new record plates to record after shocks.

b. Retriev'e record plates and tapes from the Teledyne PRA-103 Peak Recording Accelerometers per HNP-1-5625 and Engdahl P6R400 Peak Acceleration Recorders per

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HNP-2-5626. Install new record plates and tapes to record after shocks.

c. Retrieve magnetic tapes from the Time History Accelerograph recorder, L51-R600, per HNP-1-3980. Make hard copy records and install new tapes.

d. Restore all instrumentation to operable status with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (Unit 2 Tech. Specs. 4.3.6.2.2).

e. Recalibrate all seismic monitoring instruments actuated during a seismic event within 30 days. Notify Kinemetrics, Inc. (telephone 213-795-2220) to perform r3 calibration of the Time-History Accelerograph System

(_/ and the Peak Shock Annunciator System ,(Lhit a Tech.

Specs. 4.3.6.2.2). . . ; - j v

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APPHQvAL PRCC(DyHL NQ E. I. HATCH NUCLEAR PLANT WP-4858 See Title Page atax^

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See Title Page v 4 of 11

3. plant inspection should include.but not be limited to the following:

a. Inspect the main steam lines and turbine extraction steam lines for damage.

b. Inspect the condensate piping and pumps for leaks and damage.

c. Inspect the feedwater piping and pumps for leaks and damage.

d. Inspect the turbine oil system for leaks or damage.

e. Inspect the RWCCW and service water for external leaks. Check for an internal leak by monitoring th,e RBCCW surge tank level.

f. Inspect the intake structure and associated equipment for damage.

g. Inspect the off-gas stack and equipment for leaks.

O h. Visually inspect the diesel generators and their switchgear to assure the units are intact. Perform the routine surveillance test to prove the system is operable. Tie each diesel generator onto its bus and isolate its bus from the system one at a time.

Minimize operation of the diesel generator in parallel with the system because a major transmission line fault, which is probable during this event, could cause damage to a parallel diesel generator.

1. Inspect the switchyard for damage.

j. Inspect the turbine pedestal for damage.

4r. Inspect instrument racks and control panels for damage.

1. Inspect CSCS components for damage.

m. Inspect fuel pool for damage.

n. Inspect ali plant batteries for damage.

o. Inspect instrument and service air system.

(} p. Inspect plant communications for damage.

4. Evaluate the post earthquate instrumentation review and "5 73 l plant inspection. gggg&lET 'O, '

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5 of 11

5. Completer analysis of seismic data.

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NOTE The results of the plant inspection will immediately be reviewed by the Plant Review Board and appropriate surveillance testing will be specified. A special report must be submitted to the NRC within 10 days.

D. BEEERENCE Unit 2 Technical Specifications para. 3.3.6.2 E. QONDITION:_ TORNADO The plant shall normally be alerted by outside communications and/or local indications of a tornado condition in the area which may disrupt the transmission system or present a hazard to the .

station facilities. The plant will remain at full availability unless dictated to be otherwise by deteriorating conditions. As evaluated by supervision.

O r. m eRaTOR 4CT10N

1. Thoroughly inspect the plant for loose materials which may be blown about.

2. Instruct contractor personnel of the event and advise them to commence preparations for the securing of construction

, materials and equipment.

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3. Remove or secure all outside scaffolding and swinging stages.

4. Close and secure all Reactor, Turbine Building, Switchyard and Off-Gas Filter Building doors.

5. Plant personnel shall seek refuge within buildings and

' report to their supervisors for specific instructions.

6. Perform routine surveillance test of the standby Diesel-Generators in anticipation of a potential off site power failure, if a tornado has been sighted in immediate area or known to be headed in direction of site.

7. Arrange for additional assistance to provide continuous inpections of buildings and roofs.

(y') 8. Install door braces on all roll-up doors eguipped for braces.

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i 9. Notify plant management.

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APPH@f*( PHQLgDyHg W E. I. HATCH NUCLEAR PLANT HNP-4858 See Title Page auem w oara _. 4

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10. For any tornado onsite causing significant damage affecting plant operations, refer to procedures HNP-4420, 4422, 4423 or 4430 for appropriate response.

11. For any +ornado striking the facility incurring damage affecting safety systems, refer to procedures HNP-4520, 4522, 4523 or 4530 for appropriate response.

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12. For any tornado or sustained winds in excess of design level (300 mph), refer to procedures HNP-4620, 4622, 4623 or 4630 for appropriate response. )

G. @UggEQUENT_OPERATIgN_ACTIgN

1. In the event buildings have been damaged or the reactor power level has become abnormal, internal damage to the ,

process system may be suspected. Proceed with an instrumentation review and plant inspection per HNP-4858 section C.

2. Perform continuous building inspe-tions.

( ~) 3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow the applicable annunciator response or emergency procedstre.

4. If the plant is not damaged and is operationally intact following an alert, resume normal operations and inform Load Dispatcher.

H. CgL9DIT_I_ON: HIGH WINDS (HURRICANE)

The plant shall normally be alerted by outside communications and/or local indication-of high wind conditions which may disrupt the ttansmission system, or present a hazard to the plant facilities. The plant personnel shall prepare for plant load reduction as may be required. In the event winds reach hurricane velocities (sustained wind speed greater than 75 mph) near the plant site and/or a plant load rejection is imminent, notify the load dispatcher and reduct to load ac directed.

I. QPERATgR_ ACTIONS t

1. Thoroughly inspect the plant for loose materials which may be blown about.

2. Instruct contractor personnel of the event and advise them to commence preparations for the securing of construction

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3. Remove or secure all outside scaffolding sw M tages.h L

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4. Close and secure all reactor, turbine building, switchyard and off gas filter building doors.

5. Plant personnel shall seek refuge within the plant buildings and report to their supervisors for specific instructions.

6. Perforn the reutine surveillance test of the standby emergency diesel gener4 tors in anticipation of a potential off-site power failure when winds reach hurricane velocities near the site.

7. Arrange for additional assistance to provide continuous inspection of buildings and roofs.

8. At the direction of plant management or the Operations Supervisor reduce power to 25% rated when winds reach '

hurricane velccities near the site and a plant load rejection is imminent.

9. Install door braces on all roll-up doors equipped for braces.

10. Notify plant management.

11. For any hurricane (wind speed greater than 75 mph) onsite causing significant damage affecting plant operations, refer to procedures HNP-4420, 4422, 4423 or 4430 for appropriate response.

12. For hurricane winds nea.- design basis level (300 mph), refer to procedures HNP-4520, 4522, 4523 or 4530 for appropriate response.

13. For hurricane winds greater than design level, refer to procedures HNP-4620, 4622, 4623 or 4630 for appropriate r,esponse.

J. @UD@gGUENT OPERATOR _ ACTION

1. .In the event buildings have been damaged or the reactor power level has become abnormal, internal damage to the process system may be suspected. Proceed with an instrumentation review and plant inspection per HNP-4858 section C.

2. Perform continuous building inspections.

3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow p)1 s- the applicable annunciator response or emergency.precedure.

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4. IF the plant is not damaged and is operationally intact following an alert, resume normal operations and inform Load Dispatcher.

K. CONDITION: FLOOO The plant shall normally be alerted by outside communications and/or local indications of river elevation greater than or equal to 88.6 ft Mean Sea Level which may present a hazard to the plant facilities. The plant personnel shall prepare for plant load reduction as may be required.

L. OPERATOR ACTIONS

1. For (50 year) flood causing significant damage affecting plant operations, refer to procedures HNP-4420, 4422, 44,23 or 4430 for appropriate response.

2. For flood near design level (greater than 100 ft. Mean Sea Level), refer to procedures HNP-4520, 4522, 4523 or 4530 for appropriate response.

( 3. For flood or hurricane surge greater than design levels (greater than 120 ft. Mean Sea Level), refer to procedures HNP-4620, 4622, 4623 or 4630 for appropriate response.

M. SUG_SEGLJENT OPERATOR _ ACTION

1. In the event buildings have been damaged or the reactor power level has become abnormal., internal damage to the process system may be suspected. Proceed with an instrumentation review and plant inspection per HNP-4858 section C.

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2. P_erform continuous building inspections.

3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow the applicable annunciator response or emergency procedure.

4. If the plant is not damaged and is operationally intact following an alert, resume normal operations and inform Load Dispatcher.

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NAL PHOCEDvHt NO

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1 HAVE REVIEWED THIG DATA PACKAGE FOR COPPLETENECS AND AGAINGT ACCEPTANCE CRITERIA IN ACCORDANCE WITH FM-830.

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REMARMS: . . - - - - ._ . .

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11 of' 11 OATA PACHAgg_1 PEAM ACCELEEA.IlQN_RECQ8QG8.21AIVQ Oate of Seissric Event Time of Event E = Esep to Lights 4 e = Lamp is not Lightad-l l

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HATCH NUCLEAR PLANT PROCEDURE C-Pocket Dosimet,er Use and Performance Test PROCEDURE TITLE

..H..NP-8.108 PROCEDURE NUMBER

_ . __ _ _ L..a b RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

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Revit, ion No. kb doutpto_ov OEFZ57iEAY~~i"Id_~5FFFiiEEL -- -

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Name: g ar- ucte: ignature:

lo It 83 Remo4 4rCono 9.2c,-e3 a-n.r.1 f ----

REVISION CHANGES NCDE OF CFERATION OR INTCNT AS DESCRIGED IN l'SAR:

( v) Yes ( ) No CHANGE INVOLVES:

( ) An unrevieweri Gafety Guestion ( ) Tech. Specs. ( .t Neither (See t>ack f or Gafety Evaluation if required).

PRESENT STATUS: Gafety Related ( Non-Safety Related (- )

The abova Safety /Non-Safeiy Gtatus has changed ( ) Yes to ~_ _

Attach marked up copy of procedure to this Form. .

RChSON FOR REGUEST: $ cL .Dvmn*r rE L_. Cph n h 7'ef>_ G im b bVr 0 a n_.est tzu.=.. u s.r.ri.e__ci__Dwmen.aL ___ __

- _ _ _ _ _ _ . _ _ _ _ - - _ . . _ _ _ _ _ _ _ = - -

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DESCRIPTtON OF CH/.NGEG: __ /A I / d#.4 D' C- I'i.dC.M_%d..~_7 4 > G4/4/4U,, --

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PRO RECOMhtr.NDS' APPDOVAL: (Mes ( )No __

PRO Secretary 83-19'.1 = _ _ B:2 .0.. 9 s _- -

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EAEETY EV.M.UATIQt.j . .. . ..._ _ ..__ ._ _ . . . . ..

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_Jhh.Igyision .does not constitute an unreviewed safety question as explained U '

below.._[ .

1. I.h.g.g,qht)1],1.ty__of occurrence and the consequences of an accident _or ing.1.fy.nq1i,.gn_of equipment important to safety,are not _ increased above thgig_gng]ngd in the FSAR due to this revision because the revision _ _ _

d.qgs not change the pugose o_r_y,e.rfomance

- -- - o_f _t_h_e _sys_te_m.

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_ 2. .Th.g gqitibility of an a_ccident or malfunction of a different type th'an AMly;gd in the FSAR does not result from this revision because the f,yty 1 2gsp_gn,ds and is operated as_before the revision.

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___2dTh.9.!!Laz.qfin of safety._a.s.,defi_ned in the_, Technical Specifications is _

_. _. .tl91_r.e. uged g due to thisj evision because the revision does not change

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_ _ , . . - ,,,any limited safe _ty_sy,s_t_e.m. se_tti.ngs__which .__ _

would allow a safety limit to be exceeded or allow _.a.-limiting condition for operations _ _ _ - - - ___ _ _

to be .,

..e_x.ceeded as s.t..a.t_ed in T.e..c.hnical Specifications.

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l A. EW8EQSE To ensure that the instrument is leak tested and response tested properly and to provide operation guides for the user.

B. SeEEIY I Observe radiation protection procedures.

C. BgEgagutgg

1. ANSI N13.5-1972

2. S-10249 J. L. Shepherd and Associates Installation and Operation Manual for Model 423 Dosimeter Calibrator D. IEDI_E991Et!ENI O

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1. Model 423 Dosimeter Calibrator S.N. 14015

2. Gamma Gource

3. Dosimeter Charger

4. Timer

c. OgggBIEI1QN_QE_1UQIEytjgNI The pocket dosimeter is a pencil shaped ionization chamber that measures gamma radiation and given an instant read-out in l milliroentgens or roentgens. The dosimeter is basically a l capacitor with a single movable electrode. The capacitor is l charged to a predetermined voltage which results in a given separation of the two electrodes. When exposed to X or gansna radiation, or both, ionization' occurs in the chamber surrounding the electrodes and causes a decrease in the charge on the electrodes. This results in a change of position or deflection of the movable electrode. The magnitude of the deflection is a function of the radiation exposure and is observable through a self-contained optical system.

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Handle dosimeters with care. These instruments are delicate and expensive.

1. Check that the dosimeter is not visibly damagedg

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2. Clean optical eyepiece of dosimeter with lens tissue paper as often as required.

NQIE Dosimeters will be routinely checked for radioactive contamination by the Health Physics staff. However, if the user suspects contamination of his dosimeter, he should notify the Health Physics Staff immediately. A contaminated dosimeter should Dal be used.

3. Zeroing of dosimeter

a. Place dosimeter over charge connector on dosimeter charger and depress dostmeter.

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b. Look in dosimeter eyeple ce and adjust hairline to zero. Remove the dosimoter slowly. ,

c. Check its zero by reading the scale with the dosimeter in a vertical or near vertical position.

O NQIE The initial (zero) reading and final reading of the dosimeter must be made with the dosimeter in approximately the same geometrical position, i.e., read vertically or near vertical.

4.' Reading of dosimeter for dose.

Read the dosimeter as in step F.3.c.

NQIE If the reading is 75% of the fu11 scale deflection or greater the dose must be logged and the dosimeter re-zerced. Notify the Health Physics Staff.

NQIE If at anytime the dosimeter is dropped or erratic readings are noted by the user, the Health Physics staff should be notified in order that another dosimeter may be issued if deemed necessary.

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1. Charge-leakage test  ; j j

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a. Adjust the hairline on the dosimeter using the

_ dosimeter charger for a value of "O". Record value, date and time and dosimeter serial number on Data Package 1 (Data Sheet 1).

b. Store dosimeter in a radiation' free area (less than 0.02 mR/hr) for a period of about 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

c. Read the dosimeter at and of storage period.

d. Enter the reading, date and time of reading on Data Package 1 (Data Sheet 1).

e. Determine the average rate of charge-leakage per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and enter the value on the data sheet.

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f. If the average charge-leakage exceeds 2% of the fulls ale reading per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, tag the dosimeter as having failed leak rate test, and mark the tag with the date of test and initials of tester.

O g. REPEAT STEPS a - F a second time for failed dosimeters. If the dosimeter does not meet the 2%

criteria the second time, it is to be disposed of or repaired.

2. Camma Source Exposure

a. Recoad dosimeter serial number on Data Package 2 (Data

, Sheet 2).

b. Post area where exposure is going to take place in accordance with HNP-8003.

c. Adjust the hairline as in step G.1.a and log the reading in the Reading Defore Exposure column.

d. Set-up dosimeter calibrator as follows:

'(1) Place calibrator on stand in center of room.

(2) Plug electrical cord into outlet.

(3) Plug timer card into timer and tighten.

(4) Place dosimeters in the appropriate ring for calibration.

(a) Duter Ring - 200 mR dosimeters (appx. 86.5 mR/hr) / J. -1,

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(c) Inner Ring - 1000 mR dosimeters (appx. 397 mR/hr)

e. Determine the time required for an exposure of 80% the fu11 scale reading. Record in the appropriate column on Data Package 2 (Data Sheet 2).

f. Calibrator Operating Procedure (1) Remove the padlock which locks the source in the "off" position.

(2) Grasp the black operating knob while standing,,at arms length from the calibrator and raise it until the spring loaded detent engages the depression on the operating shaft, to expose the source. ,.

(3) After the allotted time has expired, return the r3 source to the "off" position. Push the operating

(,/ knob down until the pin on the shaft strikes the stop on the calibration top.

U916 The shielding provides full shiciding in all directions at all times when the source is in the "off" position. Position indicating lights (green = "off", red a "on") at the top of the calibrator shows source position at all times. The "on" light is activated whenever the source is not fully "off".

(4) Remove dosimeters from the calibrator.

(5) Disconnect timer and electrical plug.

.(6) Store in designated location and cover.

g. Read the dosimeter (s) and record in the Reading After l Exposure column.

h. Determine the net exposure. l

, 1. Determine the efficiency by dividing the net exposure (J ) by the calculated exposure.

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j. The dosimeter indication should be within -10%, t10% of

,the calculated exposure. If it is not, it is probably defective. Perform another complete exposure on the dosimeter.

k. If the dosimeter does not iJet the -10%, t10% criteria the second time, place the dosimeter in a " Fall Cal" box for return to a vendor or disposal.

UQIE Dosimeters are leak-tested and calibrated twice annually, usually once every six months.

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1. Handle dosimeter with care. These instruments are delicate and expensive. .-

2. Clean optical eyepiece of dosimeter with tissue paper as O often as required. Also visually inspect its physical condition.

3. Check dosimeters for both loose and fixed contamination according to the following schedule:

a. Dosimeters in use: Check as often as dictated by the possibility of their becoming contaminated.

b. General dosimeters in dispensers: Check on a routine weekly basis,

c. All dosimeters: Check just prior to their charge-leakage test and calibration.

d. Immediately replace any personnel or general dosimeter found to be contaminated with an equivalent dosimeter from stock.  !

e. Decontaminate and clean dosimeters as necessary by removing the clip and washing both the barrel and clip with soap and water. Observe applicable radiological safety practices and rules. Exercise care, particularly with the charging end of the dosimeter.

f. Immediately replace dosimeters when found defective.

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H. E. Well_G9WD11r._S nism PROCEDURE TITLE

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RESPONSIBLE SECTION GAFETY RELATED ( X) ,

NON-GAFETY RELATED ( )

.. ... . ......___......... 3 ................m. . . . . . . . . . . . . . . . .........

APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER

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(See back f o r- Safety Evaluation if required).

Non-Safety Related ( )

PREEENT STATUS: Safety Related (

) Yes to jk7b The above Safety /Non-Safeiy Status has changed ( L marled up copy of procedure to this form.

Attach PEASCN FOR R DUEST: d Yo cG Ybe .s n >!a 2 l Y? Frb' Nb U

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- E. I. HATCH NUCLEAR PLANT HNP-8154 See Title Page aevisaw wo

^ 1 See Title Page 1 of 23 H. P. WELL COUNTER SYSTEM A. PURPOSE To provide operating and calibration instructions for use of the ORTEC modular single channel analyzer to obtain accurate analyses of radio-iodine counting.

B. SAFETY Observe Radiation Protection Procedures C. REFERENCES

1. Ortec Operating and Service Manuals

a. Single Channel Analyzer - Model 550, TDC #2044 M ,

b. Counter - Model 770, TDC #2059 M *

c. Timer - Model 719, TDC #2061 M

d. Amplifier - Model 485, TDC #2045 M

e. High Voltage Power Supply - Model 456, TDC #2055 M

f. Nim-bin and Power Supply - Model 401A, TDC #2039 M D. STANDARDS

1. I-131 source .6 to .2 uci

2. Ba-133 source .25 uci

3. Co-57 source

4. Cd-109 source E. DESCRIPTION OF INSTRUMENT The H. P. well counter system is assembled from modular l components as listed in C.1 placed in Nim-bin (C.1.f), a sodium iodide crystal placed on the photomultiplier base to the preamplifier. Radioactive gamma decay is sensed through the sodium iodide crystal and photomultiplier, the electrical signal i is amplified and converted to a digital readout over a timed l g3 interval. l G

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GeorgiaPower 2 of 23 F. DESCRIPTION OF CONTROLS The controls are listed and described, by module, as assembled left to right in the nim-bin.

1. Single Channel Analyzer

a. Window or Upper Level - A 10-turn potentiometer, used to determine the window width (when the toggle switch is in the Window position) or the upper level threshold (when the toggle switch is in the Normal or Integral position).

b. Lower Level - A 10-turn potentiometer adjustable from 20 mv to 10.02 volts. When the rear panel LL Ref switch is set on Int., determines the threshold foq the Lower Levci Discriminator.

c. Integral / Normal / Window - A 3 position locking togglh switch which selects the integral mode of operation'or either of two types of differential single channel modes of operation.

(1) Integral - LL and UL are independently adjustable (O to +10V) and UL response is ignored for an SCA output.

(2) Normal -LL and UL are independently adjustable (O to +10V) and differential mode is effective.

(3) Window - LL sets baseline level (O to +10V) and UL sets window width (O to +1V) and differential mode is effective.

d. LL Ref Mode - Rear panel toggle switch which selects front panel LL control or voltage signal supplied through rear panel LL Ref connector as LL threshold.

2. Counter

a. Readout Display - A direct reading 6-digit display.

b. Overflow - A lamp which is illuminated from first readout overflow until reset.

c. Display Test - A pushbutton switch. When depressed, I the readout display will read 888888 to verify that all l \ elements of all six digits are illuminating. This test

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l does not erase the reading or alter sample counting l which may be in progress.

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d. Master / Slave / Normal - A 3 position toggle switch selects functional module control when the module is in

_a printing loop.

e. Discriminator - A single-turn potentiometer, used to set the discrimination level for the positive input signal from O.1 to 10 volts.

f. Reset - A pushbutton switch. When pushed and released, resets readout display and internal logic to en initial condition.

g. Count-Stop - A toggle switch. In UP position, unit is in counting mode; in DOWN position, unit is in non-counting mode.

h. Gate - An LED indicator lamp to the right of the -

count-stop switch is illuminated when the unit is in counting mode.

3. Timer

()

a. Preset - A 4 position switch, which with the multiplier switch, selects the number of time base intervals (see c below) over which the counting process will be made.

Settings are 1, 2, 4, and 8.

b. Multiplier - A 5-position switch. Selects the decade multiplier factor to modify the Preset switch and determine the number of preset counting time

. intervals. Settings are 1, 10, 100, 1000, and 10,000.

c. Time Base - A 3 position slide switch. Used to select the time intervals to be counted. With the switch in the right position, an internal source of 0.1 second time intervals will be counted. With the switch in the left position, an internal source of 0.01 minute time intervals will be counted. With the switch in the middle (External) position, the time intervals

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furnished through the External Input connector will be counted.

NOTE To determine actual counting time, l multiply a, b, and c settings. For i example, settings of 2, 100, and gs left will give an actual counting

( time of 200 x 0.01 minutes or 2.00 minutes. Similarly, settings of l

8, 1000, and 0.1 second will give g a an actual counting time of 800 .

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d. Start - a pushbutton switch. When pushed, initiates the synchronizing process and the following timing

-interval.

e. Stop - A pushbutton switch. When pushed, stops and inhibits the counting interval, even though interval has been completed.

f. Interval - A lamp which is illuminated during each preset counting interval.

4. Amplifier

a. Coarse Gain - A rotary switch with 6 positions of X2, X4, X8, X16, X32, and X64 gain.

b. Fine Gain - A single turn rotary potentiometer selectable for factors of X3 through X10. ,

c. P-Z Trim - A slot-head screwdriver - adjustable potentiometer to adjust the pole-zero-cancellation network for varying preamplifier decay times.

O d. POS-NEG - A toggle switch used to select compatibility with either positive or negative input signals from the preamplifier.

e. UNIPCLAR-BIPOLAR - A toggle switch used to select either unipolar or bipolar output pulses.

5.- High Voltage Power Supply

a. Front Panel (1) Meter - zero-center indicating meter, shows the polarity and approximate kilovolts of the output.

(2) Output Level - Determined by setting three dials located vertically below the meter. Output level

, is the sum of the three settings. The top dial is ,

a 6-position switch with settings of O, 500, 1000, l 1500, 2000, and 2500 volts. The middle dial is a 5-position switch with settings of O, 100, 200, i 300, and 400 volts. The bottom dial is a 10 turn potentiometer with a range of O to 100 volts (10 volts per turn).

(3) Power-Off - A toggle switch, when power cable is k'_')s plugged into an appropriate source and the switch is in the UP position, the High Voltage Power Supply is energized and the indicator lamp is illuminated. Ter c 2

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b. Rear Panel

-(1) Polarity - A slot-head switch. Adjustable with a screwdriver. Selects either positive or negative polarity of the output.

NOTE Do not change polarity while the power is on. High Voltage meter must read zero.

(2) Control - A slide switch. Used to select the reference source for the output voltage. With switch in the left position, the front panel controls select the output voltage and the '

polarity (1 above) is used to select either polarity. With switch in the right position, output voltage is proportional to reference input. .

(3) Two 1.5 amp fuses are located on the rear panel,

_ one of each side of the input power line.

6. NIM-BIN and Power Supply The power supply is factory assembled in the NIM-BIN. The NIM-BIN becomes the cabinet for the other 5 modules. Toe NIM-BIN itself has no controls. The power supply controls are as follows.

a. Front Panel (1) Power On-Off - A toggle switch. In the UP position, the unit is energized and an indicator

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lamp is illuminated. In the DOWN position, the unit is not energized and the indicator lamp is out.

(2) Temp - An indicator lamp which is lighted when the

, internal temperature rises to within 20 degrees C of the maximum safe operating temperature.

b. Rear Panel Power-Selector Switch - A slide switet. is located on the rear panel for selecting 110 or 220 volt inputs.

7. Sodium Iodide Detector and Photomultiplier Base Potentiometer - A single turn locking potentiometer used for adjustment of photomultiplier tube grid potential. '

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See Title Paas i G. OPERATION OF It9TRUMENT

1. Verily power cables for power supply and HV Power supply are connected to grounded 115 volt line receptacles.

2. Verify cables from photomultiplier tube are properly connected.

3. Energize power supply and HV power supply (switches in UP position). Verify system is energized by checking the indicator lamps.

NOTE Allow system to warm up for at least 60 minutes. -

4. Verify the well contains no sample or standard. Move door over well. .-

5. Set controls.

NOTE Module control settings are. based on data obtained from sections C and H of this procedure. Initial settings given below are to be used as guidelines only and may change from time to time.

a. Single Channel Analyzer (1) Window of Upper Level - 10 (2) Lower Level - 130 (3) Integral / Window / Normal - Normal

b. ' Counter (1) Discriminator - 4.0 volts (2) Count Switch - Up (3) Reset button - depress (readout should be zero)

() (4) Display Test Button - Depress (readout should show six 8s while button is depressed and one zero when button is released.) '

it . . l (5) Master / Slave / Normal - Normal *

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c. Timer

-(1) Set timer to desired time by setting Preset, Multiplier, and Time Base. A ten minute time would be as follows:

(a) Preset - 1 (b) Multiplier - 1000 (c) Time Base - Switch in left pos'ition (0.01 min.)

d. Amplifier (1) Coarse Gain - 32 .

(2) Fine Gain - 8.5 , ,

(3) Input - Positive (4) Polarity - Bipolar O e. High Voltage Power Supply (1) Top switch at 500 (2) Middle switch at 300 (3) Bottom switch at 7.00 (4) Meter at top of unit should indicate less than 1 on the right (positive) side of zero.

6. Daily Background Count

a. After system is properly warmed up, set timer controls for ten minutes and depress Reset button and Start button. Interval lamp on timer should light.

b. Observe and record background count on Data Package 1.

If count rate is excessive (typically, 40 to 100 cpm is normal), instrument may not be functioning properly. l If out of tolerance, notify H. P. Foreman.

7. Daily Calibration

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a. Insert the Ba-133 charcoal cartridge calibration standard and count for four minutes as in Step G.6.a.

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b. Observe and record count on Data Package 1. If instrument is within i 1% of expected reading, it is

' functioning properly. If out of tolerance, notify H.P.

Foreman.

NOTE If the system is out of tolerance for 3 consecutive calibrations, a new chi-square should be completed.

c. Press Display Test button on counter. The readout should display six 8s. If it does, check column on Data Package 1. If not, notify H.P. Foreman.

8. Sample Count .

a. Insert radio-iodine charcoal cartridge to be counted in the well counter and set timer for desired count time (normally 10 minutes), depress Reset and then Start pushbutton.

() b. Record the gross counts, counting time, background count rate, and efficiency on the appropriate data package for Unit 1 or Unit 2 as appropriate.

H. CALIBRATION OF INSTRUMENT

1. High Voltage Plateau (Annually or more often as deemed necessary by H.P. Foreman)

a. Place Ba-133 calibration source in well counter.

b. Count source for one minute intervals between voltages

. of 700 to 1100 volts, advancing voltage controls by 25 l volts after each count.

c. Record data on Data Package 2.

d. Set operating voltage at optimum count rate as indicated by data.

l-l e. If optimum voltage differs from previous setting by more than 10 volts, inform H. P. foreman.

2. Efficiency Determination (Annually or more often as deemed necessary by H. P. foreman)

a. Place the I-131 calibration source in well counter.

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b. Count source for four minutes and record results on Data Package 3.

c. _Obtain a background count rate and record on Data Package 3.

d. Compute actual activity in uci and actual dpm of the calibration source and record the results on Data Package 3.

e. Calculate the efficiency factor for the source by dividing the net epm by the known dpm of the standard. l

3. Chi-square Test (Gt;rterly)

a. Place the Ba-133 calibration source in well counter.

b. Count source for one minute duration twenty times and record results on Data Package 4.

c. Calculate chi-square. If result is between 7 and 35, the instrument is functioning properly. If not, investigate the possibility of malfunction.

O

d. Calculate ii + 1% of n and M - 1% of n. Enter data on Data Package 4 and Data Package 1.

e. If instrument does not pass chi-square test, notify H.P. foreman and initiate repairs.

4. Annual Recalibration Gain and lower level discriminator set points.

NOTE The well counter system must be calibrated for a gain and diccriminator bias at 32 Kev.

a. Perform step H.1.

b. 'Make a series of count rate determinations for isotope standards using the information provided in Table 1 below and as follows: Record on Data Package 5.

TABLE 1 l

Coarse Gain Fine Ga in Lower Level Disc.

l 1 l ([)' Cobalt 57 32 8.5 10.00 - 5.00 l (.122 Mev) 16 8.5 6.0 - 2.00 l Cadmium 109 32 8.5 8.50. ,3.00 '

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(.088 Mev) 16 8.5 ;U!?4.00 ~1.00

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(1)- Set the Coarse Gain and Fine Gain on the first settings in Table 1.

(2) Set the count time for one (1) minute.

(3) Place tF? radioactive standard in the well cave.

(4) Set the Lower Level Discriminator to the maximum in Table 1.

(5) Count the standard for one minute and record data on Data Package 2.

(6) Repeat steps H.4.b.(1) thru H.4.b.(5), each time decreasing the discriminator setting by a maximum of 0.5 until the minimum setting in Table 1 is reached. ,

NOTE .

Always approach the discriminator setpoint from a counterclockwise direction when O' changing the setting.

(7) Repeat steps H.4.b.(1) thru H.*.b.(6) but with the other gain settings in Table 1.

(8) Repeat steps H.4.b.(1) thru H.4.b.(7) until all standards have been counted.

(9) Plot data on 5 cycle semi-log paper for lower level discriminator setting (linear) vs count rate (log) for each gain setting. Draw smooth curve through points.

(a) Construct straight extension lines from the nearly horizontal upper and lower arms of the curve.

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(b) Determine the recorded counts at the two points where the curve breaks.

(c) Subtract lower reading from higher reading and divide by 2. Add the result to the lower 4

reading.

(d) Locate result of step H.4.b.(9)(c) on the log

()

• scale axis. Construct horizontal dashed line through this point and extend to the curve.

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(f) Read lower level discriminator value indicated by vertical dashed line. )

(g) Label values of dashed lines and the two break points.

c. Make an energy vs discriminator plot by performing the following: )

(1) On linear graph paper, label shorter scale Energy (MeV), longer scale discriminator setting. En'ergy scale range is O to O.7 in O.1 increments. The discriminator scale range is O to 10. ,

(2) Plot gamma energy of the standard source versus the respective discriminator settings determined

() in step (9)(c).

(3) Connect the points determined with the same coarse gain setting by a straight line and extend the line in both directions. The lines drawn should meet near the origin of the graph.

(4) Locate energy level of 0.032 MeV on the energy scale. Construct horizontal dashed line through this point and extend past both straight line curves.

(5) Determine and label discriminator setting readings for the two points where the dashed line in step H.4.c.(4) intersects each straight line curve.

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Enter these on Data Package as the Daily Calibration Count Rate Guides.

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, COMPLETED BY:

DATE COMPLETED:___

I HAVE REVIEWED THIS DATA PACKAGE FOR COrPLETEE SS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HrP-830.

ACCEPTABLE LNACCEPTABLE REVIEED BY:

, DATE FEVIEED:

REMARKS:

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t GEORGIA POWER COMPANY HATCH NUCLEAR PLANT t (3

s_) PROCEDURE Em_ er2g enc % Call Li_s_t_______________

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PROCEDURE NUMBER

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R55PONSIDL S5CTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

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APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANA R p,_ - - -_ ._____ _ - - _ ___-_.-_.__- .-- - --

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CEVIS f GNI CHANGEG :*GCE OF CF ERATION GR INTENT AG DESCRIGEO IN FGAR:

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) Yes (K) No CHANGE INbOLVEG:

( ) An unrevievent % f ety Guastion ( ) Tech.Specc. ( M') Neither

( Go es t> a ck f r; r- Niety Osalua tion if required).

PREEDIT STATUS: CMety Re lated (K) Non-Gafety Related ( )

The abovo Saf ety n.lon-Ca re l y Sta tus has changed ( ) Yes to __.,__ ___

Attach marked up copy of procedure to this form.

nEAcca roR rEcuCsT: _ _ _ _ _ _ . _ _ - - _ _ _ _ __- _ ____ .__________

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E. I. HATCH NUCLEAR PLANT HNP-4862 See Title Page *vis o~ ~o om See Title Page GeorgiaPower d ~ ~o 1 of 1 EMERGENCY CALL LIST A. PURPOSE To describe the requirements for distribution and updating of an emergency call list for Plant Hatch.

B. FREGUENCY OF UPDATE AND DISTRIBUTION At least quarterly, in the first month of each quarter.

C. RESPONSIBILITY The Health Physics Superintendent is responsible for updating the call list at least quarterly.

D. DISTRIBUTION A distribution list is attached to each copy of the call list.

Each person or title having responsibility for notification in the call list will be issued a copy.

E. REVIEW The Health Physics Superintendent will review each updated call l list prior to. distribution.

F. MINOR CHANGES Minor changes (i.e. telephone numbers, title changes, and name changes), to the Call List may be made by the Health Physics Superintendent between quarterly updates by written notification to persons on the distribution list.

O massal set

Georgb Power Company Post Office B x 439 Baxley, Georgb 31513 Telephone 912 367-7781 912 537-9444 ,

z Edwin 1. Hatch Nuclear Plant October 31, 1983 GM--83-1962 ,

t PLANT E.I. HATCH Emergency Implementing Procedures Docket Nos. 50-321/50-366 United States Nuclear Regulatory Commission Director of Nuclear Reactor Regulation Washington, DC 20555 Gentlemen:

Pursuant to Appendix E,Section V of 10 CFR 50, please find enclosed ten (10) copies of the latest revisions to the Plant E.I. Hatch Emergency procedures. Three (3) copies of these procedures are also being forwarded to the Region II office in Atlanta, Georgia.

I

~ .-

d H.C. Nix General Manager, Plant Hatch HCN/ECS/ car XC: U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 l

file l

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<, g oq(o g, UNITED STATES E o NUCLEAR REGULATORY COMMISSION

$  ; WASHINGTON. D. C. 20555

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%, July 9, 1984 I 50-321/366 Hatch MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Division of Rules and Records, ADM

SUBJECT:

REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be m3 d e publicl available.

/ '/

. M. Felton, Director ivision of Rules and Recor 'gg '

Office of Administration

Attachment:

As stated l

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