ML20081B673
| ML20081B673 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/18/1984 |
| From: | Nix H, Sorrell E GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GM-84-53, PROC-840118, NUDOCS 8403090282 | |
| Download: ML20081B673 (46) | |
Text
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UNITED STATES 8' n NUCLEAR REGULATORY COMMISSION g :: E , WASHING TON, D. C. 20555 8 11 arch 7,1983
%, * . . . 3 50-321/366 Ilatch MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Divison of Rules and Records, ADM
SUBJECT:
REVIEW OF llTILITY EMERGENCY PLAN DOCUMENTATION The submitter of the attached document has expressed no desire to withhold any information contained therein. Therefore, this material may now be made publicly available.
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J. M. Felton, Director Division of Rules and Records Office of Administration
Attachment:
As stated l 8403090282y4M1b PDR ADOCK PDR F
t 8 Georg!3 Power Compiny Post Offic) Box 442 , Baxley, Georgia 31513 - Telephone 912 367-7781 912 537-9444 h Het h Plet Georgia Power the southem eiectnc system
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January 18, 1984 GM-84-53 PLANT E.I. HATCH bnergency Implementing Procedures , Docket Nos. 50-321/50-366 United States Nuclear Regulatory Commission Director of Nuclear Reactor Regulation Washington, DC 20555 Gentlemen: Pureuant 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.
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Eberline Model PCM-i Po'tal Monitor PROCEDURE TITLE HNP-8161 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) _____p _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ . _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ APPROVED APPROVED REV. DESCRIPTION DEPT. GEbE_1AL DATE MANAGER MANAGER ______4 . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______ _______v___,__,__.._ _..________ W O New Procedure + _____-. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ __1 d _ _ _ . _ _ _ _ _ . __ _ _ _ . . _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________u.________ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .______________a.________
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PROCEDURE RETTEV REQUEST FOR NEW PROCEDURES
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EIGNATURE DATE DEPARTMENT MANAGER APPROVAL : MkM AI' '-- //6/8M SIGNATURE DATE -
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( d SAFETY RELATED ; ( ) NON-SAFETY RELATED IF SAFETT RELATED. QA REVIEW : [#M f /d /[M/W
/ / / 4 / T4 SIGNA [RE DATE COPY OF PROCEDURE g BE ATTACHED TO THIS FORM!
REVIEW SY DOCUMENT CONTROL CLERK : '// N u r//t [7(C ^. / / 6- / f </. SIGNATURE DATE . HKASON FOR REQUEST : Tc; 7elt t l el > e __ o r. e) 3 c t A - N 'o v t Cl ev b ( A k $3 A b N Dilar e tu't R ( ,* . : .L t . r/ w
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( ) F90CEDURE RETISION DOES TEIS DOCUMENT CEANGE THE MODE OF OPERATION OR INTENT AS DESCRIEED IN l THE FSAtt ( ) YES ; (d No DOCUMENT INVOLVES : ( ) AN UNEEVIEWED SAFETT QUESTION ( ) TECH. SPECS.
, ( d NEITHER DOES TER IMPLEMINTATION OF THIS DOCURINT REFEESENT AN UNEEVIEWED SAFETY QUESTION : ( ) TER ; M NO GIVE THE RASIS FOR FOR THE DETEREIMATION OF insETHER OR NOT THE THE IMPLEMENTATION OF THIS DOCUMENT REPRESENTE AN INIEEVIEdED SAFITY: QUESTION Tiu im ale .>, <, v ts h ;~ d 4h. % Mse eStut e -
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8 . SHEET 0F 7 3fFETT EYALU& TION O . , (CONTINVED) THE IMPLEMENTATION OF THIS DOCUMENT (DOES / Q T) AN CONSTIT.IE UNEEVIEWED.. SAFETY QUESTION AS EEFLAINED BELOW: 1. THE FROSABILITY OF OCCURRENCE OE THE CONS $QUENCES IDENT 0E MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY (ARE NOT) INCREASED AB0VE TMOSE PREVIOUSLY ANALYZED IN THE FSAE DUE TO 'LEMENTATION OF THIS DOCUMENT BECAUSE:
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- 3. THE MARCIN OF SAFETY DEFINED IN THE BASIS FOR ANT TECHNICAL EPECIFICATION DOCUMENT BECAUSE: (IS / IS NOT) REDUCED DUE TO TME IMPLEMENTATION OF THIS
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- See Title Page GeorgiaPbwer 1 o,1S gggRLIPE MODEL PCM-1 PORTAL MONITQR
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A. PURPOSE To ensure that the instrument is calibrated properly and to provido cporation guides to the user. ,
- 8. SAFETY Observe Radiation Protection procedure.
C. ggEEEEXEH TDC-6002M, Model PCM-1 Technical Manual D. TggT gGUIPPENT
- 1. P-10 Gas. (10% methane, 90% argon) ..
- 2. Electrostatic voltmeter .
- 3. Assorted check sources E. QgEqRIP_ TION - GEN _ggL%
The Eberline Personnel Contamination Monitor, Model PCM-1, is a microprocessor-based radiation detection system which provides a quick indication of beta-ganna contamination on personnel. The microcomputer provides a sophisticated and flexible means of acquiring and manipulating data and presenting operational conditions and alarms on the alphanumeric gas-discharge display and status indicator lights. The PCM-1 has an operate and a test mode. While in the operate mode the monitor will run in its main routine, measuring and storing background for all channels, checking for high background alarm levels, low or high count failure, and low gas pressure conditions until the ultrasonic motion sensor detects the movement of a person into the monitor. This causes the personnel monitoring routine to be executed. This routine checks all channels for high activity alarm conditiovs with automatic background subtraction, according to the protocol of one of the three operating modes in which the monitor has been set to operate. The test mode is used to run detector plateaus, determine counting efficiencies, etc. massa i set
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See Title Page Georgia Pbwer a of 15 The PCM-1 has fifteen (15) independent gas-flow proportional det ect o r~s. Maximum detector sensitivity is achieved through the use of an input preamplifier for each channel which interfaces each detector to the microcomputer. Each channel has adjustable gain and discriminator to permit the operating point to be optimized for each detector. Each group of five channels has an independently adjustable high voltage power supply, with a ncminal range of 500 to 2500 Vdc. The outputs from the fifteen'discriminators are fed to a counter board, and then to a central processing unit (CPU) module which includes an Intel 8085 microprocessor, memory, and input / output lines. A non-volatile memory is used to preserve system parameters during periods of power outage. All electronics for the PCM-1 are located in the rear of the unit requiring no exterital cabling or additional installation. . Electronics components are mounted on plug-in modules providing easy access. Troubleshooting and maintenance are facilitated,by the compute _a's systems diagnostics routine which self-tests the display, keyboard, lights and memory. F. DESCRIPTION _OF CONTROLS AND INDICATORS
- 1. External
- a. Ultrasonic sensing unit; Senses ones approach to the monitor and causes background counting to stop and the display to read STEP UP--INSERT RIGHT ARM, accompanied by a short beep.
- b. Alphanumeric display; Indicates appropriate messages to users and operating conditions and parameters when the monttor is in the test mode.
- c. Display lights; Alarm, Counting, Ready and Trouble lights that assist in indicating appropriate messages to users.
- d. Photoelectric sensor; Indicates to the monitor that it is occupied or if the occupant has excited the monitor before the count cycle has been completed.
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- e. Operate / Test switch; A key operated switch that controls the operation of the monitor between the normal operation mode and its test and maintenance routines.
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- g. Ala t t.; acknowledge; not functional.
- 2. Internal
- a. Power Switch; provides on-off capabilities for 110 volt AC power.
- b. Flow gauges; (3) indicate inlet flow rates in cc/ minute for flow groups A, B, & C.
- c. Pressure Regulators; (2) a dual guage fully adjustable control for the P-10 gas used in the detectors. They are mounted on type 1A gas cylinders and are connected to the instrument by a 3/16" id Tygon. Tubing. .
- d. FU Switches; (3) switches that provide on-off ' ..
capabilities for each of the three high voltage sections.
- e. HU Adjust; (3) potentiometers that provide a' reference voltage to each of the high voltage power supplies enabling control of the HU setting.
G. OPERATION OF INSTRUMENT
- 1. Initial Set-up
- a. P-10 gas hook up: Install the P-10 gas bottles in both sides (bottle #1 is on the left, bottle #2 is on the right) connect the pressure regulators on bottles 1&2 and connect the 3/16" tygon tubing to the outlet side of the regulators.
- b. Cas Flow and Pressure Adjust: Adjust the pressure regulaters to 5 psig and the flow regulator to 50cc/ minute.
CAUTIQN Do not exceed 50 cc/ minute or 5 psig or damage to the detectors may occur.
- c. Initial Pur]e: Allow approximately 4 to 5 hours purge time at 50cc/ minute to insure that the system is completely purged of outside air and moisture. The flow rate can then be adjusted to 25cc/ minute for normal operation. ,
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See Title Page Georgia Pbwer . ,, is ds Power Connection: The instrument uses 110 volt AC
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~ power. It may be plugged and turned on at this time.
l 2. Normal Use l OPERATE vs. TEST If the OPERATE / TEST switch next to the keyboard is set to OPERATE, the monitor will run in its main routine, measuring and storing background for all channG1s, checking for high background alarm levels, low count failure, and low gas pressure conditions until the actuation of sensing switches calls the personnel monitoring routine. This routine causes all channels to check for high activity alarm conditions with automatic background subtraction, according to the protocol of one of the three operating modes in which the monitor has been set to operate: Mode 1 Preset All Mode 2 Maximum Sensitivity Mode 3 Minimum Count Time "" If the OPERATE / TEST switch Si is set to TEST, the monitor runs in its test and maintenance routines. In this mode, the keyboard is active and the other sensors are inactive. Background measurements and related computations are suspended while in TEST, and all parameters are available for display and/or modification as listed in Table II-1. The display prompts the cperator with the name of the parameter list ready for examination or, within a list, the name of the variable being displayed and its present value. The keyboard protocol is such that touching the "+" key causes an increment to the next item, the " " key causes a decrement to the prior item and the ENTER key causes entry to that Fist. EDIT and ENTER allow modification of appropriate items as indicated by E in the table.
- a. Routine Monitoring (OPERATE)
The ultrasonic unit will sense an individuals approach to the monitor. All background counting will cease and the display will read STEP UP--INSERT RIGHT ARM. The individual then inserting their arm in the detector cavity will break a light beam and the monitor will initiate counting. The display will read COUNTING RICHT SIDE for the duration of the specified counting time. If no alarm levels are exceeded, the unit Lseos massa i ae t I
arpaovg nuackoum suo w -sisi See Title Page E. l. HATCH NUCLEAR PLANT . .. ,,o om - O See Title Page h0 E 5 of 15 . -_- and displays RIGHT SIDE OK--INSERT LEFT ARM. The
display will indicate COUNTING LEFT SIDE when the left arm interrupts the light beam in the detector cavity.
AT the end of the counting time the unit displays COUNT COPPLETE, YOU MAY PASS, accompanied by a chime if no alarm levels are exceeded. Contamination in excess of alarm levels is signaled at the end of Right or Left side counting, or both, as appropriate by the alarm sonalert and display messages indicating the contaminated area as ALARM: ZONE 1--ZONE 2--ZONE 3--ETC. Premature arm withdrawal will cause the alarm sonalert to sound and COUNT INCOPPLETE ** RECOUNT **to be displayed. Reinsertion restarts the count. v. h, G 1 massa i se t
amocrov e w 71,3,p.,, E. l. HATCH NUCLEAR PLANT 7-816* e Title Page GeorgiaPower d '"' ~ s o, is A. TEST MODE TA8bE 1 TEST MCSE E MU Operating Mode Pai ameter List l Mode 1 Mode 2 Mode 3 Default and Item Preset All Max. Sens. Min Ct Time Value _ DISPLAY SYSTEM PARAETERS Identification and type H H H - Program Name and Version H H H -
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Mode (1.2 or 3) E E E 2 Sigma Factor (SF) E E E 3.V-Weighting Factor (W) E E E 10
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Alam Hold Time (seconds) E E E 1 Count Time, Test (seconds) E E E 1 Count Time (T, seconds) E E C 1 Min. Count Time (Mode 1 only) C NA NA - Max. Count Time (Mode 3 only) NA NA E 1 Units. E E E Cps DISPLAY CHANNEL PARAETERS 7ene or Channel Identification
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Average Background cps (R ) N N N ~ B Alam Setting cps (RA) E NA E 1000 (it>de 1 and 3 only)
- Min. Alarm Limit (Mode 1 only) C NA NA -
Max. Alam Limit (Mode 2 only) NA E NA 1000 Alam Level (Mode 2 only) NA C NA - (Repeats for each zone or channel) 1 l massa i set i t I
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See Title Page GeorgiaPower y ,, is 4, Te8LE 1_19,QNT) Operating Mode Parameter List Nde 1 Mode 2 Mode 3 Default and Item Preset All Max. Sens. Min Ct Time Value COUNT RATE MODE Zone or Channel cps M M M - (Repeats for each zone or channel) DISPLAY TROUBLE LIST (available only if trouble light is on) Zone or Channel Identification High Background .M M M . - High Count Fail M M M - Low Count Fail M M M T Bottle 1 Empty . M M M - Bottle 2 Empty M M M - Failure ** Out of Gas! M M M - SYSTEMS DIAGNOSTICS Display Test A A A - Keyboard Test OI O! OI - Alann Ack A A A - Light Test A A A - Chime Test - A A A - Read / Write Memory Test A A A - Program Memory Test A A A - USAGE Personnel Counter / Elapsed Time M M M - RESET Re-initialize system parameters E E E - and background averages LEGEND H - Fixed by hardware /firmware configuration E - Edit / Enter via keyboard - (value must be between 0.25 and 600) C - Computed yariaole M - Measured variable . NA - Not available A - Auto sequence asseaiset O! - Operator Input f
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., (1) Operating Mode (a) Preset All, Mode 1 In this mode the alarm setpoint Rf for each channel, and the counting time T and sigma factor SF for all channels, are entered via the keyboard. A personnel alarm occurs if the count N in the counting time T is such that N JL R g TtR g T The high background alarm occurs if SF y R g T .3, R 4 T (b) Maximum Sensitivity, Mode 2 ,
In this made the maximum alarm limit R 4puh* counting time T, and SF are entered via tre' keyboard. Each time the background is updated a new alarm setting RA is computed for each channel. R 4 = SF fRg/T A personnel alarm occurs if N SL R gT + Rg T The high background alarm occurs if
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_ A A mAA (c) Minimum Count Time, Mode 3 In this mode, SF and maximum count time Tmagare entered. RA ,Each time background is updated a new count time is computed from GL T= (SF) R8/(R g ) 3, based on the channel with the highest Rg Personnel alarm occurs if N d> Rg T t Rg T The high background alarm, occurs if Tggg i
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" -8161 See Title Page E. I. HATCH NUCLEAR PLANT E,,uw e o ,, _
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(2)- Simga Factor (SF): A user entered variable that g" is a multiplier of the background standard deviation used in determining alarm setpoints. (a) Mode 1, the SF as used in determining the alarm setpoint for the high background alarm l when j F Rg T 1R A T the alarm will occur (b) Mode 2, the SF is used in determining the personnel alarm setpoint - RA where R /T 4=SF{R (c) Mode 3; the SF is used in determining the minimum count time, where the alarm setpoint RA is preset and the highest ave' rage . backg_roundR6gis (SF) used where count time T =.~ RB/(Rg ) NOTE The value of the Sigma Factor will vary based on which of the 3 modes of operation is to be used. Determine values for the variable repre-sented in the formulas based on the' location and operating conditions of the monitor. Use these to arrive at an acceptable value for the SF that will produce the most sensitive operation with the least amount of false alarms. (3) Weighting Factor (W): A number that is used in
- compensating for background variation. An increase in the W value results in an increased confidence level for false alarms, but at the same time it increases the amount of time it takes to
- respond to real changes in the ambient background. A value between 10 and 20 is recommended.
(4) Alarm Hold Time: The length of time the sonar alert and the display module remain activated during an alarm condition. (Operator determined 1 to 9 seconds). (5) Count Time, Test: The length of time that the ( ~ system counts in the " Count Rate" mode, normally j used for source checking individual thennels.
- (Operator determined 1 to 900 seconds).
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.- (6) Count Time (T): (Modes 1 & 2) A predetermined period of time for the count durstion of the background update and the personncl count.
(Operator determined 1 to 10 seconds). (7) Maximum Count Time (Tntaa ); (Mode 3 only) - The maximum amount of counting. time, (T) allowable before a high background al. arm will occur when T A_, Tg. (8) Units: The units displayed can be in seconds or minutes which ever is desired. (9) Alarm Setting (RA ): (Operator determined - Modes 1 and 3). The maximum amount of counts (N) collected before a contamination alarm will occur when N = R4 + Rg . Rg can be solved for given T, Rg,R b ' Z and W. R b is taken to be equal to'Rg as it is the best estimate of Rh- __b_ __h_-Y ______M____ h T T (2W t 1) Z is determined by choosing the desired confidence level that will produce an acceptable false alarm rate, and still maintain the confidence level as high as possible. This determination should be based on the location of the monitor and the conditions under which it is to be used. For 99.9 percent confidence level, F(z) = .999, z = 3.090 _ For 99.0 percent confidence level, F(z) = .990, z = 2.326 For 95.0 percent confidence level, F(z) = .950, z = 1.645 For 90.0 percent confidence level, F(z) = .900, z = 1.282 For 75.0 percent confidence level, F(z) = .750, z = 0.674 For 50.0 percent confidence level, F(z) = .500, z=0 54558 l se t e __ . _ _ _ . - ~ .
i . Amm>g a== ,.o HNP-B161 E. l. HATCH NUCLEAR PLANT See Title page ~ ,.o m ~ P See Ti+1. page GeorgiaPbwer A - 11 af 15
.... (10) Mar Alarm Limit (Rgg,x): (Mode 2) Preset amount
. 5 "- of counts that will cause a '.igh background alarm if the setpoint is exceeded.
Variable Leoend R4 Alarm Setpoint (Limit) R4 Activity Count Rate , Rg Average Background Rb Individual Background Count N Personnel Count SF Sigma Factor T Count Time Tg Maximum Count Time Z Confidence Level Value
- 3. Fail and Trouble Indications
~~
a.- High Background . If the background count rate, Rg , in any zoneFT) should increase to such an extent that it and the e' selected sigma factor, SF, counting time, T, alarm _ level, Rg , max alarm limit, R A ma x , a6d max count
! time, Tmax, relate so as to satisfy the .
inequalities of Section 2.C.2.b., 2.C.2.c., or 2.C.2.d.; the alarm light, trouble light, sonalert, and (CHANNEL DESIGNATION) HIGH BACKGROUND message will be activated for the duration of the alarm hold time. The trouble light will remain lighted when the unit automatically reverts to counting background, but the zone (s) involved will not update background or 4 be capable of further alarm sensing until cleared l - through the DISPLAY TROUBLE LIST section of the test mode mer.u, which lists all the current trouble conditions and zones. After returning to the operate mode, any trouble which persists will cause reactivation of the alarm and message. l 5. High Count Fail i If the 64K count capacity of any zone counter is exceeded during a background count interval, the
! alarm light, trouble light, sonalert, and (CHANNEL DESIGNATION) HIGH COUNT FAIL message are activated. The trouble light will remain on and
- the failed zone will remain inactive until cleared.
l (j as in the ease of the high background alarm. High count fail is more likely to be' caused by l electrical noise than by legitimate counts. massai4et l
I APP *lOVAL P8tOCEDuM NO E. I. HATCH NUCLEAR PLANT " -8161 See Title Page
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can O See Title Page 12 of 15 g c. Low Count Fail , If a zone counter receives no counts within 256 consecutive background counting cycles, a (CHANNEL , DESIGNATION) LOW COUNT FAIL message / alarm is ' activated in a manner identical to the previous l ones. Any counts which occur between background ! counting cycles, during the overhead time of the computer, are not registered in the zone counters.
- d. Loss of Gas Pressure If both gas bottles have pressure when the PCM-1 is first turned on, gas will be drawn from bottle
#1, through ports 2 and 3 of gas bottle select valve V1 (unectuated), to the input flowmeter.
When bottle #1 runs out of gas, pressure switch 52 senses the, loss of pressure, causing the computer to activate the alarm and message BOTTLE #1 EMPTY, , and to actuate V1, drawing gas from bottle #2._., The trouble light will remain on until bottle #1 is replaced. V1 will remain actuated until Bottle
#2 runs out of gas, whereupon Vi switches back to Bottle #1, and the alarm and message BOTTLE #2 EMPTY is activated. If both bottles are out of gas, the alarm and message FAILURE ** OUT OF GAS!
is activated, all counting stops, and the message remains on the display until pressure is restored to either or both pressure sensors.
- e. All Zones Failed If personnel counting is attempted whila all zonas have failed, the display will indicate FAILED, and no count will be attempted.
H. WEEHLY SOURCE CHECK NOTE Due to the frequency of the routing source check, other periodic calibration is unnecessary.
- 1. Observe and record the pressure in bottles 1 & 2 and the l regulated pressures to the instrument. The regulated pressure should be 5 to .5 psig. Adjust if necessary. I i I l 2. Observe and record on Data Package 1 gas ? Low on the gauges
- for both sides. The flow should be 25.1,2.5 cc/ minute. 1 l Adjust if necessary.
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- 3. Esitch the Operate / Test switch to Test. Advance the display t6
- Display Channel Parameters" using the "t" key. Press
" Enter" to gain access to the program list. The display will show the zone identification number. Press " Enter" to gain access to the individual Zone / Channel parameters. Use "t" to step tnrough the list recording the " Average Background" and the " Alarm Level". Continue through the 11 Zone / Channels in the above manner recording the required data. If the instrument is being used in the " Maximum Sensitivity, Mode 2", a.1so record the " Max Alarm" setting.
- 4. Advance the display using the "t" key to the " Count Rate Mode". Press " Enter" to gain access to Zone / Channel #1.
Center the source against the detector screen. Allow 2 count cycles to occur before recording the results of the 2nd count. Continue through all 11 Zone / Channels using the "t" advance recording the data on Data Package 1.
~
S. Dackup to-the " Display System Parameter" list using the ." " key. Press " Enter" to gain access. Press "t" to increment through the list recording the parameters for the '" following: Mode (1, 2, or 3), Sigma Factor, Weighting Factor, Alarm Hold Time, Count Time, Test, and Count Time.
- 6. Return the Operator / Test Switch to Operate. Allow the monitor to background count momentarily. Place the source on Zone #1 while standing in the monitor. Indicate on the data package in the Alarm Acceptable Column whether or not the channel alarms. Step out of the monitor, allow the alarm to clear. Continue through the remaining zones in the above manner.
- 7. Calculate the efficiency for each Zone and Channel completing the Data Package. If the detector efficiency is below 202 it is not acceptable. Replace the detector or initiate repairs to return the efficiency to an acceptable level.
l 1 l meena l se t l
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PROCEDt.RE DATA PACKAGE DOCtJPENT N3: W -8161-1 SERIAL NO: ROO-PFL NO: RTYPE: G15.14 XREF: TOTAL SHEETS: 2 FREQUENCY: - v. CCPFLETED BY: DATE COMPLETED: I HA%E REVIEWED THIS DATA PACKAGE FOR COMPLETE?ESS AND AGAINST ACCEPTANCE CRITERIA IN ACCCRDANCE WITH HNP-830. ACCEPTABLE tJNACCEPTABLE REVIEWED BY:
- DATE REVIEWED:
REMARMS: l l Page 1 of 2 Hre-8161 ROO FIGURE 1 ' Page 1 of 2 S ) massa i se t I
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Source #: Source D P.M. Cas Pressures: 1. PSI Regulator Cas Flow 1. cc/ min
., , 2. PSI Regulator Cas Clow 2. cc/ min Sourc's CPM-BKG Divided By Source D.P.M. X 100 = EFF.
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4 . GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Radiation Work Permit
- - PROCEDURE TITLE HNP-8008 l PRCCEDURE NUMBER l
- l 1
1 Lab 1 RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) _ _ _ _ _ _ ..____________________y________________o_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . , _ _ _ _ _ _ _ _ . APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE PENAGER MANAGER
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5 MEED Y DATE: / //.2 ,fy P!OCJDURE REVISION REOUEST PROCEDURE NO. HNP- [OO _ SHEET 1 OF [ CURRENT RETISIO4 30. /[ REQUESTED ET : $)lY 0)g U f /////90 gIGEATURE DATE . g DEPARTMENT MANAGER APPROVAL : $NM,,- -M / /// /M DATE
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PRESENT STATUS : ( N SAFETI RELATED ; ( ) NON-SAFITY RELATED THE ABOYE SAFETY /50N-SAFETY STATUS MAS CHANCED: ( ) TES; TO LIST ANT APPLICABLE QA TEACEE NUWBER's : /f/'A IP QA TRACER IS APPLICARLE. INDICATE REVIEW ST RBC. COMP. : MARKED-UP COPY OF CURRENT PROCEDURE E SE ATIACHED TO THIS FORN! REVIEW SY DOCUMENT CONTROL CLERE : 'N//2 k/[ID Ndo / / // /M. SIGMATURE DATE REASON FOR REQUEST : 5 i."kr#i J's ? .xN <* W $; A / A fA
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l l l SNEET 1 0F k3 i ! EAFITT EYALUATION TYPE OF DOCUMENT, TO %5tIch THIS ITALUATION APPLIES : ( ) NEW PROCEDUEE ( SOCEDUEE REVISION DOES THIS DOCUMENT CRAIIGE TER N005 0F OPERATION,05 INTENT AS DESCRIBED IN ~ THE FSAEt ( ) TER ; (M NO DOCUMINT INTOLYES : ( NEITNER ( ) AN UNRETIEWED SAFETT QUESTION , ( ) TECN. SPECS. , t DOES THE IMPLEMENTATION OF TEIS DOCUMENT REPERJENT AN UNEEVIEWED SAFETY QUESTICII : ( ) TER ; (M NO GIVE THE RASIS FOR FOR THE DETERMIMATIOli 0F %ARETERE DE NOT THE THE : IMPLEMENTATION OF TNIS DOCUMENT REPESSMNTS AN UIBEEVIEWED SAFETY QUESTI0ll f /1> '+:f,* *) % - P 4'4- A ./ .A
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- 1. THE PEORARILITY OF OCCURRENCE OR THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY (q / ARE NOT) INCREASU ABOVE TNOSE PEEVIOUSLY ANALYZED 15 TER FSAR DUE TO THE IMPLEMENTATION ,.c .
THIS DOCUMENT BBCAUSE: .
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- 2. THE POSSIBILITT OF Ak ACCIDENT OE MALFUNCTION OF A DIFFERENT TYPE THAN c!
ANALYZED IN THE FSAR ( 6 DOES 'ADT) EESULT FROM THE IMPLEMENTATION OF. , THIS-DOCUMENT BECAUSE
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- 3. THE.EARCIN OF SAFETT AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION ( @ IS NOT) REDUCED DUE TO THE IMPLEMENTATION OF THIS DOCUMENT BECAUSE: .
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cpweova PROMovat Peo E. l. HATCH NUCLEAR PLANT HNP-8008 See Title Page a** = we 17 See Title Page 1 of 19 t . RADIATION WORK PERMIT A. PURPOSE To provide instructions for the issuance of and implementation of Radiation Work Permits (RWP). The Radiation Work Permit procedure is designed to pro ide a capability to control and minimize radiation exposure that is received from work performed in radiation areas, high radiation areas, contaminated areas, and airborne radioactivity areas.
- 8. REFERENCES
- 1. 10 C.F.R 20
- 2. Reg. Guide 1.16 ,
- 3. Operators Manual for RWP/1000 TDC 6002 M e.
C. CONDITIONS REGUIRING RADIATION WORK PERMITS (
- 1. Entry into a High Radiation Area, Airborne Radioactivity Area, (as required by Health Physics), or any area posted with a " KEEP OUT - Radiation Work Permit Required" sign.
- 2. Entry to the drywell.
- 3. Maintenance or inspection of contaminated or radioactive equipment in excess of the following limits:
- a. Smearable contamination in excess of 1000 dpm/100 cm2 beta gamma.
NOTE THE HEALTH PHYSICS SUPERVISOR OR DESIGNATED ALTERNATE MAY DETERMINE THAT A R.W.P. IS NOT NECESSARY TO DO INSPECTION OR MAINTENANCE ON EQUIPMENT WITH CONTAMINATION LEVELS IN EXCESS OF 1000 DPM/ LOO CMk IF THE JOB IS OF A NATURE THAT CAUSES NO I MEASURABLE CONTAMINATION TO THE INDIVIDUALS PERFORMING TFE JOB.
- b. Radiation levels at 18 inches in excess of 100 mR/hr or where a whole body exposure of 100 mR/hr is likely.
. 4. Entry into areas with measurable neutron exposure.
#Allll A L 3ET I:
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% -o E. I. HATCH NUCLEAR PLANT .
N -8008 See Title Page at<* * ~o wt 17 See Title Page 2 of 19
- 5. E5tcy into an area of unknown condition.
- 6. Breaching of contaminated or potentially contaminated system.
D. ISSUANCE OF THE RWP (Refer To Ficure 1) . NOTE If a computer generated RWP is to be used, ; see Section L. l
- 1. A supervisor responsible for work requiring an RWP should originate the permit. The originator should enter the date, location, Unit number, job description, and names of personnel expected to require access to the controlled area. He should provide an estimation of man hours required for work in the controlled area and enter his signature in the Requested By section. The RWP should then be' forwarded to the Health Physics Supervisor or his designated alternate.
- 2. The Health Physics Supervisor or his alternate will review the work to be performed for any conditions which may f adversely affect the safety of the plant or personne1 ir.v o lv e d. He will log the required information into the Radiation Work Permit Log Book and enter the permit number from the log book on the RWP. He will determine the appropriate work category using Section K and check off the appropriate block on the RWP.
NOTE The Radiation Work Permit Log Book is a notebook kept in the
. Health Physics office and con-tains Form 3, Radiation Work Permit Log.
The Shift Supervisor may complete the RWP for Health Physics provided the following criteria are met:
- a. A qualified member of the Health Physics staff is not on site, AND
- b. The safety of the plant warrants immediate action which would preclude calling in a Health Physics staff member From off site, OR
- c. Authorization is received from the Health Physics
- Supervisor or his designated alternate. .
# ANNA i 3ET 4
** e w.movc4 NDuM NO HNP-8008 See Title Page E. l. HATCH NUCLEAR PLANT .e.,s %
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See Title Page Georgia Power 3 of 19
- 3. Th.e RWP should be reviewed by the Health Physics staff to determine appropriate actions and controls to be implemented to preclude exceeding exposure limits and to maintain exposures as low as is reasonably achievable (ALARA). Also )
refer to paragraph D.6. The area should be adequately , surveyed prior to entry or be surveyed at the time of entry, l items of protective clothing required should be identified, the type of monitoring required should be specified and exposure records of personnel involved should be reviewed to assure exposures will remain ALARA and within permissible limits.
- 4. Temporary shielding may be specified in order to reduce personnel exposure, to reduce background levels in frisking areas, or to bring radiations levels into compliance with plant and regulatory limits. This type of shielding should only be installed for specific time periods such as:. for the duration of a job, until the next scheduled outage or as directed by plant management. Any shielding specification l must be subjected to the applicable work controls and~ design reviews described in procedures HNP-8 Maintenance Request and HNP-809 Design Change Request.
- 5. The Health Physics Supervisor or designated alternate will review the RWP, enter the estimated Man-rem, expiration date and time, sign the RWP for Health Physics approval, and remove the Health Physics copy for filing. A Man-rem estimate will be made only for RWP's with work area dose rates of ~> 10 Mrem /hr or hot spots h 100 Mrem /hr.
NOTE Estimated Man-rem = Estimated man hours x average dose rate , ' in rems / hour.
- 6. Some Radiation Work Permits require an ALARA evaluation !
prior to issue. As Man-rem estimates increase further ALARA l measures should be considered for implementation. For RWP's with Man-rem estimates of 1 or less, no formal ALARA evaluation is required. RWP's with estimates greater than 1 should be routed to ALARA coordinator for evaluation and processing. An ALARA review should also be performed in I conjunction with any RWP which covers the use of a temporary I radioactive liquid processing system or storage system. The review will determine the possibility of a release to the environment, the precautionary measures to prevent such a release, and the actions necessary to rer.olve a release if it should occur. . l i WAN#4 L SET l . i i I - --. _ , . . . . -
NAL psaOC&Cu% NO E. l. HATCH NUCLEAR PLANT HNP-8008 See Title Page
- v=w =o o^m 17 See Title Page 4 of 19
- 7. Tie. Shift Supervisor will review the RWP for any operations or conditions which may adversely affect the safety of the plaat, enter the approved date and time, and sign the RWP.
The Control Room copy of the RWP will be placed on file in the Control Room. . NOTE Approval to start work will be in effect after the RWP is signed by Health Physics and Shift Supervisor. See D.8 for exception. S. The Supervisor requesting the RWP will review the RWP to > familiarize himself with all requirements. The original RWP will then be talten to the jobsite and posted at the entrance to the jobsite on the clean side of the step-off pad. The supervisor should ensure that the workers have seen the RWP and are aware of its requirements.
- 9. In some situations where the plant needs immediate ettention
. due to en emargency condition, a job may commence prior to ! the sign-off approvals of an R.W.P. by the Health Physics Supervisor or his designated alternate and the Shift Supervisor. The approval to work, in these situations, will be contingent on the policy that a Health Physics person will accompany the workers, will perform the necessary radiation monitoring at the work place to protect the workers, and will give the workers proper instruction in radiation protection. The approval to work will also be contingent on the proper clearance and tegging of the effected equipment by the Shift Supervisor and his staff.
E. ADDITION OF PERSONNEL NAMES TO RWP's While an RWP is in Furce, the addition of names of personnel tc the RWP may be made only on the approval by the Health Physics staff. The work assignment of the person being added must be directly related or associated with the job description on the RWP. When approval is granted, the person's name will be entered on the original RWP at the job site and on the Health Physics copy in the Health Physics Office. F. PERSONNEL RESPONSI9ILITIES
- 1. Supervisor responsible for work under RWP. ,
- a. The supervisor is responsible for assuring that personnel working on the job know the protection requirements. .
# ANN A L SET i;
.i
wescova PROCEDuat No E. I. HATCH NUCLEAR PLANT HNP-8008 See ritle Page cus 17 See Title Page 5 of 19 b2 If Health Physics monitoring is specified on the RWP, the work supervisor will notify Health Physics Staff when the job is to start.
- c. The individual shares a responsibility to promote an awareness of good ALARA practices.
- 2. Personnel performing work
- a. Each person entering and exiting the RWP area must ;
enter data on the RWP Time Record (Figure 2) or on the dosimeter sign in sheet (Form 1), or ensure that this data is entered on the right sign in sheet, (i.e. by H.P. tech.).
- b. Each person must be familiar with all requirements and instructions written on the RWP.
- 3. Health Physics Staff n.
- a. The Health Physics staff will provide radiation surveying and monitoring as required by the RWP.
(,
- b. The Health Physics staff will assist the Supervisor-in-charge and personnel by providing guidance in radiation protection matters to minimize exposure.
- c. The Health Physics staff shares the respons'bility to promote an awareness of good ALARA policies.
G. TERMINATTON OF THE RWP
- 1. When the_ job is to be terminated, the RWP with supplementary sheets attached, must be returned to the Health Physics Office by the Supervisor-in-charge of the work, or his alternate.
- 2. An RWP should be terminated for the following reasons:
- a. Cc pletion of the job.
- b. Cancellation of the job or RWP.
- c. Expiration of the RWP.
(1) Twenty-four hour limit. (2) Time limit as noted on RWP.
#ANU A L SET 1
(
_ -o HNP-8008 See Title Page E. l. HATCH NUCLEAR PLANT %,uw o om 17 See Title Page N 6 of 19 d r, , Change in radiological conditions. NOTE Na further work will be performed , under the RWP once the permit is terminated or expired.
- 3. The Health Physics Supervisor or his alternate will mark the RWP as terminated by checking the appropriate reason for termination, entering the time and date of termination, and signing the RWP in the Terminated By section. He will then mark the time and date terminated in the Radiation Work Permit Log Book.
- 4. Prior to filing in documentation the original copy of the RWP, the Laboratory Supervisor (or alternate) should review the collective exposures associated with work in the contr611ed area. For jobs involving greater than 10 Man-rem collective exposure, or where the actual Man-rem exceeds.ihe estimated Man-rem by 25%, a copy of the RWP data should be
- forwarded to the Alara Coordinator or his designate for an ALARA past job review. When the original copy of the RWP is
(' filed, the Health Physics copy may then be removed and destroyed. H. ROUTINE RADIATION WORK PERMIT
- 1. Jobs that continue for more than 24 hours such as in outages, (i.e. turbine overhauls, etc.) a routine R.W.P. may be issued. Routine RWPs will only be issued to areas with constant H.P. coverage or an H.P. assigned to the control point unless approved so by an H.P. Supervisor or Foreman.
Routine RWPs will have " Routine" written at the top and bottom t6 distinguish them from RWPs that expire after 24 hours. Routine RWPs will be terminated at the end of the month.
- 2. Routine R.W.P.s will be issued according to section D.
except it will be stapled to a folder with dosimeter sign in sheets and a recent survey. Each dosimeter sign in sheet must have the R.W.P. number, date, and work category filled out.
- 3. When airborne conditions exist in the work area involving routine RWPs, the following additional steps will be taken for completion of Form 1-A. Air sampling program will be followed as per HNP-BOl3. Weighted MPC values will be calculated and proper action taken for personnel entries into airborne radioactivity areas. The, action pequirements
~
for weighted MPC values designated below are as fo - s: ! A l SET 4!
.i
- -o E. L HATCH NUCLEAR PLANT HNP-8008 See Title Page ""***
cm 17 See Title Page 7 of 19 a? Less than 0.25 weighted MPC. No control of MPC-HR exposures required.
- b. Greater than 0.25 weighted MPC but less than 1 MPC.
Use respirators and limit exposure to airoorne . radiation as far as practicable or keep track of MPC-hrs in the following manner-(1) Enter the result of the air sample analysis on the MPC-HR log sheet (Form 1A). (2) For each entry calculate the total time in hours, for those individuals who did not receive any respiratory protection for either particulate or iodine or both. MPC-HOUR = MPC fraction x Total time in Hours
- c. Greater than 1 MPC-HR but less than 10 total MPC-HR must be restricted to 35 per week. All steps in 3 4 .
must be followed. ( d. MPC-HR values should be transferred to Form 5'of HNP-SO10 from Form 1-A for each individual on a daily basis. A daily margin of MPC-HR should be supplied to the control point Health Physics techaician, and he will use this to control stay time.
- 4. In areas where work continues 24 hours a day the routine R.W.P. will be left at the control point for the duration of the job. At the end of each shift change the dosimeter sign in sheets will be pulled and new ones attached. The completed dosimeter sign in sheets will be sent to dosimetry for dose _ recording.
- 5. The minimum survey f regt ency for routine R.W.P. s is every 24 hours. The H.P. Supervi sor or Foreman will review all routine R.W.P.s and may set a more frequent survey requirement, according to radiclogical hazards associated with certain areas and the type of work being performed.
Once the survey is performed and is written it is sent to the H.P. office for review and a copy is made. The copy is sent back to the control point to be attached to the routine RWP. I NOTE If a routine R.W.P. is not used, a current radiation survey will _ not be updated and attached until the R.W.P. is put back into effect. gAN#4 L SET 4 . t
E. l. HATCH NUCLEAR PLANT HNP-8008 See Title Page *www ~o
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See Title Page Geo laPower A ~ ~o g of 19 I. BLANKET RADIATION WORK PERMIT
- 1. For certain routine or repetitive work, a Radiation Work Permit Form may be issued to Operations, Herlth Physics and Radiochemistry groups, Plant Supervisors and designated.
inspection and surveillance groups, and marked BLANKET at the top and bottom of the form. The Blanket RWP must be approved by a Shift Supervisor, the Health Physics Supervisor or designated alternate and an appropriate member of supervision of the group to perform the work. The Blanket j RWP will be valid until cancelled by Health Physics or until the last Friday in each month.
. 2. The approved permit is stored in a protective holder in a a book in the Health Physics Office. Exposure rates and a log of personnel doing the work are not entered on the Blanket RWP form. Such records are kept on Form 2, Blanket Radiation J; Perrit Entry Log. After personnel complete work under the l Blanket Permit, the information required on Form 2 MUST BE recorded. .r . ? .
NOTE ( Record information for each RWP area entered. J. REGUIREMENTS FOR ENTRY INTO HIGH RADIATION AREAS
- 1. All personnel entering a High Radiation Area where the field dose rate
- is expected to be greater than 1000 mr/hr must obtain a high range dosimeter from the Health Physics Office before entry.
- 2. All persgnnel entering any High Radiation Area (greater than or equal to 100 mr/hr) must notii-/ the Health Physics Office before entry. This applies bcth to regular RWP holders and Blanket RWP holders.
- 3. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rates in the area.
l' b. A radiation monitoring device which continuously I integrates the radiation dose in the area and alarms l when a preset integrated dose is received. Entry into such areas with this monitoring device may_be made after the dose rate levels in the area have been established and personnel have been made know g b g of them. 4 *.'
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CV9RovCL MDM NO E.1. HATCH NUCLEAR PLANT HNP-SM8 See Title Page ****"* one 17 See Title Page 9 of 19 cg. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over activities within the areas and shall perform periodic radiation surveillance.
- 4. The purpose of these three options is to assure that adequate dosimetry is provided to assess radiation exposure, to assure that personnel entering these areas are properly informed as to the radiological conditions of the area, and to assure that the required equipment for entering has been provided.
, NOTE
- Field dose rate is referred to as the dose rate approximate.ly 18 inches from a point or line source, or any. area dose rate 3. .
greater than 1000 mr/hr. ( H. EXPOSURE CATEGORY DEFINITIONS (REG. GUIDE 1.16) The following is to be used for determining the work category of the RWP.
- 1. Routine Surveillance and Inspection (RSI)
All inspections or surveillance that is continuous or repetitive in nature.
- a. Inspections of pumps, valves, systems, etc.
- b. Routine observations in Radiation Controlled Areas.
- c. Inspection of all mechanical or electrical components that does not involve physical work cn that system.
- d. All Blanket RWPs except in the case of work involved on special categories, i.e. R.O., W.P., S.P.M., I.S.I., or R.P.M.
- 2. Routine Plant Maintenance (R.P.M.)
All plant maintenance that is routine in nature. This includes all maintenance that is performed or can be performed during normal plant operation.
- a. Repair of all valves. .
MANEn L SET 4 i
- _-_ _ _ --_---_ _ ___-_____-____-_-_______ ______--_ -_ __ __ _ ____J
- -o E.1. HATCH NUCLEAR PLANT HNP-8008 See Title Page *** * *o om 17 See Title Page 10 of 19 bE . Repacking of valves.
- c. Rebuilding of pumps - RWCU, FPCU, etc.
- d. Changing oil in system. -
- e. Repair of electrical motors and components - MOVs, Breakers, Motor Control Centers, etc.
- f. Changing of filters in HVAC filter trains.
- g. Greasing of pumps, valves, and motors.
- h. Checking shaft voltage readings on components.
- i. Welding, grinding, lapping of components associated with systems.
- 3. Special Plant Maintenance (S.P.M.)
Refers to special maintenance not usually performed during normal operations. Most major maintenance is associated ( with outages. *
- a. Removal of feed water spargers,
- b. Radiographic examinations of all components.
- c. Repair of major steam supply delivery components -
MSRs, MSSVs, MSIVs, SRVs, FWHs.
- d. Repair Turbine mechanical components - Main Turbine and RFPTs.
- e. Removal and replacement of in-core monitors, TIPS, LPRMs, IRMs, SRMs, etc.
- f. Installation of new electrical systems or maintenance on those systems outage related - pulling cable, removal of insulation, etc.
- g. Ir. RPV maintenance, i.e. Cladding Removal, Jet Pump Removal, etc.
- 4. Refueling Operations (R.O.)
All work performed that is directly related to the refueling done during a refueling and maintenance outage.
- a. Removal of RPV Head, Dryer Separater, Moisture ,
Separator, Drywell Head, etc. 4AN#4iSET 1 1
- -o E.1. HATCH NUCLEAR PLANT HNP-8008 See Title Page om 17 See Title Page 11 of 19 b; Moving of new spent fuel from RPV to fuel pool or from fuel pool to RPV.
- c. Fuel Sipping.
- d. Gamma Scanning.
- e. Inspection of new fuel.
- f. Detensioning of RPV head.
S. Waste Processing (W.P.) All work that is associated with radioactive waste processing.
- a. Capping of drums in Radwaste drum capping room.
- b. Compa: ting of trash.
- c. Washing down of Drum Capping Rooms, Hopper Rooms, and Centrifuge Rooms.
- d. Radioactive Waste Shipments - loading, surveying, and processing.
- e. Maintenance personnel removing and replacing lids on shipping casks or operating cherry pickers (cranes).
G. In Service Inspection (I.S.I.) All work associated with inspection of Reactor Vessel, Steam Supply or Delivery components that has been in service. All non-desttuctive testing and/or inspection of components to determine quality of that component and/or system. Inspection of cmnponents that have been in service and preventive inspection of equipment that has been in service. Outage-relateu inspection of reactor vessel or i assJciated components. l l
- a. Dye penetrant testing (PT).
l
- b. Ultrasonic testing (UT).
i ! c. Radiographic testing (RT).
- l
- d. Magna Flux testing.
l l , j aansatsti a l . g I 1
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"-8 8 See Title Page E. I. HATCH NUCLEAR PLANT _
l cm 17
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See Title Pag, Georgiafbwer 1, ,, 1, L. COPPUTER RWP's If a computer generated RWP is to be used, the information is first entered into the original handwritten RWP up to the point of the Shift Supervisor's approval. The handwritten copy is used to enter the information into the computer. The computer wif1 print a copy of the RWP (Figure 7). This copy is then distributed for signature. Once the RWP has been signed by the originator, the Health Physics Technician, the Health Physics Foreman or designee, and the Shift Supervisor, it should be approved on the computer. When this is done, it is ready for use. All aspects of the computer RWP will be handled as in the previous sections of this procedure and/or the Operator's Manual for the RWP/1000 program. ( IAN#4 L SET f . i
_ oa m r Ee le HATCH NUCLEAR PLANT * -8008 See Title Page """* om 17 Georgia Power ' *
- See Title Page U 13 Of 19
~
FIGURF 1 5 . RADIATION WORK PERMIT (FRONT SIDE) i l . .. . .
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W%N NO 1 E. I. HATCH NUCLEAR PLANT HNP-8008 See Title Page *v.sm ~o wt 17 See Title Page 14 of 19 FIGURE 2
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#AN#4 L SET 4l 8
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. E.1. HATCH NUCLEAR PLANT HNP-8008 See Title Page o.ra 17
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