Text

Public Version of Revision 1 to Emergency Plan Procedures Vols 1 & 2,including Changes to Section I Re Onsite Procedures,Section II Re Offsite Procedures & Section IV Re Radiation Protection/Chemistry Procedures
	ML20041D263
Person / Time
Site:	Salem
Issue date:	10/27/1981
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18086B336	List: ML18086B337; ML20041D263;
References
	PROC-811027, NUDOCS 8203050049
	Download: ML20041D263 (650)
	v • d • e

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SALEP, GENERATING STATION

() EMERGENCY PLAN EMERGENCY PLAN PROCEDtJRES INDEX JCTOBER 27, 1981 REV. NO.

SECTION I - ON-SITE PROCEDURES EP I-0 Accident Classification Guide ................................................ 1 Part 1 Radiological Part 2 Operational Part 3 Fire / Natural / Security Part 4 Miscellaneous Flow Chart .................................................................... 0 EP I-l Notification of Unusual Event ................................................ 1 EP I-2 Alert ......................................................................... 1 EP I-3 Site Area Emergency .......................................................... 1 EP I-4 General Emergency ............................................................ 1 EP I-5 Personnel Emergency .......................................................... 1 EP I-6 Radioactive Spill ............................................................ 1 EP I-7 Station Fire .................................................................. 1 EP I-8 Personnel Accountability ..................................................... 1 EP I-9 ) Search and Rescue Operations ................................................. 1 EP I-10 Conducting an Inventory of Emergency Equipment ............................... 1

! EP I-ll Communications Equipment ..................................................... 1 EP I-12 Site Evacuation .............................................................. 1 EP I-13 Post Accident Low Pressure Injection Monitoring .............................. 1

'P I-14 Initiation of Recovery Operations ............................................ 1 i

EP I-15 S table Iod ine Thyroid Bloc king . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP I-16 Recall of Evacuated Site Personnel ........................................... 1 EP I-17 Radiation Protection - Emergency Action ...................................... 1 EP I-18 Operations S,upport Center Activation ......................................... 1 EP I-19 Activation / Evacuation of the Technical Support Center ........................ 1 SECTION II - 0FF-SITE PR0rFDURES EP II-l Emergency Response Manager Preparation to Assume Responsibilities ............ 1 EP II-2 Site Support Manager Preparation to Assume Responsibilities .................. 1 EP II-3 Radiological Emergency Manager Preparation to Assume Responsibilities ........ 1

! EP II-4 Notification of Corporate Emergency Response Personnel ........................ 1 EP II-5 Emergency Paging of Corporate Emergency Response Personnel ................... 1 Off-Site Administrative Support ............................................... 1 EP II-6 EP II-7 Testing of Emergency Procedure EP II-4 ........................................ O s

i 8203050049 810301 Rev. 1

' PDR ADOCK 05000272 Page 1 of 3 F PDR

REV. NO.

(}) SECTION III - SECURITY EMERGENCY PROCEDURES EP III-l Opening of the Technical Support Center ...................................... 0 EP III-2 Opening of the Emergency Operations Facility ................................. 0 EP III-3 Personnel Accountability ...................................................... 0 EP III-4 Emergency Vehicle Support ..................................................... O EP III-5 Site Evacuation - Security support ............................................ O SECTION IV - RADIATION PROTECTION / CHEMISTRY EMERCENCY PROCEDURES EP IV-101 TSC Initial Response .......................................................... 1 EP IV-102 Control Room Initial Response ................................................ 1 EP IV-103 Control Point Initial Response ................................................ 1 EP IV-104 TSC Evacuation ............................................................... 1 EP IV-105 Control Point and Equipment Evacuation ....................................... 1 EP IV-106 ALARA Task Review and Emergency Exposure Authorization . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-107 Radiation Monitor Evaluation ................................................. 1 EP IV-108 Protective Action Recommendations ............................................ 1 EP IV-109 Plume Tracking by Helicopter ................................................. 1 EP IV-110 Field Monitoring ............................................................. 1 EP IV-lll Effluent Dose Calculations ................................................... 1 EP IV-112 Not Used EP IV-ll3 Computerized Dose Calculations ............................................... 1

) EP IV-114 Not Used EP IV-115 Personnel and Vehicle Survey ................................................. 1 EP IV-ll6 Fire Brigade Escort ........................................................... 1 EP IV-ll7 Re-Entry Te am Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-ll8 High Activity Sample Analysis ...........................................,.... 1 EP IV-119 Personnel Decontamination .................................................... 1 EP IV-120 Equipment Decontamination .................................................... 1 EP IV-121 Containment Atmosphere Remote Sampling ....................................... 1 EP IV-122 Emergency Staffing Guide ...................................................... 0 EP IV-201 Radiation Protection Senior Supervisor Response ............................... 1 EP IV-202 Chemis try Senior Supervisor Re sponse . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-203 Administrative Assistant Response ............................................. 1 EP IV-204 Short Term Environmental Response ............................................ 1 EP IV-205 Material and Instruments Supervisor Response .................................. 1 EP IV-206 Dos bnetry-Counting Room Supervisor Response . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-207 Rad Waste Supervisor Response ................................................ 1 EP IV-208 Dose Assessment - ALARA Supervisor Response .................................. 1 EP IV-209 In-Plant Supervisor Response ................................................. 1 EP IV-210 P roc ed ur e s-Tra ining Supe rvi s or Re s pon s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-211 Radiation Protection Communications Guide ..................................... 1 EP IV-212 Radiation Protection Emergency Inventory Control ............................. 1 EP IV-301 Interim Post Accident Primary Coolant S ampling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

/ EP IV-302 Emergency Sampling Procedure for the Plant Vent .............................. 1 Page 2 of 3 Rev. 1

REV. NO.

SECTION V - ENGINEERING DEPARTMENT EMERGENCY PROCEDCPES

() EP V-1 Notification of Engineering and Construction Department ....................... O EP V-2 Corporate Engineering Support Manager Response (CHERC) ........................ 0 EP V-3 Sito Engineering Support Manager Response (EOF) ............................... O EP V-4 Corporate Engineering Team Lead 9r Response (CHERC) ....... .................... O EP V-5 Corporate Quality Assurance Department Response (CHERC) ....................... 0 EP V-6 Site Quality Assurance Department Response (EOF) .............................. 0 EP V-7 Site Engineering Team Leader Response (TSC) ................................... O EP V-8 Methods Department & Engineering Department Divisional Representatives Response (CHERC) ........................................................... O SECTION VI - PLAN ADMINISTRATION EP VI-l Revision and Approval of Plans and Procedures ................................ 1 EP VI-2 Dis tribution o f Plans and Procedure s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . O EP VI-3 Review of Plans and Procedures ............................................... 0 EP VI-4 Procedures Format ............................................................. O EP VI-5 Conduct of Drills and Exercises .............................................. 1 SECTION VII - PUBLIC INFORP.ATION EP VII-l Public Information Notification .............................................. 0

  ) EP VII-2      General Manager - Information Services Response ............................... O EP VII-3      Public Information Manager Response ........................................... 0 EP VII-4      Public Information Technical Liaison Response ................................. 0 EP VII-5      Public Information Technical 3ssistant Response ............................... 0 EP VII-6      Internal Information         ........s,................................................                                     0 EP VII-7      Media Relations .............................................................. 0 EP VII-8      Emergency News Center Activation /Public Information Coordinator Response ...... 0 ADDENDUM Addendum 1 Master Phone List          .............................................................                                       1 Addendgm 2 Supplemental Station Status Checklist                        .........................................                         1 flGURES Figure 1      EDO Checklist     .................................................................                                         1 Figure 2      Communications / EOF Manning Board .............................................. O Figure 3      Operational Status Board ...................................................... O Figure 4      Radiological Status Board .................................................... 0 A

V Page 3 of 3 Rev. 1

0 ACCIDENT CLASSIFICATION GUIDE EP 1-0 PURPOSE The purpose of this procedure is to describe the Accident Classification System and to delineate those actions necessary to properly identify an accider.t class by initiating conditions and associated observable plant parameters. Detailed emergency response or " Action Statements" for each class of emergency are feand in Procedures EP I-1, EP I-2, EP I-3 and EP I-4. DFSCRIPTION - ACCIDENT CLASSIFICATION GUIDE The Classification Guide is separated into four (4) basic modules. They are:

1) RADIOLOGICAL - An actual rele=== of radioactive material, abacrmal radiation level, or indicated failure of a fission product boundary.

2) OPERATIONAL - Any plant corditions, equipment failures or combination of the two (2) which could result in a radiological incident.

3) FIRE / NATURAL / SECURITY - Any fire, natural phenomena, or security event affecting the operability of structures or equipment which could lead to a radiological incident.

4) MISCELLANEOUS - Any event not addressed in the nadiological, operational, or Fire / Natural /

Security modules which could lead to a radiological incident or require off-site notifica-tion. Each basic module is broken down into major event categories as submodules, illustrated on the

   " Accident Classification Flowchart" (Attachment No.1 of this procedure) . Each submodule is then further divided. The specific initiating conditions comprise the left hand column of each page in the Classification Guide. The middle column in the Guide lists the observable plant parameters or " Emergency Action Levels" (EAL's), the recognition of which requires entry into l

1 the appropriate accident classification. The right hand column in the Guide provides the accident classification (listed by Emergency Procedure) required for specific initiating conditions. DESCRIPTION - ACCIDENT CLASSIFICATION FLOWCHART The Accident Classification Flowchart (Attachment No. 1 of this procedure) is a tool designed to assist the Senior Shift Supervisor / Shift Supervisor / Shift Technical Advisor /EDO in selecting the appropriate portion of the Accident Classification Guide when certain combinations of plant conditions may dictate selection of, or escalation to, a higher order or emergency classifica-tion. Page 1-3 Rev. 1

EP I-0 Q USE OF TuE ACCIDENT CLASSIFICATION SYSTEM The mechanisms by which Emergency Procedures EP I-l through EP I-4 are initially implemented are as follows:

1) An event occurs which causes initiation of a Plant Emergency Instruction which in turn refers to a specific part within the Accident Classification Guide.

2) Plant parameters which reach an EAL for an accident class in the Accident Classification Guide are observed by plant operators.

Upon recognition of conditions which require implementation of the Emergency Plan, the Control Operators will notify the Senior Shift Supervisor / Shift Supervisor. In the event that plant conditions degrade or additional abnormal plant conditions arise, the Senior Shift Supervisor / Shift Supervisor /ED0/STA may find additional assessment guidance by use of the Accident Classification Flowchart (although the Flowchart is not intended to replace the ! Accident Classification Guide). The Flowchart can indicate, for certain combinations of plant i l I conditions, which basic module in the guide contains the Initiating Cont.itions, EAL's, and j l applicable Emergency Procedure for the conditions present. O Prepared By: _ />f.'/ // he M Reviewed By /) / O " E7- bI Department tiend Date Reviewed By: - > W-_ -

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sistant to Manager Date Reviewed By: , [ D Station Quality Assurance Engineer Date l SORC Meeting No.: bI~ lII IO/37 !bl

                                                                                                                                    ' Date Approved By:                                                                                                            ///J                     V Manager - 9tlem Generating Station                                        Date ~

Approved By: * *

                                                                                       >/I Manager - Emergency Preparedness d       V Date O

l Page 2 of 3 Rev. 1

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O o ACCIDENT C1.ASSIIPICATIC3 CUIDE d failure of a fission product An actual Release of Radioactive piaterial, abnorssal radiation levels or indicate RAD 101DGICAL: boundary. ACCIDENT CIASS EMERGENCT ACTION 1.EVEl.S EP I-1 INITI ATING CONDITION A. Any of the following valid process monitor readings for longer

1. Caseous effluent instantaneous release rate than 1 br. which are greater than:

Technical Specifications limits exceeded for I hr. (Appendia B Technical Specification 1R-12A: 3.0E4 cpm (vent moottor mode) (1.86E-2 pCi/cc) 2.3.3). 1R-128: 1.5E4 cpm (vent monitor mode) 2R-41C: 4.9E5 cpm (1.31 E-2 pct /cc) 25-418: 8.3E4 cpm Conformattoa by grab sample and laboratory analysis shall be made as soon as possible. EP I-2 A. Any of the following valid RMS process monitor readings for

2. Sustained liquid release (grester than longer than 15 min which are greater thans 15 min.) of radiological effluents greater than 10 times Technical Specification 1R-12A 3 0E5 cym (vent monitor mode) (1.86E-1 pC1/cc) instantaneous limits and which is not 1R-128: 1.5E5 cpm immediately controllable.

2R-41C: 4.9E6 cpm or high off-scale (1.31E-1 pct /cc) 2R-415: 8.3E5 cpm

3. Dose rate at the minimum exclusion area equivalent to 500mm/hr W.B. or 2500mR/hr to the thyroid for 2 minutes. EP I-3 A. Any of the following valid RMS process monitor readings for A. Based upon Caseous Effluent Monitors and longer than two minutes which are greater than:

site gecific 5% worst case meteorology. 1R-12A: 2.1E6 cpm (3.56E-1 pC1/cc) 1R-125 1.0E6 cpm R-43: 5.0E0 mR/hr 2R-41C: 3.4E7 cpm (8.99E-1 pct /cc) 2R-418: 5.8E6 cpm EP I-3 B. Valid radiation monitor reading as follous: B. Based upon containment radiation levels, design basis leak rate and site specific 1R-21: Off-scale o_r

               $1 worst case meteorology.                                                       2R-21: 3.7E5mR/hr EP I-3 l

i C. 1) Field team measures whole body dose rates greater than for 250 min. C. Based upon dose rate survey. mres/hr. for 0.5 hr. or greater than 500 ares /hr. at the MEA. SS

2) Field team measures Thyroid dose r'stes (equivalent I-131 concentrations) greater Elian:

250 ares /hr (1.0E-7 pC1/cc) for 0.5 hr; or l 2500 aree/hr (1.0E-6 pC1/cc) for 2 min. at the HFA Rev. 1 Page 1 of 11 EP I-0, PART 1

rm U O O ACCIDENT CLASSIFICATION GUIDE RADIOLOGICAL: An actual Release of Radioactive material, abnormal radiation levels or indicated failure of a fission product boundary. INITIATING CONDITION DtERCENCY ACTION LE'vELS ACCIDENT CIASS

3. (continued)

Dose rate at the minimum esclusion area equivalent to 500mR/hr W.B. or 2500 mR/hr to the thyroid for 2 minutes. D. Projected WB/ Thyroid dose using actual D. As indicated by dose cale.ulation procedure EP IV-Ill, 112 or EP I-3 meteorology. 113.

4. Dose rate at the minimum esclusion area equivalent to IR/hr W.B. or SR/hr to the Thyroid.

A. Based upon Caseous Effluent Monitors and A. Any of the following Valid Radiation Monitor Reading as follows: EP l-4 site specific 52 worst case meteorology. IR-12A Off-scale or 1R-125: Off-scale E R-43: 1(knR/hr [ 2R-41C Off-scale or~ 2R-41B: Off-scale B. Based upon containment radiation levels, B. ValiJ Radiation Monitor Reading as follows: EP I-4 design basis leak rate and site specific 5% worst case meteorology. IR-21: Off-scale high og 2R-21: 7.5E5 mr/hr C. Based upon dose rate survey. C. Field survey team measures 1 R/hr W.B. at the MEA or 5 R/hr EP l-4 Thyroid (I-131 concentration of 2.0E-6 pC1/cc). D. Projected W.B./ Thyroid dose using actual D. As indicated by dose calculation procedure EP IV-Ill, 112, or EP I-4 meteorology. 113.

5. Radiation levels or airborne contamination A. Increase in measured or calculated dose rated (mR/hr) either EP I-2 which indicate a severe degradation in the installed or portable monitoring equipment by a factor of 1000.

control of radioactive materials which i results in an increase in measure or OR

calculated dose rate (mR/hr) by a factor of l Unit I verification based on increase of analog strip chart j 1000 times. B. reading over 20 minute period. l En C. Unit 2 verification based on RMS computer trend. , l l EP I-0, PART 1 Page 2 of 11 Rev. 1

O O ACCIDENT CIJLSSIFICATION CUIDE O - RADIOLOGICAL: An actual Release of Radioactive snaterial, abnormal radiation levels or indicated failure of a f,ission product boundary. INITIATINC (DNDITION D4ERCENCY ACflON LEVELS ACCIDENT CLASS

6. Liquid effluent concentration specification *A. Any of the following valid RMS readings for lonRet than 15 min. EP I-1 limits exceeded for 15 min. which are greater thans IR-18: 1.0E4 cpm er 2R-18: 4.08E4 cpm and B. Isolation valve fails to close.

EE

                                                             *C,     IR19a   b,c.da    alarm and blowdown to 12SCB tank in prostean or 2R19a. b. c. de alarm and blowdown to 22SCB tank in progress

7. Fuel Damage indication A. Radiation Monitor 1(2)R31C (Letdown k nitor) Alarms. EP I-2 AND

5. Sample of RCS confirm equivalent I-131 or gross activity greater than Technical Specification 3.4.8.

8. Severe loss of fuel cladding A. Primary coolant sample indicates 1-131 concentration equivalent EP I-2 greater than 300 pC1/ce.

ER_ B. Unit I letdown monitor 1R31A in high alarm (off-scale) or Unit 2 letdown monitor 2R31A in high alarm (off-scale) and Laboratory analysis which indicates an increase in failed fuel of 1 percent in 30 min. or a total failed fuel of 5 percent.

9. Reactor Coolant Pump seizure leading to A. 1) N tor current spiking to the locked rotor value then going EP I-2 fuel failure to zero.

ER

2) Sudden decrease in RCS flow in the affected loop.

R S..

3) Reactor Coolant Piane vibration of loose Parts Monitor alarm.

                                                              .A._N_D B. 1) Radiation Monitor 1(2)R31C (Letdown Monitor) alarms AN, g

2) Sample of RCS confira I-131 or gross activity Rreater than Technical Specification 3.4.8.

eConfirmation by laboratory analysis. Release permit set point based upon Technical Specification and 10CTR20 limits. EP I-0, PART 1 Page 3 of 11 Rev. 1

a a ACCIDENT CLASSIFICATION CUIDE RADIOLOGICAL: An actual Release of Radioact.ive material, abnormal radiation levels or indicated failure of a fission product t>oundary. INITIATINC CONDITION __ FMRCENCY ACTION LEVELS ACCIDENT CLASS

10. Degraded core with possible loss of coolable A. 5 or more core exit therecouples indicate greater than 1200*F. EP l-3 geometry (indicators should include instrumentation to detect inadequate core OR coo 11os, coolant activity and/or contaisument radioactivity levels). S. Loss of all feedwater and aualliary feedwater capability with no wide range Steam Cenerator level and no steam pressure.

SR C. 1) Unit I letdown monitor 1R31A in high alarm (off-scale). Unit 2 letdown monitor 2R31A in high alarm (off-scala), and_

2) Laboratory analysis which indicates an increase in failed fuel of one percent in 30 min. or a total failed fuel of 52.

EE

3) Primary coolant sample indicates equivalent 1-131 concentra-tion gre ter than 300 pC1/cc; s %

D. 1) hro (2) or more wide range hot leg RTD's indicate greater than 700*F. M

2) RMS monitors R11A, R12A or R125 alarm or

3) Contalement sump level greater than 81' 3" or

4) Containment pressure greater than 4.0 pais. (2/4)

11. less of 2 or 3 fission product barriers with The following indicators are representative oft EP I-4 a potential loss of 3rd barrier, (e.g. loss of primary coolant boundary, clad failure As Degraded core (cladding failure and/or fuel damage) and high potential for loss of containment).

B Loss of primary coolant (IDCA) , C: Containment fa!!ure Thus any combination of two of the above with the potential for the third indicates a " General Emergency" condition and EP l-4 must be implemented issediately. Page 4 of 11 Rev. 1 EP I-0, PART 1

O O ACCIDENT CLASSIFICATION CUIDE O RADIOLOGICAL: An actual Release of Radioactive material, abnormal radiation levels or indicated failure of a fission product boundary. INITIATINC CONDITION INERCENCY ACTION LEVELS ACCIDENT CIASS

11. (coneinued)

Loss of 2 or 3 fission product barriers with A. Dearaded Core a potential loss of 3rd barrier, (e.g. loss of primary coolant boundary, clad failure 1. a) Unit 1 letdown monitor 1R31C in high alarm (off-scale) or and high potential for loss of containment). Unit 2 letdown monitor 2R31C in high alarm (off-scale) AM.D b) Laboratory analysis which indicates an increase in failed fuel of one percent in 30 min. or a total failed fuel of 52, or c) Frimary coolant sample indication equivalent 1-131 concentration greater than 300 pC1/cc; E

2. a) Either one of the following:

1) 5 or more core exit thermocouples indicating greater A n 1200*F.

B

2) 2 os more wide range hot leg RTD's indicating greater than 700*F.

9 AN.D_ b) One of the following:

1) Ragidly diverging AT M

2) No AT(T h -T = 0)

E

3. Loss of all feedvater and aum111ary feedwater with no wide range steam generator level indicated and no steam pressure.

EP I-0, PART I Page 5 of 11 Rev. 1

O O ACCIDENT CLASSIFICATION CUIDE O RADIOLOGICAL: An actual Release of Radioactive material, abnormal radiation levels or indicated failuim of a fission product boundary. INITIATINC COND1 TION EMERCENCY ACTION 1.EVEl.S ACCIDENT CIASS

11. (continued) loss of 2 or 3 fission product barriers with 4. Loss of Primary Coolant Inventory a potential loss of 3rd barrier, (e.g. loss of primary coolant boundary, clad failure 1. Primary coolas.t leakage eaceeds makeup capacity low and high potential for loss of containment. pressus f rer level with level decreasing and Charging Pianps' flow at maximum.

9E

2. a) Valid containment pressure greater than 4.0 psig.

M b) Accumulator (s) discharge (while in moda 1, 2 or 3) SE

3. Inadequate sub-cooling, as indicated by F-250 strip chart recorder or manual calculation and the plant in modes 1, 2, or 3.

SE

4. The following radiation monitor readings a) 1(2)R21 Indicating 20R/hr or greater.

AN,p b) Any 2 of 4 of the following RMS channels off-scale 1(2)R2 1(2)R7 1(2)R10A 1(2)R108 9R

5. Either one of the followings a) 2 out of 5 Fan Coil IJnit Drainage Alarms Actuate, c_r indication of Containment pressure greater than 4.0 psig, (2/4)

M b) Containment sump level greater than 81' 3**. There is no tedication of an in-containment steam line break. EP I-0, PART I Page 6 of 11 Rev. I

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

O o ACCI!*NT CLASSIFICATION GUIDE o r ItADIOLOGICAL: An actual Release of Radioactive material, abnorssal radiation levels er indicated failure of a fission product boundary. INITIATING CONDITION EERCENCY ACTION LEVELS ACCIDDit CLASS

11. (continued)

Imse of 2 or 3 fission product barriers with C. Containment Failure (Actual or Likely) a potential loss of 3rd barrier (e.g. loss of primary coolant boundary, clad failure 1. Containment H c ncentration greater than 41. 2 and high potential for loss of contairment). 93

2. Indication of Containment pressure greater than 47 rsig and increasing. (2/4)

SE

3. Either of the following:

a) There are less than S Fan Coil Units available, with no , Containment Spray train capability, or b) There are less than 3 Fan Coil Units available, with 1 only 1 Containment Spray train capability. M c) Indication of Containment pressure greater than 23.5 psig and increasing. (2/4) EE

4. raisolatable steam line break outside containment with indicctions of a primary to secondary leak.

9E

5. Contaisusent penetration isolation valueis) or hatch failure as determined by ED0/SSS (Visud observation or high air-t borne activities around penetcJt&on or hatches). l EP I-0, PART 1 Page 7 of 11 Rev. 1

O O O . ACCIDENT CIM "31FICATION CUIDF. RADIOLOGICAL: An actual Release of Radioactive material, abnormal radiasion levels or indicated failure of a fission product boundary. INITIATING CONDITION ,, ENERCENCY ACTION LEVELS ACCIDENT CLASS

12. gaceeding primary to secondary rate A. Primary to secondary leakage exceeding either of the following: EP 1-1 Technical Specification or primary system leak Technical Specification. 1) I gym total leakage through a!! steso generators, o_r

2) 500 gallons per day through any one steam generator.

M B. Reactor coolant system leakage escoeding any of the following:

1) No pressure boundary leakage, or

2) 1 gpa llNIDENTirlED LEAKACE, o_rr

3) 10 spe Identified Leakage, or

4) 40 gym Controlled Leakage with RCS at Norma % Operating .

Pressure

13. Failure of a Pressurizer Safety or Relief A. Pressurizer pressure less than 2200 peig with POPS not armed g EP I-1 Valve to Reseat.

3. Pressurizer pressure less than 375 peig with turS armed.

O C. Relief / Safety valve ta!! pipe high temperature indication or D. Pressurizer Relief Tank level increasing

14. Rapid gross failure of one Steam Cenerator A. Reactor Trip and Safety Injection initiate on decreasir.g EP I-2 tube with loss of offsite power. Pressurizer h essure.

2 B. Valid Radiation Monitor Alarma are received on channels R15 or R19a, b,c, at d. O C. Pressuriser pressure (after initial decrease) recovers to a pressure greater than secondary (main steam) pressure and (if required) steam line atmospheric discharges to control steam pressure. M D. Offsite power loss is indicated by Overhead Annunciator or meters on panet RP6 or indication on the Control Console. EP I-0, PART 1 Page 8 of 11 Rev. 1

O O ACCIDENT CLASSIIPICATION CUIDE O RADIO!DGICAL: An actual Release of Radioactive material, abnormal radiation levels or indicated failure of a fission product boundary. - INITIATING CONDITION ,_ EMERCFNCY ACTION LEVELS ACCIDFNT C1. ASS

15. Rapid failure of Steam Generator tubes A. Reactor Trip and Safety Injection initiat e m decreasing EP I-2 (e.g., several hundred gym prianary to Pressurizer Pressuru.

secondary leak rate). AND B. Valid Radiation Monitor Alarms are received on Channels R15 or R194, b, c, or d. 39 3 C. Pressuriser Pressure fails to recover to a pressure greater than Steam Generator Pressure.

16. Steam line break with significant (e.g., A. Steam Line fr.ntslion and Safety injection initiated on High EP I-2 greater than 10 spa) primary to secondary Steam Line 71ow with either Low Tava or low Steam Pressure and leak rate. valid Radiation M mitoring Alarms on Channels R15 or R19a, b, c, or d.

EE i B. Safety Injection initiated on Steam Line High Differential Pressure and valid Radiattors,N=sitor Alarms on R15 or R19a, b, c, or d.

17. Primary coolant leak rate greater than 50 A. In accordance with Technical Specification Secties 3.4.6.2 and EP I-2 gym. one charging pump is unable to maintain pressuricer level in accordance with Technical Specification Section 3.4.4.

18. Known Losa of Coolant Accident & renter than A. Low pressuriser level with level decreasing and Charging P -ps' EP l-3 makeup pump capacity. flow at maximum.

19. Rapid failure of Steam Generator tubes A. Reactor Trip and Safety injection initiate on decreasing EP I-3

          . (several hundred spe leakage) with loss of Pressuriser Pressure.
          ' offsite power.

ES , B. Valid Radiation Monitor Alarms are received on Channels R15 or R19a, b, c, or d. AN_D C. Pressurizer Pressure falls to secover to a pressure Rreater than Steam Cenerator Pressure. giD D. Offsite power loss is indicated by Overhead Annunciators and/s,r meters on Panel RP6 and on the control console. EP I-0, PARY 1 Page 9 of 11 Rev. 1

r. , ..,

y 'u R O ACCIDENT CLASSIFICATION GUIDE , O , ItADIOLOGICAL: An actual Release of Radioactive material, abnormal radiation levels or indicated failure of a fission product boundary. EMERGENCY ACTION LEVELS ACCIDENT CLASS

                                 " INITIAT1HC CONDITION

20. Steam line t,reak with greater than 50 spa , A. Steam Line leolation and Safety injection initiated on High EP I-3 primary to secondary leakage and indication Steam Line Flow with either Low Tavg or lena Steam Pressure or of fuel damage. ,

B. Safety injection initiated on Steam Line High Differential Pressure. ( AN_D , C. Valid Radiation Monitor Alarms on Chanacia FIS or R19a, b, c, or d. AN.D , D. Unit I letdown monitor IR31A in high alarm (off-scale) Unit 2 letdown monitor 2R31A in high alarm (off-acals) AND E. Laboratory analysis which indicates an increase in failed fuel of 1 percent in 30 min, or a total failed fuel rate of 5 . percent, or

                                                                                  !) Primary coolant sample familcates 1-131 concentration greater than 300 pC1/cc.

21. Loss of Containment Integrity resulting in a A. In accordance with Technical Specification Section 3.6.1.

unit shutdown by Technical Specifications. A. A valid alarm on the following Radiation Monitor EP l-2

22. Fuel damage accident with release of radio-activity to containment or fuel handling building. 1) 1(2)R5: Alarm o_r

2) 1(2)R9: Alarm E

3) 1(2)R29: Alarm AND W 1812A (in Plant Vent Mode) or 2R418: Alarm or~ +

5) 1R128 (in Plant vent Mode) or 2R41C: Alarm pR B. 2 of the 4 Containment RMS Monitor

(

1) 1(2)R2 Alarm

2) 1(2)R7 Alarm

3) 1(2)R10A: Alarm

4) 1(2)R105: Alarm AND T) 1(2)R21: IR/hr 4

_AND, C. Verify fuel handling problem where damage to fuel may have occurred. EP I-0, PART 1 Page 10 of 11 Rev. 1

O O O ACCIDENT CLASSIFICATION GUIDE RADIOIDGICAL: An actual Release of Radioactive material, abnormal radiation levels o' indicated failure of a fission product boundary. INITIATING CONDITION DtERCENCY ACTION LEVELS ACCIDENT CLASS

23. Major damage to spent fuel in containment or A. A valid alarm on the following Radiation Monitor EP I-3 fuel handling building (e.g., larRest object damages fuel or water loss below fuel level). 1) 1(2)R5: Alare g

2) 1(2)R9: Alarm or

3) 1(2)R29: Alarm SE B. 2 of the 4 Containment RMS Monitor

1) 1(2)R2: Alarm

2) 1(2)R7 Alara

3) 1(2)R10A: Alarm

4) 1(2)R105: Alarm AND W 1(2)R21 1R/hr AND C. Confirmed fuel damage or loss of water level to below fuel level.

t Page 11 of 11 Rev. 1 EP I-0, PART 1

O O O ACCIDENT CLASSIFICATION GUIDE

OPERATIONAL: Any abnormal plant conditions, equipment failures, or cosabination of the two which could result in a radio-logical incident. INITIATING CONDITION DERCENCY ACTION LEVELS ACCIDENT CIASS

1. Manual or automatic actuation of emergency A. Any limit in Technical Specification Table 3.3-3 and 3.3-4 EP l-1 core cooling systems with a discharge to the exceeded or manual initiation has been made or vessel.

B. Logic lights for any single or coincidence initiation lit on RP-4. Safeguards Status Display. AHp C. ESF System Actuation is verified by control console indication (flow, valve positions, tank levels, etc.) for any of the following:

1) Safety injection

2) Steam Line Isolation

3) Containment Spray ,

i E D. Verification that one or more of the limits of Technical Specification Table 2.2-1 has been exceeded or manual initiation has been made and, E. Rod botton lights are lit, control console indication (nuclear instruments, rod position indication, etc.) or overhead annunciator (Section F) indicates a Reactor Trip.

2. Uncontrolled rapid secondary depressuriza- A. High Steam Flow orr EP I-1 tion (steam or feedwater line rupture).

B. Abnormal increase in feedwater flow to one or two steam generators ANg C. Any of the following:

1) tow steam generator pressure

2) Low T (average)

3) Reduced RCS pressure

3. Failure of a stear, generator Safety or A. Visual and/or audible indication at the vent stacks of the open EP I-1 Atmospheric relief valve to rescat. valve after pressure restored to desired level.

E B. Excess feedwater flow or steam flow for the affected generator. A. In accordance with Technical Specification Section 3.2 EP I-!

4. Loss of Engineered Safety Feature function requiring shutdown by Technical Specification (because of malfunction, personnel error or procedural inadequacy).

EP I-0, PART 2 Page 1 of 5 Rev. I

m U O ACCIDENT CLASSIFICATICZ CUIDE O ! OPERATIONAL: Any abnormal plant conditions, equipssent failures, or cosibination of the two which could result in a radio-l logical incident. INITIATING CONDITION ENERCENCT ACTION LEVELS ACCIDENT C1 ASS

5. An event which requires initiation of unit A. In accordance with Technical Specifications. E.P I-1

! shutdown to comply with Technical Specif1-cation Limiting Conditions for Operation.

6. Complete loss of any function needed for A. Fa!!ure of the BHR system to attain or maintain the primary EP 1-2 plant cold shutdown. system temperature less than 200*F.

ER. B. Entry into Action Statement a. of Technical Specification Section 3.5.3 (Emergency Core Cooling Systan).

7. Complete loss of any function needed for A. less of Hain and Aux 111ary Feedwater. EP I-3 plant hot shutdown.

9R. B. loss of Steam Disap system and all Steam Cenerator Power Operated Relief Valves and Safety Valves.

8. Total loss of offsite power or loss of on- A. Shutdown required in accordance with Technical Specification EP 1-1 site AC power capability. Section 3.8.1.1.a.

pR B. Indication of the loss of 500 KV. 13 KV and 4 KV group buses on the control console RP-6 electrical display and lit overhead annunciators (Section J and K). SR_ C. Reactor Trip on " Loss of 4 KV Croup Buses" (overhead i annunciator F-26). , SR. D. Shutdown required in accordance with Technical Specification Section 3.8.1.1.b. SE E. Indication of loss of 4 KV Vital Buses on the control console and on overhead annunciators (J-17, 18, 19) with inability to energize those buses from the emergency diesels. EP I-0, PART 2 Page 2 of 5 - Rev. 1

O O ACCIDENT CLASSIFICATION CUIDE O OPERATIONAL: Any abnormal plant conditions, equipment failures, or combination of the two which could result in a radio-logical incident. INITIATINC Q)NDITION EMERCENCY ACTION 1.EVEl.S ACCIDENT C1JLSS

9. loss of offsite power and loss of all onsits A. Indication of the loss of 500 KV, 13 KV and 4 KV Croup Buses on EP 1-2 AC power. the control console RP-6 electrical display and lit overhead annunciators (Section J and K).

M

8. Indication of loss of 4 KV Vital Buses on the control console and on the overhead annunciators (J-17, 18, 19) with inability

' to energise those buses from the emergency diesels.

10. Loss of offsite power and loss of all on- A. Indication of the loss of 500 KV 13 KV and 4 KV Croup Buses on EP I-3 site AC power for more than 15 minutes. the control console, RP-6 electrical display and lit overhead annunciators (Section J and K) for greater than 15 minutes.

AM, D,

5. Indication of loss of 4 KV Vital Buses on the control console and on overhead annunciators (J-17, 18, 19) with inability to energize those buaes from the emergency diesels for greater than 15 minutes.

11. Failure of offsite and onsite power along A. Loss of 500 KV 13 KV and 4 KV Croup Buses, Vital Buses EP I-4 with total loss of Auaillary Feedwater System capability for several hours and M projected core melt and failure of contain-ment. B. Inability to energize 4 KV Vital Buses from emergency diesel generators for greater than 2 hours M

C. Flow indication for Auxiliary Feedwater System shows no flow for greater than 2 hours.

12. Loss of all onsite DC power. A. Recein of all the following valid overhead annunciator alarms: EP I-2 A23, A31, A39, A46 and A47.

13. Loss of all onsite DC power for more than 15 A. Receipt of all the following valid overhead annunciator alarms: EP I-3 minutes. A23, A31, A39, A46 and A47.

2 B. Inability to restore onsite DC power within 15 minutes of the occurrence.

14. Loss of all overhead annunciator alarms for A. As Stated. EP I-2 more than 15 minutes due to an unknown cause. l

15. Loss of all overhead annunciator alarms for A. As Stated. EP I-3 more than I hour and a plant transient initiated or in progress.

Rev. 1 EP I-0, PART 2 Page 3 of 5

O O ACCIDENT CLASSIFICATION CUIDE O OPERATIONAL: Any abnormal plant C,onditions, equipenent failures, or combination of the two which could result in a radio-IcH31 cal incident. INITIATING CONDITION EHERCENCT ACTION LEVELS ACCIDENT CLASS

16. Failure of the Reactor Protection System to A. Receipt of Reactor Protection Logic input (see Technical EP I-2 initiate and complete a trip which brings Specification Table 2.2-1) as displayed on panet RP-4.

l the reactor subcritical. I AND l B. Not all Rod Botton lights lit or Nuclear Instrumentation indicates reactor not subcritical. '

17. Failure of the Reactor Protection System to A. Receipt of Reactor Protection Logic (see Technical Specifica- EP I-3 automatica!!y, or through control operation tion Tabis 2.2-1) as on panel RP-4.

action, manually initiate and complete a trip which brings and maintains the reactor AND suberitical.

8. All Rod Bottom lights not lit or Nuclear Instrumentation indicates reactor not subcritical.

AND C. No boration capabilities.

18. Evacuation of Control Rove anticipated or A. As Stated. EP I-2 required with control of shutdown systems established from local stations.

19. Evacuation of Control Room and control of A. As Stated. EP I-3 shutdown systems not established from local stations in 15 minutes.

20. Transient initiated by loss of Feedwater and A. Reactor trip on low feedwater flow; EP 1-4 Condensate Systems followed by f ailure of Auxiliary Feedwater System for extended AND period and core melting possible in several hours. 8. Decreasing wide-range steam generators; toward off-scale low on all steam generators; O

l C. 1) Auxiliary feedwater flow indicators indicate zero flov 2 minutes after required; or

2) Control Console indication of turbine and motor driven '

Auxiliary Feedwater pumps indicates pmaps not running 2 minutes af ter required; AND D. Auxiliary Feedwater cannot be restored within 30 minutes. l l EP I-0, PART 2 Page 4 of 5 Rev. 1

O O ACCIDENT CLASSIFICATION GUIDE O OPERATIONAL: Any abnormal plant conditions, equipsnent failures, or combination of the two which could result in a radio-logical incident. INITIATING CONDITION DIERCENCT ACTION LEVEL.S ACCIDENT CIASS

21. Transient requiring operation of shutdown A. Reactor ressains critical or returns to criticality af ter trip; EP I-4 systems with failure to scram which results in core damage or additional failure of core g cooling and makeup systems (which could lead to core melt). g. 1) Flow indicators on safety injection systems and RHR systems show zero flow with safety injection initiated; or

2) St.tus lights show safety injection systems and BHR pumps not running with safety injection initiated.

EP I-0 PART 2 Page 5 of 5 Rev. 1

O O ACCIDENT CLASSIFICATION CUIDE O FIRE /NAIURAL/ SECURITY: Any fire, natural phenomena, or security event affecting the operability of structures or equipment, which could leak to a radiological incident. INITIATING CONDITIO84 EMERCENCY ACTION I.EVELS M DENT CLASS

1. Fire lasting greater than 10 minutes that A. Observation of a fire lasting greater than 10 minutes that EP I-1 affects plant operation (e.g., causes a affects plant operation reduction in power or a mode change).

M

8. Fire alarm receiveJ and confirming observation of a fire lasting greater than 10 minutes that affects plant operation.

2. Fire potentially affecting safety systems. A. Observations of a fire in one of the following areas EP l-2 potentially affecting a safety systems

1) Containment g

2) Control Room or

3) RelayRoomo[

4) Protection Racks g

5) Auxiliary Building ol

6) Service Water Structure or

7) Penetration Areas or

8) Fuel Handling Building M

B. Observation of a fire that, in the judgeneat of the Senior Shift Supervisor /EDO, could affect a safety system.

3. Fire compromising the function cf safety A. Observation of a fire in one of the following areas that has EP I-3 systems. affected a safety systems

1) Containment or

2) Control Room or

3) Relay Room or

4) Protection Racks or

5) Ar:111ery Building orr

6) i vice Water Structure or

7) Penetration Areas or

8) Fuel Hand!!ng Building M

B. Observation of a fire that, in the judgement of the Senior Shift Supervisor /EDO has affected a safety system.

4. Security Incident A. Substantiated Security Threat, attempted A. Implementation of security Procedures Section 5.3, event (5), EP l-1 entry or attempted sabotage. (6), or (8).

B. Ongoing Security Compromise. 8. Ongoing Security event Security Procedure, Section 5.3, EP l-2 events (5), (6), or (8). Page 1 of 3 Rev. I EP I-0, PART 3

O o ACCIDENT CLASS 1PICATION GUIDE o FIRE / NATURAL / SECURITY: Any fire, natural phenomena, or security event affecting the operability of structures or equipment, which could leak to a radiological incident. EMERCENCY ACTION LEVELS ACCIDENT CIASS IMITIATlWG CONDITION

4. (continued)

Security Incident . C. Ongoing Security event which may result in loss of physical EP I-3

    ' C. Ongoing Security Compromise involving imminent loss of physical control of               control of the plant (physical attack with Ismainent occupancy the plant.

of the Control Room, hot shutdown panel or other vital areas), Security Procedures Section 5.3, events (6) or (8). D. Ongoing Security event which results in loss of physical EP I-4 D. Ongolog Security Compromise resulting l in the loss of physical control of the control of the plant (physical attack with occupancy of the l plant. Control Room, hot shutdown panel or other vital areas of the plant). Security Procedures. Section 5.3, events (6) or (8).

5. Natural phenomena being experienced or projected beyond usual events.

A. Seismic monitoring instrumentation is activated (0.023 ), as EP I-1 A. Any earthquake felt in-plant or detected on station seismic instrumentation. Indicated by all of the fo!Iowing:

1) Seismic Monitor Alarm (overhe 4 annunciator 843) actuates in Unit No. 1 Control Room and

2) Observattua that seismic monitoring is recording and,

3) Verification of a seismic disturbance by calling the National Earthquake Information Center at (303-234-3994).

P. Tide level recorder indicates 97.5 f t. (PSE&C DATUM) for flood, EP I-1 i B. Unusual flood or low water levels. or 83.1 ft. (PSE&G DATUM) for low water. Tornado Funnel observed within the minimise exclusion area. EP I-I C. Any tornado on site. C. D. Sustained winds in excess of 90 mph, as indicated by any of the EP I-1 D. Any hurricane or unusual wind conditions. following Meterological Instrumentation:

1) Nominal Elev. 33 ft. channel for wind speed of

2) Nominal Elev. 150 ft. channel for wind speed or,r

3) Nominal Elev. 300 ft. channel for wind speed

6. Severe natural phenomena being experienced or projected.

A. Seismic Monitoring Equipment (strip-chart) indicates (0.lg) or EP I-2 A. Earthquake greater than OBE levels. greater and verification of a seismic disturbance by cs11tng the National Earthquake Information Center at (303-234-3994). B. Tide Level recorder indicates 99.0 ft. (PSE&C DATUM) for flood, EP I-2 B. Flood or low water near design levels. or 81.0 ft. (PSE&G DATHM) for low water. C. Tornado funnel observed within the Security Boundary. EP I-2 C. Any tornado striking facility. Rev. I EP I-0, PART 3 Page 2 of 3

O O O ACCIDENT CLASSIFICATION GUIDE

FIRE / NATURAL / SECURITY: Any fire, natural phenomena, or security event affecting the operability of structures or equipment, which could leak to a radiological incident.

INITIATING CONDITION ____ EMERCENCY ACTION LEVEL.S ACCIDENT CLASS

6. (continued)

Severe natural phenomena being experienced or projected. D. Any hurricane or unusual wind conditions. D. Sustained winds of 95 mph, as indicated by any of the following EP I-2 Meterological Instrumentation

1) Elev. 33 ft. channel for wind speed or

2) Elev. 150 ft. channel for wind speed orr

3) Elev. 300 ft. channel for wind speed

7. Severe natural phenomena being experienced Ur projected that compromises the functions of safety systems.

A. Earthquake greater than DBE levels. A. Seismic Monitoring Equipment (strip-chart) indicates (0.2g) or EP I-3 greater and verification of a Seismic Disturbance by calling the National Earthquake Information Center at (303-234-3994). B. Floor or low water greater than design B. Tide level recorder indicates 100.5 ft. (PSE&G DATUM) for flood, EP I-3 levels. or 78.4 ft. (PSE&C DATUM) for low water. C. Any tornado on site affecting safety C. Tornado funnel on site ,1wpacting the following: EP l-3 structures.

1) Turbine Building g

2) Service-Building og

3) Auxiliary Building n

4) Containment Building g

5) Service Water Intake Stsucture or

6) RWST or PWST or AIE T g

7) Fuel Handling Building D. Any hurricane or unusual wind conditions. D. Sustained winds in excess of 100 mph as indicated by the EP 1-3 following Meterological Instrumentation

1) Elevation 33 f t. wind speed g

2) Elevation 150 ft. wind speed of

3) Elevation 300 ft wind speed EP I-0, PART 3 Page 3 of 3 Rev. 1

b O V V V ACCIDENT CLASSIFICATION GUIDE . MISCELLANEOUS: Any event not addressed in the radiological, operational, or fire / natural / security isodule which could lead to radiological incident or require offsite notification. INITIATING CONDITION EMERCENCY ACTION LEVEL.S ACCIDENT CLASS

1. Aircraft Crash Occurring:

A. Nearsite A. Aircraft crash within the minimum exclusion area or a crash EP I-1 affecting one of the 500 KV transmission lines. t

B. On Site B. Aircraft crash within the security boundary. EP I-2 C. Onsite affecting plant structures. C. Aircraft crash causing damage or fire in: EP I-3

                                                              !) Turbine Building g

2) Service Building or

3) Auxiliary Butiding g

4) Containment Building g

5) Service Water Intake Structure or

6) RWST or PWST or AFWST g

7) Fuel Handling Building

2. Onsite Toxic Flasanable Cases:

A. A release which threatens onsite A. Observation of a release or warning from offsite. EP I-1 personnel. B. A release which enters vital areas B. Observation or measurement of gases which exceed flammability EP I-2 thr=.Laning operability or accessability. or toxicity levels after entering the Control Room or Auxiliary Building ventilation system. C. A release which enters vital areas C. Detonation or combustion of a flammable gas in one of the areas EP l-3 compromising the functions of safety actually affecting a safety system. systems.

1) Containment or

2) Contrc1 Room E

3) Relay Room or

4) Protection Racks orr

5) Auxiliary Building or

6) Penetration Areas o_rr

7) Service Water Intake Structure or

8) Fuel Handling Building

3. Turbine generator failure causing an outer A. Turbine trip and observation of penetrations through the outer EP l-1 casing penetration. casing.

4 Missile impact onsite resulting in structural A. Observation of an impact causing severe structural damage to a EP l-2 damage, building within the security boundary. EP I-0, PART 4 Page 1 of 4 Rev. 1

          .     -     _                           _ . .     . . _ ~ . . . . _ __ >         _          . _ . . . . _ _       . . _      _  sm ,,, . ._ _..-.-. . .-_ . ~ . _ . - _                  . . _ , . . _ . . _ .

O O O

ACCIDENT CLASSIFICATION CUIDE MISCELLANEOUS: Any event not addressed in the radiological, operational, or fire / natural / security anodule which could lead to radiological incident or require offsite notification.

ENERCENCY ACTION LEVELS ACCIDENT Cl. ASS INITIATING CONDITION

5. Missile impact onsite resulting in damage to A. Observation of an impact causing structural damage to the EP l-3 a vital structure, following:

1) Turbine Bui'lding or

2) Service Building ol

3) Auxiliary Building or

4) Containment Building or

5) Service Water Intake Structure orr

6) RWST or PWST or AiWST or

7) Fuel Hand!!ng Building

6. Emplosion within the security boundary

. excluding planned activities. EP I-I A. An explosion which affects plant A. Observation of an explosion or its consequences. operations (e.g., causes a reduction in power or mode). B. An explosjon which potentia!!y affects a B. An explosion in one of the following areas potentially EP I-2 safety system, affecting a safety system.

1) Containment o

2) Control Room or

3) Relay Room or

4) Protection Racks or

5) Aust!!ary Building or

6) Penetration Areas orr

7) Service Water Intake Structure C. An explosion compromising the functions C. An explosion in one of the following areas that has affected a EP I-3 of safety systems. safety system.

1) Containment og

2) Control Room or

3) Relay Room o_r, r

4) Protection Racks or,

5) Auxiliary Building or

6) Penetration Areas or

7) Service Water Inta G Structure o

8) Fuel Handling Building

7. Other Plant conditionJ exist that warrant A. As judged by the Senior Shift Supervisor /EDO. EP I-!

increased awareness on the part of reste and local offsite authorities.

8. Other Pla.nt conditions exist that warrant A. As judged by the Senior Shift Supervisor /EDO. EP I-2 precautionary activation of Technical Support Center.

EP I-0, PART 4 Page 2 of 4 Rev. 1

O O ACCIDENT CIASSIFICATION CUIDE O MISCELLANEOUS: Any event not addressed in the radiological, operational, or fire / natural / security snodule which could lead to radiological incident or require offsite notification. INITIATING Q)NDITION EMERCENCY ACTION LEVELS ACCIDENT CIASS

9. Other Plant conditions exist that warrant A. As judged by the Senior Shift Supervisor /EDO. EP l-)

precautionary activation of the Technical Support Center and the Emergency Operations Facility and/or notification to the general public.

10. Radiation one time esposure to any A. As evaluated by the Senior Shift Supervisor /EDO and the EP l-1 individual equal to or greater than 5 rem Radiation Protection Engineer.

whole body; 30 ren sking or 75 rems extremities or forearms.

11. Any serious personnel radioactive contamina- A. As judged by the Senior Shift Supervisor /EDO. EP l-1 tion requiring extensive on site decontamina-tion or taansport of a contaminated injured individual offsite. Notification of hospital takes preference.

12. Any serious or fatal injury occurring on alte A. As judged by the Senior Shift Supervisor /EDO. EP I-1 and requiring off-site medical assistance (hospital stay greater than 48 hours).

13. Any ever* that results in the plant not being A. As judged by the Senior Shift Supervisor'EDO. EP I-I in a' .11ed or espected condition (Mode 1-6).

14. Any event requiring initiating any section(s) A. As judged by the Senior Shift Supervisor /EDO. EP I-l of the Station Emergency Plan Procedures, except for EP I-5 for injuries requiring less than 48 hour hospital stay.

15. Loss of one day or more of plant operation A. As judged by the Assistant to Manager / Designee. EP I-l or damage in excess of $2000 due to incident involving nuclear material.

16. Union strikes affecting the availability of A. As judged by the Senior Shift Supervisor /EDO. EP I-l of operating personnel or the security personnel.

17. Any of the following items which require notification in accordance with 10CFR50.72 or letters of agreement.

A. Any unit startup or a unit trip (planned / A. As judged by the Senior Shift Supervisor /EDO. EP I-1 unplanned) from greater than 20% turbine power. B. Any event requiring a press release be 8. As judged by the Assistant to Manager / Designee. EP I-l prepared. , C. Physical plant damage in excess of C. As judged by the Assistant to Manager / Designee. EP I-l

        $200.000.

EP I-0, PART 4 Page 3 of 4 Rev. I

O O ACCIDENT CLASSIFICATION GUIDE O MISCELLANEOUS: Any event not addressed in the radiological, operational, or fire / natural / security module which could lead to radiological incident or require offsite notification. INITIATING CONDITION EMERCENCY ACTION LEVEL.S ACCIDENT CIAS5

17. (continued)

Any of the following items which require notification in accordance with 10CFR50.72 or letters of agreement. D. Unusually large fish kills, large move- D. As judged by the Senior Shift Supervisor /EDO. EP I-l ment of equipment or personnel which could sianificantly af fect local traffic pattern. E. Significant increase in noise levels E. As judged by the Senior Shift Supervisor /EDO. EP 1-1 steam release on site alare or strens which might be heard off-site. F. Derating caused by a regulatory action. F. As Stated. EP I-l C. Any event meeting the notification C. As evaluated by the Senior Shift Supervisor /EDO and the EP 1-1 criteria of 10CFR20.403. Radiation Protection Engineer. NOTE: The specified time response in this procedure takes presedence over those noted in the above code . reference. l EP I-0, PART 4 Page 4 of 4 Rev. 1

EP I-l m EMERGENCY PROCEDURE c(v) EP I-1 NOTIFICATION OF UNUSUAL EVENT The intent of the notification of unusual event is to provide early and/or prompt notification of minor events and/or minor events that could lead to more serious consequences. Under this event class there should be no potential release of radioactive material requiring off-site monitoring or action unless further system degradation occurs. When any of the conditions noted in EP I-0 mandate declaration of an unusual event, the Senior Shift Supervisor / designee shall initiate the notification sequence noted below using Attachmc.ts 1 and 2. EVENT DECLARATION ( ) INDICATES REQUIRED NOTIFICATION TIME FROM EVENT DECLARATION SENIOR SHIFT SUPERVISOR DEL N1tC LLC (15 MIN) (15 MIN) (1 HR) NJSP EDO ASSISTANT TO 4ANAGER/ DESIGNEE (1 HOUR) (15 MIN) (15 MIN) BPU NRC (24 HR) RESIDENT (24 HR) GMIS DOE SSS (24 HR) (24 HR) (.; 4 HR) NOTE For any event which does ng satisfy an emergency action level per EP I-0 but judged as a potential news release item, contact the Assistant to Manager before initiating any additional notifications. THE SENIOR SHIFT SUPERVISOR, OR HIS DESIGNEE, SHALL ESTABLISH AND, IF NECESSARY, MAINTAIN CONMUNICATIONS WITH THE NRC OPERATIONS CENTER VIA THE DEDICATED (ENS) LINE. THIS COMMUNICATION i s LINK SHALL BE CLOSED WHEN NOTIFIED BY THE NRC.

       )
    ..J l

Page 1 of 4 Rev. 1

EP I-l IF IT HAS BEEN DETERMINED BY THE ASSISTANT TO MANAGER THAT A PRESS RELEASE IS NECESSARY, AND WHEN THE NECESSARY PHONE CALLS ARE COMPLETED, THE ASSISTANT TO MANAGER WILL NOTIFY THE SENIOR SHIFT SUPERVISOR CONCERNING THE BASIC PRESS RELEASE. INCOMING PHONE CALLS TO THE SENIOR SHIFT SUPERVISOR, OR HIS DESIGNEE, REGARDING THE INCIDENT, SHOULD BE ANSWERED WITH '.HE SAME INFORMATION EXPRESSED IN THE PRESS RELEASE. I If additional information is requested, the Senior Shift Supervisor, or his designee, should refer the caller to the Assistant wo Manager or the PIO. Any requests for information should be recorded in the Control Room Log for the appropriate unit. , Any written follow-up or close out action will be the responsibility of the Assistant to Manager. NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attact sny referenced completed EP's or attachments. Prepared By: jrftM* h d , Reviewed By: /0 C6 W Dep r nt ead ' Date Reviewed By: '

                                                                           /0 0 I/

safstant to Manager Date Reviewed By: . 1 JAA ('h G 4tation Quality Assurance Engineer ' Date SORC Meeting No.: I- III /C!27/I/ I D&te Approved By: /d D Manager '- Salfem Generating Station ~Datd Approved Byr. *

                                                         ]/b                  #

N Manager - Emergency Preparedness Date 1 O l l l Page 2 of 4 Rey. 1

                                             >                                                                                        EP I-l ATTACHMENT 1 ATTACW.ENT 1
   \                                                      UNUSUAL EVENT CALL LIST E

DIRECTIONS The EDO/ Senior Shift Supervisor or his designet shall complete the below description of the event and make those notifications as indicated by the asterisk. The Assistant to Manager / designee will make the remaining notifications, including a call back to the Senior Shift Supervisor indicating completion.

                                                            . .---------------               ___=.                  .           =..-     -
       .---                      =....--...

PRIMARY INITIATING CONDITION (from Accident Classification Guide, i.e. , EP I, Part 2, No. 5) EP I-0, PART , NO. BRIEF DESCRIPTION OF EVENT: NOTE In the event of a test, drill or exercise, preface and complete each message with the phrase "THIS IS A DRILL, THIS IS A DRILL".

       -.      .. ............-                    ... .----....-----.---------                    _ _ - - - - - - - - - - . . - - - - -    ~~~---

PERSON CONTACTED CALLER TIME /DATE O '2. *NRC LENS)

3.

ASSISTANT TO MANAGER

4.

LAC DISPATCHER

5. BPU

6. GENERAL MANAGER - INFO SERVICES

7. NRC RESIDENT

8. DOE (N.J.)

9. SENIOR SHIFT SUPERVISOR NOTE

1. Refer to Addendum No. 1 of the Emergency Plan for required phone numbers.

2. * = Calls to be made by Senior Shift Supervisor, Shift Supervisor or other technical personnel.

3. Return both attachments to the Assistant to Manager.

Reviewed Byt O Manager - Salem Generating Station Page 3 of 4 Rev. 1

l EP I-l ATTACHMENT 2 O ATTACHMENT 2 INITIAL CONTACT MESSAGE FO $ DIRECTIONS FOR COMMUNICATOR Upon completion of the below prepared message by the EDO/ Senior Shif t Supervisor or his designee the assigned consnunicator shall make the required notifications. No additional information is required to be given at this time. Requests for further information should be directed to the Assistant to Manager or the Public Information Offices. PRIMARY INITIATING CONDITION (from Accident Classification Guide, i.e., EP I, Part 2, No. 51 EP I-0, PART , NO. NFTE 1 l In the event of a test, drill or exercise, preface and complete each message with the phrase "THIS IS A DRILL, THIS IS A DRILL". PERSON CONTACTED CALLER TIME /DATE

1. STATE OF NEW JERSEY (STATE POLICE)

2. DELAWARE (STATE POLICE)

PR VACY ACT O L, , .O.1MK.IO N,

l l THIS IS _ . l (N AME) (TITLE) j SALEM NUCLEAR GENERATING STATION, UNIT NO. THIS IS A NOTIFICATION OF: U an UNUSUAL EVENT C a SITE ADIA EMERGENCY R an ALERT a GENERAL EMERGENCY THE EVENT OCCURRED AT . on THERE IS NO RELEASE IN PROGRESS. ! WE HAVE A CONTROLLED RELEASE IN PROGRESS. _____ U___ W_E HAVE AN UNCONTROLLED RELEASE IN _____________________________________________ PROGPESS. ______________________ NO PROTECTIVE ACTIONS ARE PIC0ffENDED.

    %            R WE RECOMMEND SHELTEPING FOR THE FOLLOWING SECTOR (S)                                                                              /

(Distance-Miles) 4 U WE REC 0lt1END EVACUATION FOR THE FOLLOWING SECTOR (S) . / (Distance-Miles) NCfrE Return completed attachment to the Assistant to Manager. l l- - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ frm 0 og 0 ED% 8

EP I-2 EMERGENCY PROCEDURE ( )) EP l-2 ALERT The purpose of an " alert" status is to assure that amargency personnel are readily available to respond if an emergency status degrades, perform confirmatory radiation monitoring and provide off-site authorities with current status information. NOTE Refer to EP I-0, " Accident Classification Guide" for possible escalation to a higher level accident classification or fJr deescalation to a lower level accident classification. Notification of a change in the emergency classifi-cation shall be conveyed via the " Initial Contact Message Form" (Attachment No. 1). Termination of the emergency response and initiation of the recovery phase shall be conveyed via the " Termination Call List" (Attachment No. 4). ACTION STATEMENTS 11gE' TNITfAL

1. If necessary, sound Radiation Alert Alarm, announce if possible, the O nature of the alert. Request evacuation of affected area (s) if necessary.

2. Announce via the plant Public Address System (P. A.) : "Radition Protection personnel report to your amergency duty stations".

3. Contact the Shift Radiation Protection Technician (Shift RPT) and direct him to initiate procedure EP IV-101 (Radiation Protection Initial TSC Response).

4. Complete the " Initial Contact Message Form" (Attachment No. 1).

Protective Action Recommendations are to be based upon EP IV-108 as inforr.ation becomes available.

5. Direct the communicator to transmit the " Initial Contact Message Form" (Attachment No. 1) in accordance with contained instructions.

O l I Page 1 of 14 Rev. 1 l

EP I-2 ACTION STATEMENTS (CONTINUED) I.121E' INITIAL

6. Es a) New Jersey / Delaware State Police cannot be contacted, E b) Local contact is requested by New Jersey / Delaware State authorities.

THEN: Directly contact Salem and Cumberland Counties in New Jersey, Kent and New Castle Counties in Delaware and/or U.S. Coast Guard. Instruct the communicator that the information transmitted to the Counties shall be in the form of the " Initial Contact Message Form" (Attachment No. 1). Also instruct the communicator that any additional inquiries shall be referred to the respective state emergency manage-ment agencies.

7. Direct a qualified individual to complete the " Station Status Checklist" (Attac.'unent No. 3) . Coordinate Emergency Dose Calculations and completion of Attachment No. 3 with the Shift RPT.

8. Initiate the Alert Call List (Attachment No. 2). l l

l l

9. If the EDO/ Senior Shift Supervisor decides to a-tivate the EOF: l l

a) Contact Plant Manager or his designee and advise him to implement EP II-4, Notification of Corporate Response Personnel. b) If Plant Manager or designee cannot be reached the ED0/ Senior Shift Supervisor shall assume responsibility for implemencing EP II-4. c) Dispatch a Security Guard to open the facility as per EP III-2. Page 2 of 14 Rev. 1

 .                                                                                                      EP I-2 O. 6CTION STATEMENTS (c0NTINUED) f:         11dE' INfTIAL

10. Upon receipt of a phone call from the New Jersey Bureau of Radia: ion Protection (BRP) or Delaware Division of Emergency Planning and Operations (DEPO) da the followings s

a) Provide the " Station Status Checklist" at current level of completion. b) Exchange contact phone numbers for future updates /information.

11. Initiate the EDO Checklist (Figure No. 1).

12. Direct a communicator to proceed to the activated TSC and initiate 15 minute updates to New Jersey BRP and Delaware DEPO. Updates shall be in the form of the " Station Status Checklist" (Attachment Nc. 3) as information becomes available.

[}

13. If necessary, account for personnel in accordance with EP I-8.

14. Direct a technically qualified person to commence data collection in accordance with the Operational and Radiological Status Boards (Figure No. 3 and No. 4, respectively). Transmit this data t.) the TSC and EOF.

15. Contact the Assistant to Manager / designee and advise him to appraise the State Board ot Public Utilities and Department of Energy of the emergency event.

16. If the EOF is activated, transfer the responsibility of the 15 minute notifications to the States and the coordination of off-site survey teams to the EOF staff. Update the EOF Manning Chart (Figure No. 2) as appropriate.

O Page 3 of 14 Rev. 1

EP I-2 8CTION STATEMENTS (CONTINUED) / 11gg* fNYTIAL

17. complete the procedure steps as follows:

a) Radiological Emergencies (18 through 25) b) operational Emergencies (26 through 29) c) Fire / Natural / Security Emergencies (30 through 36) d) Miscellaneous Emergencies (37 through 40) NOTE The previous steps are intended to place personnel on standby in the event of a radiological release. [} Dispatching survey teams may not be required at this tLme. RADf0LOCfCAL

18. Coordinate emergency on and off-site radiation surveys in accordance with Radiation Protection Procedure EP IV-110 with the Shift RPT and/

or the Radiation Protection personnel assigned to the TSC.

19. If a radioactive spill caused the emergency, refer to EP I-6.

20. Insure the actions required of Emergency Instruction I-4.16 (Radiation Incident) are or have been taken as applicable.

21. If a fuel handling 'cident occurred, refer to EI I-4.25 (Fuel Handling Incident).

A Page 4 of 14 Rev. 1

EP I-2 8CTION STATEMENTS (CONTINUED) O IlgE* INITIAL RADIOLOGICAL (CONTINUED)

22. If any personnel have been injured or exposed to radiation in excess of 10CFR limits, refer to EP I-5 (Personnel Emergency). ,

23. If site evacuation becomes necessary, evacuate in accordance with EP I-12.

24. Complete an Operational Incident Report in accordance with Administrative Procedure No. 6.

25. Upon termination of the event complete the " Termination Call List",

Attachment No. 4 and initiate recovery operations, EP I-14, as necessary. OPERATIONAL

26. If the Reactor Protection System fails to bring the plant to Mode 3 when required refer to EI I-4.3 (Reactor Trip).

27. On a loss of on or off-site power systems, as noted in the Action Levels, refer to EI I-4.9 (Blackout) .

28. Complete an Operational Incident Report in accordance with Administrative Procedure No. 6.

l t l 29. Upon termination of the event complete the " Termination Call List", Attachment No. 4 and initiate recovery operations, EP I-14, as necessary. l O Page 5 of 14 Rey, 1

EP I-2 ACTION STATEMENTS (CONTINUED) 11gE* INITfAL FIRE / NATURAL / SECURITY

30. If the Delaware River level is greater than 10.0 fest MSL (99 feet PSEsG datum) and is approaching 11.5 feet MSL (100.5 feet PSEIG datun);

a) Implement Emergency Instruction EI I-4.1 (Flooding and/or High Winds). b) If necessary, evacuate the site in accordance with E" I-12.

31. If sustained winds are predicted to be 95 mphs a) Implement Emergency Instruction EI I-4.1 (Flooding and/or High Winds).

O b) If necessary, evacuate the site in accordance with EP I-12.

32. If a seismic event occurs with a foret greater than 0.lg but less than 0.2g consider implementing 0I-1.3.5 or 1.3.6, as appropriate (Power Operation to Hot Standby, Hot Standby to Cold Shutdown).

33. Refer to EP I-7, " Station Fire", to conduct fire fighting actions.

34. If outside assistance is required call the Salem Fire Dispatcher j (609-935-4505). Give the location and type of fire and where vohicles will be met by the security personnel. Alert security of incoming emergency vehicles.

35. Complete an Operational Incident Report la accordance with Administrative Procedure No. 6.

36. Upon termination of the event complete the " Termination Call List",

() g Attachment No. 4 and initiate recovery operations, EP I-14, as necessary. Page 6 of 14 Rev. 1

EP I.2 ACTION STATEMENTS (CONTINUED) Il5E' INITIAL MfSCELLANEOUS

37. If toxic gas, e.g., chlorine, acid vapors, etc., present a safety hazard contact Performance Engineer and/or Senior Supervisor-Chemistry, for further direction. (Phone numbers may be found in Addendu- No.1) .

38. If the Control Room must be evacuated for any reason refer to EI I-4.10 (Control Room Evacuation).

39. Complete an Operational Incident Report in accordance with Adainistrative Procedure No. 6.

40. Upon termination of the event complete the " Termination Call List",

Attachment No. 4 and initiate recovery operations, EP I-14, as necessary. O Completed By: Senior Shift Supervisor /EDO Date W FORWARD ALL COMPLETED FORMS TO THE ASSISTANT TO MANAGER. ATTACH ANY REFERENCED COMPLETED EP'S OR ATTACHMENTS. l l O t i l ! Page 7 of 14 Rev. 1

l l l EP I-2 Prepared By: j p fff f,

                             -g        ,, ,-

Reviewed By: /0/26)8/

                                                             < Date Depdf ent Head Reviewed By:                                            fo[gg )pf Ass' fant to Manager            '

Date Reviewed By: .

                                                            !O N       (

titiMuality Assurance Engineer Date SORC Meeting No.: b f- Ill /0/27!I/ Date Approved By: / gg[g Managsfr - Aalem' Generating Station Dat( Approved By: - h b e asf 8[ Manager - Enfergency Prepiredness

                                                                  # #V Date O

1 1 I O) u Page 8 of 14 pey, 1

4 l EP I-2 ATT. 1 !O ATTacanait i INITIAL CONTACT MESSAGE F0Pf ) DIRECTIONS: This fotle will be filled out by the Senior Shift Supervisor /EDO and given to a communicator for transmittal to the States of New Jersey and Delaware. i j IS U IS "THIS U IS NOT A DRILL" "THIS U IS NOT A DRILL" 4,

THIS IS * '

(Title) (Name) SALEt1 NUCLEAR GENERATING STATION, UNIT NO. 1 1 THIS IS NOTIFICATION OF: ) ) an UNUSUAL EVENT l-]aSITEAREAEPIRGENCY 1 4 i l O an ALERT {_] = GEllEP.AL EMERGENCY l THE EVENT DECLARED AT ON Tram.-24 hour clocx) (Date) THERE IS NO RELEASE IN PROGRESS. l WE HAVE A CONTROLLED RELEASE IN PROGP.ESS. i l WE HAVE AN UNCONTROLLED RELEASE IN PROGPISS. I NO PROTECTIVE ACTIONS ARE REC 0r7 ENDED AT THIS TIME.

WE RECOPMEND SHELTERING FOR THE FOLLOWING SECTOR (S) (Distance / Males)

i WE RECOPMEND EVACUATION FOR THE FOLLOWING SECTOR (S) j (Distance / Miles) i 4 i Completed By: Senior Shift Supervisor /EDO

O i Transunitted By:

Communicator l Page 9 of 14 Rev. 1

 /      -

EP I-2 ATT. 1 PROCEDURE AND CAlt. LIST FOR C0!TUNICATOR TfME NAME OF PER3Cri CONTACTED .

l. Contact New Jersey state Police lis ~0RMA"l0N Road Initial Contact Message Form.

2. Contact Delaware State Police Read Initial Contact Message Form.

3. Contact General Manager - Infomation Services Primary: Addendum No. 1 Read Ir.itial Contact Mer. sage Form.

4. Inform Senior Shift Supervisor which calls were completed.

Qtill IF DIRECTED BY THE SENIOR SHIFT SUPERVISOR MAKE FOLLOWING CALLS. NEW JERSEY COUNTfES O 3RIVACY AC" E0RVA".0X ,,,,I,1,1,1 ,,,,,, ,,,,,,, ,, . 3RVACY ACT E0 RV A".0N Road Initial Contact Message Fom. DELAWARE COUNTIES New Castle County EOC TI'ORV'ATON Read Initial Contact Message Form. PR VACY ACT

                                     'N 0 R V A~'l0 N'
                                        '    '  '          l      Road Initial Conteet Message Form.

l

                                      ]    f .g           =*      U.S. Coast Guard iWi OLAii0ii Tage 10 of 14                                         Rev. 1

I EP I 2 l l ATT. 2 l i l l ATTACHMENT 2 ([]) ALEP.T CALL LIST DIRECTIONS: The EDC/ Senior Shif t Supervisor shall complete the below information and insure the following communications are completed. Advise and direct those centacted l based upon discussion with the EDO. PRIMARY INITIATING CONDITION (from Accident Classification Guide, i.e., EP I, Part 2, No. 5) EP I.0, PART , NO. TIME /DATE EVENT DECLARED (2400 Hours) BRIEF DESCRIPTION OF EVENT: NOTE In the event of a test, drill or exercise, preface and complete each message with the phrase "THIS IS A DRILL, THIS IS A DRILL". CONTACT CALLER TIME

1. Emergency Duty Officer (EDC) *

() 2. 3. NRC (ENS Line to .Bethesda) Station Manager

4. Chief Engineer / Operating Engineer

5. Station Security

6. Salem visitors Center

7. Hope Creek (Union Security)

8. Technical support - On-site

9. NRC Resident NOTE Refer to Addendum No.1 for all phone / beeper numbers.

Advise the Primary EDO to notify the secondary EDO (Technical Support Supervisor) .

Completed By: Reviewed By: Senior Shaf t Superrvisor/Shif t Supervisor /EDO Forward completed copies to the Assistant to Manager. l l 1 Page 11 of 14 Rev. 1

i EP I-2 ATT. 3 ATTACRP.ENT 3 O ALEaT STATION STATUS CHECKLIST Reactor and Unit No.

1. Date and Time of Incident: Date Time (24 Hour Clock)

2. Accident Classification: ALERT

3. System Involved:

a) ( ) Reactors or b) ( ) Radioactive Waste Systems (circle one) Caseous Liquids or c) ( ) Fuel Handling (circle one) ruel Handling Building Containment

4. Cause of Incident (if known):

O

5. Is Reactor Tripped: (circle ene) Yes No

6. Gaseous Release Information (complete as required) :

a) Release terminated (circle one) Yes No b) Anticipated or Known Duration of Release hours. c) Type of Releases (circle one) Ground Elevated d) wind Speeds aph Wind Directions (toward) Divide by 2 to get m/sec (from) (Compass Points) e) Stability Class: ( ) Unstable ( ) Neutral ( ) Stable f) Release Rate Iodine Ci/sec g) Release Rate Noble Cass C1/sec

7. Liquid Release Information (complete as required):

a) Release Terminated: (circle one) Yes No b) Anticipated or Known Duration of PT'?Tse hours. c) Estimated concentration , pico Curies / liter.

8. Recommended Of f-Site Actions (as soon as data is available) :

Use attached Worksheet.

9. Status checklist Data Relayed to Delaware States (date/ time),

(by), To: (name).

10. Status checklist Data Relayed to New Jersey (date/ time) ,

(by), To: (name) . 11. () Status Checklist Data Relayed to Information Services (PIO): (by), To: (date/ time), (name) .

12. Proceed to Supplemental Station Status Checklist as information becomes available (see Addendum No. 2).

Page 12 of 14 Rev. 1

EP I-2 ATT. 3 NORTH NNW 10 mi. 9 NE

8 -

NW ~

7

6 5 gng CHW 4 I

                                                                      %          Y/

l % , g W % i I \ ESE WSW

o i SW RECORDER COMPASS WIND TROM DIRECTION FFOM S S E 34 8 J/ 4 to 11 1/ 4 ' N SSW gg 1f4 g, 33f3f4 NNE SOUTH 33 3/4 to 56 1/4' NE 56 1/4 to 78 3/4' ENE 78 3/4 to 101 1/4* E 101 1/4 to 123 3/4' ESE l 123 3/4 to 146 1/4' SE 146 1/4 to 168 3/4* Ssr 168 3/4 to 191 1/4* S 191 1/4 to 213 3/4* SSW 213 3/4 to 236 1/4' sw 236 1/4 to 258 3/4' WSW 258 3/4 to 281 1/4* W 281 1/4 to 303 3/4' WNW 303 3/4 to 326 1/4* NW RECOMMENDED PROTECTIVE ACTIONS WORKSHEET 326 1/4 to 348 3/4' NNW Designt.te areas and/or sectors with reconnended protective actions symbols as follows: S - Take shelter F - Food, water and silk control E - Evacuate 0 - Other (specify) Time Wind Direction Wind Speed (from) O completed By: Reviewed By: SSS/EDO/ERM Page 13 of 14 Rev. 1

EP I-2 ATT. 4 ATTACHMENT 4 , ([]) TERMINATION CALL LIST A. An emergency situation may only be terminated when the following conditions are met:

1. No action levels for Alert, Site or General Emergency are applicable.

I .

2. Affected unit returned to normal or long term recovery status.

3. Concurrence of the state of New Jersey.

Contact Time /Date

4. Concurrence of the state of Delaware.

Contact Time /Date

5. Concurrence of the Emergency Response Manager. ;

Emergency Response Manager Time /Date l B. Contact the listed individuals / agencies and report the following message: THIS IS . AT SALEM NUCLEAR i (Name) (Title) GENERATING STATION UNIT No. . THIS IS TO NOTIFY YOU THAT THE ALERT ,

                                                  .                                  (1 or 2)                                                                                          ;

AT THIS FACILITY HAS BEEN TERMINATED EFFECTIVE (Time-24 Hour) (Date) REPEAT, THE ALERT AT SALEM NUCLEAR GENERATING STATION HAS BEEN TERMINATED. I CONTACT CALLER TIME

1. State of New Jersey (Bureau of Radiation Protection)

2. State of Delaware (Division of Emergency Planning and operations)

3. NRC (ENS Line)

                *4. Station Manager
                *5. NRC Residsnt                                                                                                                                       __
                '6. General Manager -

Information Services

                *7. BPU
                *8. EA
                *9. DOE (New Jersey)

NOTE: The EDO is responsible for completing Part A of this Attachment. Part B may be completed by any designated individual.

                 *See Addendum No.1 for the required phone numbers.

Reviewed By: Emergency Duty officer Date () Forward completed sheets to the Assistant to Manager. Page 14 of 14 Rev. 1

EP I-3 EMERGENCY PROCEDUDE O EP l-3 SITE AREA EMERGENCY The purpose of a " site area" status is to assure that emergency personnel respond if events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. NOTE Refer to EP I-0, " Accident Classification Guide" for possible escalation to a higher level accident classification or for doescalation to a lower level accident classification. Notification of a change in the emergency classifi-cation shall be conveyed via the " Initial Contact Message Form" (Attachment No. 1). Termination of the emergency response and initiation of the recovery phase shall be conveyed via the " Termination Call List" (Attachment No. 4). ' l I ACTION STATEMENTS IlgE' INfTfAL 1. O -If necc sary sound Radiation Alert Alarm, announce if possible, the nature of the alert. Request evacuation of affected area (s) if necessary.

2. Announce via the plant Public Address System (P. A.) : "Radition Protection personnel report to your emergency duty stations".

3. Contact the Shift Radiation Protection Technician (Shift RPT) and direct him to initiate procedure EP IV-101 (Radiation Protection Initial TSC Response).

4. Complete the " Initial Contact Message Form" Attachment No. 1.

Protective action recommendations are to be based upon EP IV-108 as information becomes available.

5. Direct the communicator to transmit the " Initial Contact Message Form" (Attachment No. 1) in accordance with contained instructions.

O V Page 1 of 14 Rev. 1

EP I-3 ACTION STATEMENTS (CONTINUED) M' INITfAL

6. g:

a) New Jersey / Delaware State Police cannot be contacted, g b) Local contact is requested by New Jersey / Delaware State authorities. 4 THEN: i Directly contact Salem and Cumberland Counties in New Jersey, Kent and New Castle Counties in Delaware and/or U.S. Coast Guard. I Instruct the conununicator that the information transmitted to the Counties shall be in the form of the " Initial Contact Message Form" (Attachinant No.1) . Also instruct the communicator that any additional ] inquiries shall be referred to the respective state emergency manage-ment agencies.

7. Direct a qualified individual to complete the " Station Status Checklist" (Attachment No. 3). Coordinate Emergency Dose Calculations and completion of Attachment No. 3 with the Shift RPT.

l 9

8. Initiate the Site Area Emergency Call List (J.ttachment No. 2).

9. Initiate corporate notification:

I l l l al Contact Plant Manager or his designee and advise him to implement EP II-4, Notification of Corporate Response Personnel, b) If Plant Manager or designee cannot be reached the EDO/ Senior Shift Supervisor shall assume responsibility for implementing EP II-4. c) Dispatch a Security Guard to open the EOF as per EP III-2. Page 2 of 14 Rev. 1

l EP I-3 ACTION STATEMENTS (CONTINUED) IlgE' fNfTIAL )

10. Upon receipt of a phone call from the New Jersey Bureau of Radiation Protection (BRP) or Delaware Division of Emergency Planning and operations (DEPO) do the followings a) Provide the " Station Status Checklist" at current level of completion.

b) Exchange contact phone numbers for future updates /information.

11. Initiate the EDo checklist (Figure No. 1).

12. Direct a communicator to proceed to the actuated TSC and initiats 15 minute updates to New Jersey BRP and Delaware DEPO. Updates shall be in the form of the " Station Status Checklist" (Attachment No. 3) as information becomes available.

O

13. If necessary, account for personnel in accordance with EP I-8.

14. Direct a technically qualified person to commence data collection in accordance with the operational and Radiological Status Boards (Figure No. 3 and No. 4, respectively). Transmit this data to the TSC and ECF.

15. Contact the Assistant to Manager / designee and advise him to appraise the State Board of Public Utilities and Department of Energy of the emergency event.

16. When the EOF is activated, transfer the responsibility of the 15 minute notifications to the States and the coordination of off-site survey teams to the EOF staff. Update the EOF Manning Chart (Figure No. 2) as appropriate.

Page 3 of 14 Rev. 1

EP I-3 ACTION STATEPENTS (CONTINUED) IltE' INITIAL

17. Complete the procedure steps as follows:

1 a) Radiological Emergencies (18 through 25) b) Operational Emergencies (26 through 29) c) Fire / Natural / Security Emergencies (30 through 36) d) Miscellaneous Emergencies (37 through 40) NOTE The previous steps are intended to place personr:e1 on

  %                               standby in the event of a radiological release.

Dispatching survey teams may not be required at this time. RADf0 LOGICAL

18. Coordinate emergency on and off-site radiation surveys in accordance with Radiation Protection Procedure EP IV-110 with Shift RPT and/or the Radiation Protection personnel assigned to the TSC/OSC.

19. If a radioactive spill caused the emergency, refer to EP I-6.

20. Insure the actions required of Emergency Instruction I-4.16 (Radiation Incident) are or have been taken as applicable.

{

21. If a fuel handling incident occurred, refer to EI I-4.25 (Fuel Handling Incident).

I O l l Page 4 of 14 Rev. 1

EP I-3 l l

    $CTION STATEPINTS (CONTINUED)

M' fNfTfAL RADIOLOGICAL (CONTINUED)

22. If any personnel have been injured or exposed to radiation in excess of 10CFR limits, refer to EP I-5 (Personnel Emergency). ,

23. If site evacuation becomes necessary, evacuate in accordance with EP I-12.

24. Complete an operational Incident Report in accordance with Administrative Procedure No. 6.

25. Upon termination of the event complete the " Termination Call List",

Attachment No. 4 and initiate recovery operations, EP I-14. n STAT 10NAL O'

26. If the Reactor Protection System fails to bring the plant to Mode 3 when required refer to EI I-4.3 (Reactor Trip).

27. On a loss of on or off-site power systems, as noted in the Action Levels, refer to EI I-4.9 (Blackout).

28. Complete an Operational Incident Report in accordance with Administrative Procedure No. 6.

29. Upon termination of the event complete the " Termination Call List",

Attachment No. 4 and initiate recovery operations EP I-14. l O l Page 5 of 14 Rev. 1

EP I-3 ACTION STATEMENTS (CONTINUED) C IJgE' fNfTfAL Ff RE/ NATURAL /REEUR f TY

30. For Delaware River flood conditions reaching or exceeding 11.5 feet MSL (100.5 feet PSE&G datum): ,

a) Implement Emergency Instruction EI I-4.1 (Flooding and/or High Winds). b) If necessary, evacuate the site in accordance with EP I-12.

31. For sustained high winds (elevation 33 feet) 100 mpn:

a) Implement Emergency Instruction EI I-4.1 (Flooding and/or High Winds) . O b) If necessary, evacuate the site in accordance with EP I-12.

32. For seismic events in excess of 0.2g (design basis) implement CI-3.5 or 3.6 (Power Operation to Hot Standby, Hot Standby to Cold Shutdown).

33. Refer to EP I-7, " Station Fire", to conduct fire fighting actions.

34. If outside assistance is required call the Salem Fire Dispatcher (609-935-4505). Give the location and type of fire and where vehicles will be met by the security personnel. Alert security of incoming emergency vehicles.

35. Complete an operational Incident Report in accordance with Administrative Procedure No. 6.

7g 36. Upon termination of the event complete the " Termination Call List", (s,) Attachment No. 4 and initiate recovery operations, EP I-14. Page 6 of 14 Rev. 1

l l l EP I-3 ACTION STATEPENTS (CONTINUED) 11gg* INfTIAL Mf5CELLANE00S

37. If toxic gas, e.g., chlorine, acid vapors, etc., present a safety hazard contact Performance Engineer and/or Senior Supervisor-Chemistry, for further direction. (Phone numbers may be found in Addendam No.1) .

38. If the Control Room must be evacuated for any reason refer to EI I-4.10 (Control Room Evacuation).

39. Complete an Operational Incident Report in accordance with Administrative Procedure No. 6.

40. Upon termination of the event complete the " Termination Call List",

Attachment No. 4 and initiate recovery operations, EP I-14. O Completed By: Senior Shif t Supervisor /EDO Date fl0TE FORWARD ALL COMPLETED FORMS TO THE ASSISTANT TO MANAGER. ATTACH ANY REFERENCED COMPLETED EP'S OR ATTACHMENTS.

        .....                    - .==-- ==                                                                       - -......................

O Page 7 of 14 Rev. 1

L_ -- . - - - - - - - - - - - - - - - - - - .- --

EP I-3 i O t Prepared By: Xeyr - _ _ /> A Reviewed By: f 0f 26 fF/ r ~ Depi

e t Head Date Reviewed By: M /0f24!P/

Assisitant to Manager Date Reviewed By

                                                      !        b!h[

Date Statiol Qualaty Assurance Engineer SORC Meeting No. bl

I/l /o/27 f 8 /

                                                          ' Dat'e Approved By:               /                            / /T k Managev- Salem Generating Station     / 'Date Approved By:          *

JW ff I!2. 0 #V Manager - Emergency Preparedness Date O

o l l Page 8 of 14 Rev. 1

EP Z 3 l ATT. 1 l l ATTACHFINT 1 O INITIAL CONTACT PISSAGE FOPr. DIRECTIONS: This form will be filled out by the Senior Shift Supervisor /EDO and given to a consnunicator for transmittal to the States of New Jersey and Delaware. U IS U IS "THIS U IS NOT A DRILL" "THIS U IS NOT A DRILL" THIS IS . (name) (Title) SALEM NUCLEAR GENERATING STATION, UNIT NO. THIS IS NOTIFICATION OF: an UNUSUAL EVENT l._] a SITE APIA EFERGENCY U = GENERAL EMERGENCY O ---______ an ALERT THE EVENT DECLARED AT .(Time-24 hour (Date) clock) ON THERE IS NO RELEASE IN PROGRESS. WE HAVE A CONTROLLED RELEASE IN PROGPISS. WE HAVE AN UNCONTROLLED RELEASE IN PROGRESS. NO PROTECTIVE ACTIONS ARE RECOMPINDED AT THIS TIFI. WE RECOMMEND SHELTERING FOR THE FOLLOWING SECTOR (S) / (Distance / Miles) U WE RECOPPIND EVACUATION FOR THE FOLLOWING SECTOR (S)/

   ---__-__-__--__---___--_____---_-.__--__-__-________-_---                          -- -__-_---   (D25tane! M 11581 ____.--_

Completed By: Senior Shift Supervisor /EDO O Transmitted By: Ccamunicator Page 9 of 14 Rev. 1

IP I-3 ATT. 1 PROCEDURE AND CALL LIST FOR C0FfUNICATOP. TfMF NAME OF PERSON CONTACTED -

1. Contact New Jersey State Police PR VACY ACT IN 20 RV A~ ON

2. Contact Delaware State Police 3RVACY ACT N :0 RMA~ 0 N

3. Contact General Manager - Information Services Primary: Addendum No. 1 Road Initial Contact Message Form.

4. Inform Senior Shift Supervisor which calls were completed.

OliL1 IF DIRECTED BY THE SENIOR SHIFT SUPERVISOR MAKE FOLLOWING CALLS. NEW JERSEY COUNTfES Salem County EOC 311VACY AC" IN :0 RN A~ 0 N

                                               .                    Cumberland County EOC 3RiVACY ACT IN :0RVK10N DELAWARE COUNTIES New Castle County EOC PR VACY AC" IN :0 R VK' O N Eent County EOC PR VACY AC" IN:0RMK10N

( U.S. Coast Guard PR VACY ACT IN:01VK~ Oh Page 10 of 14 Rev. 1

EP I-3 ATT. 2 ATTACHMENT 2 ([]) SITE AP.EA CALL LIST DIRECTIONS: The EDO/ Senior Shift Supervisor shall complete the below information and insure the following communications are completed. Advise and direct those contacted based upon discussion with the EDO. PRIMARY INITIATING CONDITION (from Accident Classification Guide, i.e. , EP I, Part 2, No. 5) EP I_0, PART , NO. TIME /DATE EVENT DECLARED (2400 Hours) BRIEF DESCRIPTION OF EVENT:

 !                                                             NOTE In the event of a test, drill or exercise, preface and complete each message with the phrase "THIS IS A DRILL, THIS IS A DRILL".
          .      ...__ ==          . . . . .                 ...    ..____. .......________......____            =      .....

CONTACT CALLER TIME

1. Emergency Duty Officer (EDO)*

2. NRC (ENS Line to Bethesda)

{}

3. Station Manager

4. Chief Engineer / Operating Engineer

5. Station Security

6. Salem Visitors Center

7. Hope Creek (Union Security)

8. Technical Support . On-site

9. NRC Resident NOTE Refer to Addendum No. 1 for all phone / beeper numbers.

Advise the Primary EDO to notify the secondary EDO (Technical Support Supervisor) .

Completed By: Reviewed By: Senior Shif t Supervisor /Shif: Supervisor /EDO t Forward completed copies to the Assistant to Manager. l l Page 11 of 14 Rev. 1

a EP I-3 i ATT. 3 ATTACHMENT 3 ()) SITE AREA EMEP.GENCY

STATION STATUS CHECKLIST l

Reactor and Unit No. l

1. Date and Time of Incident: Date Time (24 Hour Clock)

2. Accident Classification: SITE AREA EMERGENCY

3. System Involved:

i a) ( ) Reactors or b) ( ) Radioactive Waste Systems (circle one) Gaseous Liquids or c) ( ) Puel Handling (circle one) Puel Handling Building Containment 4. Cause of Incident (if known) : l I 1 i

;O i

5. Is Reactor Tripped: (circle one) Yes No

6. Gaseous Release Information (complete as required):

a) Release terminated (circle one) Yes No b) Anticipated or Known Duration of Release hours. c) Type of Releases (circle one) Ground Elevated d) Wind Speeds sph Wind Directions (toward) Divide by 2 to get m/sec (from) (Compass Points) el Stability Class ( ) Unstable ( ) Neutral ( ) Stable f) Release Rate Iodine: Ci/sec g) Release Rate Noble Gas Ci/sec

7. Liquid Release Information (complete as required):

a) Release Terminated: (circle one) Yes No b) Anticipated or Known Duration of Release hours. c) Estimated Concentration pico Curies / liter.

8. Recommended Off-Site Actione (as soon as data is available):

Use attached Worksheet.

9. Status Checklist Data Relayed to Delaware States (date/ time),

(by), To: (name).

10. Status checklist Data Relayed to New Jerseys (date/ time),

j (by), To: (name) .

11. S:atus checklist Data Relayed to Information Services (PIO): (date/ time),

(by), To: (name).

12. Proceed to Supplemental Station Status Checklist as information becomes available (see Addendam No. 2).

Page 12 of 14 Rev. 1

EP I-3 ATT. 3 NORTH NNW 10 mi. 9 9 ', .. gg

-                                          7
;-                                         6 l

5 ENE , UNW 4/ 3 2 I W l

                                               \                                   ESE MSW I        \

l O SW I \ SE RECORDER COMPASS WIND FROM DIRECTION FROM J48 3/4 to 11 1/4 N SSW SSE gg gjg g,33f3f4.' 33g SOUTH 33 3/4 to 56 1/4' NE 56 1/4 to 78 3/4' ENE 78 3/4 to 101 1/4' E 101 1/4 to 123 3/4' ESE 123 3/4 to 146 1/4' SE 146 1/4 to 168 3/4' SSE 168 3/4 to 191 1/4* 5 191 1/4 to 213 3/4' SSW 213 3/4 to 236 1/4* SW , 236 1/4 to 258 3/4' WSW ! 258 3/4 to 281 1/4* W 281 1/4 to 303 3/4' WNW ) 303 3/4 to 326 1/4' NW i REC 050dENDED PROTECTIVE ACTIONS WORKSHEET 326 1/4 to 348 3/4' NfM I Designate areas and/or sectors with recommended protective actions symbols as follows: S - Take shelter F - Food, water and milk cc-tr:1 E - Evacuate 0 - Other (specify) l Time Wind Direction Wind Speed (from) Completed By: Reviewed By: SSS/EDO/ERM Page 13 of 14 Rev. 1

EP I-3 ATT. 4 ATTACHMENT 4 ((() TERMINATION CALL LIST A. An emergency situation may only be terminated when the following conditions are met: l 1. No action levels for Alert, Site or General Emergency are applicable. l

2. Affected unit returned to normal or long term recovery status. i

3. Concurrence of the state of New Jersey.

Contact Time /Date

4. Concurrence of the state of Delaware.

Contact Time /Date

5. Concurrence of the Emergency Response Manager.

Emergency Response Manager Time /Date B. Contact the listed individuals / agencies and report the following message: THIS IS AT SALEM NUCLEAR (Name) (Title) GENERATING STATION UNIT NO. . THIS IS TO NOTIFY YOU THAT THE SITE (1 or 2) AREA EMERGENCY AT THIS FACILITY HAS BEEN TERMINATED EFFECTIVE - (Time-24 Hour)

                              . REPEAT, THE SITE AREA EMERGENCY AT SALEM NUCLEAR GENERATING (patel STATION HAS BEEN TERMINATED.

CONTACT CALLEK TIME

1. State of New Jersey (Bureau of Radiation Protection) 1

2. State of Delaware (Division of Emergency Planning and Operations)

3. NRC (ENS Line)

        *4. Station Manager
        *5. NRC Resident
        *6. General Manager -

Information Services

        *7. BPU 1
        *S. QA
        *9. DOE (New Jersey) f        NOTE: The EDO is responsible for completing Part A of this Attachment. Part B may be completed M                by any designated individual.
        *See Addendum No.1 for the required phone numbers.

Reviewed By: 1 ( Emergency Duty Officer Date l Forward completed sheets to the Assistant to Manager. Page 14 of 14 Rev. 1

EP I-4 l EMERGENCY PROCEDURE EF 1-4 GENERAL EMERGENCY A general emergency has occurred if events are in process which involve substantial core degradation with the potential loss of Containment integrity. The purpose of the General Emergency Procedure is tot initiate predetermined protective actions for the public provide continuous assessments of on-site radiological measurements; initiate additional actions as , required for actual or potential releases and provide current information for and consultation with the Emergency Operations Faci'.ity (EOF). NOTE Refer to EP I-0, " Accident Classification Guide" for deescalation to a lower level accident classification. Notificaticn of a change in the emergency classification shall be conveyed via the " Initial Contact Message Form" (Attachment No. 1). Termination of the emergency response and initiation of the recovery phase shall be conveyed via the "TermLnation Call List" (Attachment No. 4). ACTION STATEMENTS M' INfTIAL

1. If any of the conditions exist as described in Attachment 5, " Plant Parameters Requiring Protective Action Recommendations", immediately transmit the required recommendations to the appropriate State and/or County officials via Attachment No. 1.

2. Sound Radiation Alert Alarm, announce if possible, the nature of the alert. Request evacuation of affected area (s) if necessary.

3. Announce via the plant Public Address System (P. A.) : "Radition Protection personnel report to your emergency duty stations".

4. Contact the Shift Radiation Protection Technician (Shift RPT) and direct him to initiate procedure EP IV-101 (Radiation Protection Initial TSC Response).

5. Complete the " Initial Contact Message Form" Attachment No. 1.

O- Protective action recommendations are to be based upon EP IV-108 as information becomes available. Page 1 of 16 Rev. 1

EP I-4 BCTION STATEPENTS (c0NTINUED) M* INITfAL

6. If immediate evacuation is not required, account for personnel in accordace with EP I-8.

7. If imediate evacuation at the site is required, perform EP I-12.

8. Direct the ccmunicator to transmit the " Initial Contact Message Form" (Attachment No. 1) in accordance with contained instructions.

Instruct the communicator that the information transmitted to the Counties shall be in the form of the " Initial Contact Message Form"

#~

(Attachment No. 1). Also instruct the communicator that any additional inquiries shall be referred to the respective state emergency management agencies.

9. Direct a qualified individual to complete the " Station Status Checklist" (Attachment No. 3). Coordinate Emergency Dose Calculations and completion of Attachment No. 3 with the Shift RPT.

10. Initiate the General Emergency Call List (Attachment No. 2).

11. Initiate corporate notifications a) Contact Plant Manager or his designee and advise him to implement, EP II-4, Notification of Corporate Response Personnel, b) If Plant Manager or designee cannot be reached the ED0/ Senior Shift Supervisor shall assume responsibility for implementing EP II-4.

c) D1 0atch a Security Guard to open the EOF as per EP III-2. O Page 2 of 16 Rev. 1

EP I-4 r ACTION STATEMENTS (c0NTINUED) lO ! Ligc* INITIAL I

12. Upon receipt of a phone call from the New Jersey Bureau of Radiation Protection (BRP) or Delaware Divibion of Emergency Plancing and Operations (CEPO) do the following s a) Provide the " Station Status Checklist" at current level of completion.

l b) Exchange contact phone numbers for future updates /information.

13. Initiate the EDO Checklist (Figure No. 1) .

14. Direct a communicator to proceed to the actuated TSC and initiate 15 minute updates to New Jersey BRP and Delaware DEPO. Updates shall be in che form of the " Station Status Checklist" ( Attachment No. 3) as information becomes available.

15. If necessary, account for personnel in accordance with EP I-8.

16. Direct a technically qualified person to commence data collection in accordance with the operational and Radiological Status Boards (Figure No. 3 and No. 4, respectively). Transmit this data to the TSC and ECT.

17. Contact the Assistant to Manager / designee and advise him to appraise the State Board of Public Utilities and Department of Energy of the emergency event.

18. When the EOF is activated, transfer the responsibility of the 15 minute notifications to the States and the coordination of off-site survey teams to the EOF staff. Update the EOF Manning Chart (Figure No. 2) as appropriate.

O Page 3 of 16 Rev. 1 L _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _

l l EP I-4 8CTION STATEf'ENTS (CONTINUED) 115E* INITIAL 1 1

19. If the emergsncy is a result of ans a) Excessive gaseous release:

1) Insure the actions required of Emergency Instruction I-4.16 (Radiation Incident) are or have been taken.

2) Verify that the release has stopped.

3) Insure the Containment / Plant Vent Monitor is selected to the plant vent (Unit No.1 only) .

4) As soon as possible, perform additional on and off-site surveys and ascertain extent of airborne activity.

51 Insure personnel that have become or may be contaminated are

                                            " frisked" and begin decontamination as necessary.

6) Restrict movement outside the plant buildings to evacuation and surveys until radiation levels due to the release are within the limits specified in 10CFR20.

b) Excessive liquid release:

1) Insure the actions required of Emergency Instruction I-4.16 (Radiation Incident) are or have been taken.

2) Verify that the release has been stopped.

31 Obtain a sample from the system or source of the effluent () that was being discharged for analysis. l i t Page 4 of 16 Rev. 1

EP I-4 ACTION STATEMENTS (CONTINUED) O V IlgE* INITfAL

4) If boats or ships are in the immediate vicinity of the circulating water discharge, immediately inform the state of New Jersey and U.S. Coast Guard.

20. If any personnel have been injured and exposed in excess of 10CFR20 limits, refer to EP I-5.

21. Request additional emergency assistance and/or call in additional station personnel in accordance with the appropriate parts of Addendum No. 1, as the situation dictates.

22. Refer to EP I-15 if Stable Iodine Thyroid Blocking is required. Confer with Radiation Protection Engineer as required.

23. Refer to EP I-14 to indicate plant restoration operations when the O incident is under control. The incident shall be considered under control for the purpose of initiating plant restoration operations when the following guidelines are mets a) Release of radioactive materials from all portions of the plant are controlled.

b) Radiation levels in all areas are determined to be stable or decreasing with time. c) Fires, flooding, and/or equipment malfunctions are controlled. NOTE Plant restorations will be conducted in a manner f in which each individual operation is evaluated as to its total and individual man REM. All exposures will be maintained within the ICRP l () recommendations and EP IV ,106 and all attempts will be made to maintain exposures within 10CFR20 limits. Page 5 of 16 Rev. 1 i

 -                                                                                                                        EP I-4 O   ACTION STATEMENTS (CONTINUED) k M*                 INfTfAL

25. Complete an operational Incident Report in accordance with Administrative Procedure No. 6.

26. Upon termination of the event complete the " Termination Call List",

Attachment No. 4 and initiate recovery operations, EP I-14. Completed By: Senior Shift Supervisor /EDO Cate M FORWARD ALL COMPLETED FORMS TO THE ASSISTANT TO MANAGER. ATTACH ANY REFERENCED COMPLETED EP'S OR ATTACHMENTS. FOR NUCLEAR EMERGENCIES HAVING OFF-SITE CONSEQUENCES NOTIFY AMERICAN NUCLEAR INSURERS (REFER TO ADDENDUM NO. D . O -- - ----------_____ -- - ----------___------ ---------___-------------_________-------___ Prepared By: emf

&C_

7

{ Reviewed By: 10 f Z 0 !Il ad

DeparMn tP Date Reviewed By: 10 E6 Pl ihtiht to Manager Date Reviewed By: h Station Quality Assurance Engineer ' Date ! SORC Meeting No.: 8l - 1II /0/27[?/ Date Approved By: / // 7 N Managdr - Kalam Generating Station '/Datd Approved By: . . (>>f81

                                                                 ~
                                                                                                     /

Date k Manager - Emergency Pregraredness O l Page 6 of 16 Rev. 1

EP !_4

                                                                                                                                                  ^TT- 1 ATTACHPENT 1 INITIAL CONTACT PESSAGE FORP 1

O DIRECTIONS: This form will be filled out by the Senior Shif t Supervisor /EDO and given to a comununicator for transmittal to the States of New Jersey and Delaware. , NOIE WHEN CONTACTING NEW JERSEY AND DELAWARE STATE POLICE INFORti THEP. THAT SALEft, CUP 3ERLAND, KENT AND NEW CASTLE C0utlTIES WILL ALSO BE fl0TIFIED UNLESS OTHED.- , WISE DIFICTED BY STATE AUTHORITIES. IS U IS "THISI IIS NOT A DRILL" "THISI IIS NOT A DRILL" THIS IS . (Name) (Title) SALEM NUCLEAR GENERATING STATION, UNIT NO. THIS IS NOTIFICATION OF: U an UNUSUAL EVEiiT a SITE AREA EPERGENCY O R an ALERT R = GENERAL EPERGENCY THE EVENT DECLAPID AT ON (Time-24 hour clock. (Date) R THERE IS NO RELEASE IN PROGRESS. I I WE HAVE A CONTROLLED RELEASE IN PROCRESS. U WE HAVE AN UNC0flTROLLED RELEASE IN PP0GPISS. U NO PROTECTIVE ACTIONS ARE RECOPTIllDED AT THIS TIPE. . U WE RECOPPEND SHELTERING FOR THE FOLLOWING SECTOR (S) / (Distance / Miles) WE RECOPTIND EVACUATION FOR THE FOLLOWING SECTOR (S) /

   . ..__ _ __ _ __ _ _ _. . . . . _ _ _ _ _ __ _ __ _ _ _ _ . .. .. _ _ _ _ _ _ _ _ _ _ _ . . .. _ _. _ _ __ _ _ _ _ . .. _1 M

t t e c e d i l! ! L _ . ._ _ _ _ _

completed By

1 Senior Shift Supervisor /EDO Transmitted By: Comununicator Page 7 of 16 Rev. 1

TT PROCEDURE AND CALL LIST FOR C0ff'UNICATOR TIME MA?aE OF PERSON CONTAETED

1. Contact New Jersey State Polica 3RVACY ACT INFORMA"10N

2. Contact Delaware state Police PRVA0Y ACT INFORMATION NEW JERSEY EDUNTIFs

3. Salem County EOC PRIVACY ACT INFORMAT10h

4. Cumberland County EOC O PR VACY ACT IN:0RMATl05 DELAWARE COUNTIER

5. New Castle County E0C PRIVACY ACT INFORMATION

6. Kent County EOC PRVACY ACT

   ........._ ..........._ ._              ______. IN FORM ATIO N

7. U.S. Coast Guard !

PRIVACY ACT 8. INFORMA"10N Contact General Manager - Information Services Primary: Addendum No. 1 moed Initial Contact Message Form.

9. Info 5 ft Supervisor which calls were

_ - - - - - - - e

EP I-4 i ATT. 2 l ATTACHMENT 2 EENERAL EMERGENCY CALL LIST ([]) DIRECTIONS: The ED0/ Senior Shift Supervisor shall complete the below information and insure the following communications are completed. Advise and direct contacts based upon discussion with the EDO. PRIMARY INITIATING CONDITION (from Accident Classification Guide, i.e. , EP I, Part 2, No. 5) - EP I-0, PART , NO. TIME /DATE EVENT DECLARED j (2400 Hours) BRIEF DESCRIPTION OF EVENT: NOTE i In the event of a test, drill or exercise, preface and complete each message with the phrase "THIS IS A DRILL, THIS IS A DRILL". CONTACT CALLER TIME

1. Emergency Duty Officer (KDO)

t

2. NRC (ENS Line to Bethesda)

3. Station Manager

4. Chief Engineer / Operating Engineer

5. Station Security

6. Salem visitors Center

7. Hope Creek (Union Security)

8. Technical Support - On-site

9. NRC Resident NOTE Refer to Addendum No.1 for all phone / beeper numbers.

l

Advise the Primary EDO to notify the secondary EDO (Technical Support Supervisor).

Completed By: l I Reviewed By: () Senior Shift Supervisor / Shift Supervisor /EDO Forward completed copies to the Assistant to Manager. Page 9 of 16 Rev. 1

EP I-4 ATT. 3 ATTACHFENT 3 GENERAL EPIRGENCY O' STATION STATUS CHECKLIST Reactor and Unit No.

1. Date and Time of Incident: Date Time (24 Hour Clock)

2. Accident Classification GENERAL EMERGENCY

3. System Involved:

a) ( l' Reactors or b) ( ) Radicactive Waste Systems (circle one) Gaseous Liquidt or c) ( ) Fuel Handling (circle one) Fuel Handling Building Containment

4. Cause of Incident (if known):

O 5. Is Reactor Tripped (circle one) Yes No

6. Gaseous Release Information (complete as required):

a) Release terminated: (circle one) Yes No b) Anticipated or Known Duration of Release hours. c) Type of Releases (circle one) Ground Elevated d) Wind Speeds aph Wind Direction (toward) Divide by 2 to get m/sec (from) (Compass Points) e) Stability Class: ( ) Unstable ( ) Neutral ( ) Stable f) Release Rate Iodine Ci/sec g) Release Rate Noble Gass Ci/sec

7. Liquid Release Information (complete as required):

a) Release Terminated: (circle one) Yes No ( b) Anticipated or Known Duration of Release hours. c) Estimated Concentration pico Curies / liter.

8. Recommended Off-Site Actions (as soon as data is available):

Use attached Worksheet.

9. Status Checklist Data Relayed to Delaware States (date/ time),

(by), To: (name).

10. Status checklist Data Relayed to New Jerseys (date/ time),

(by), To: (name).

11. Status Checklist Data Relayed to Information Services (PIO): (date/ time),

l (by), To: (neme).

12. Proceed to Supplemental Station Status Checklist as infornation becomes available (see Addendum No. 2).

Page 10 of 16 Rev. 1

EP I-4 ATT. 3 i NORTH O 2o 9 1-l NW 8 NE . .- 7 6

                                                 /              \

5 wNW 4l 3 2 i N 1 I l E y I ESE wSw

I \ O SW SE RECORDER COMPASS WIND FROM DIRECTION FROM N SSw SSE 346 3/4 to 11 1/4* gy gf4 g, 337374 NNE SOUTH 9 3rt to 56 1/4* NE

1/ n' to 78 3/4* ENE

                                                                      !s J/4 to 101 1/4*               E 11 1/4 to 123 3/4'               ESE
                                                                         >> 3/4 to 146 1/4'            SE 4s !./4 to 168 3/4*            SSE JJ 3/4 to 191 1/4*              S 191 1/4 to 213 3/4'              SSW 213 3/4 to 236 1/4*              SW

, 236 1/4 to 258 3/4* WSW 258 3/4 to 281 1/4* W 281 1/4 to 303 3/4* WNW 303 3/4 to 326 1/4* NW RECOMMENDED PROTECTIVE ACTIONS WORKSHEET 326 1/4 to 348 3/4' NNW Designate areas and/or sectors with recommended protective actions symbols sa, *ollows: S - Take shelter F - Food, water and milk control E - Evacuate 0 - Other (specify) L Time Wind Direction Wind Speed (from) Completed By: Reviewed By: SSS/EDO/ERM Page 11 of 16 Rev 1

EP I-4 ATT. 4 ATTACMENT 4 Q TE mlHATION CALL LIST A. An emergency situation may only be terminated when the following conditions are met

1. No action levels for Alert, Site or General Emergency are applicable.

2. Affected unit returned to normal or long term recovery status.

3. Concurrence of the state of New Jersey.

Contact Time /Date

4. Concurrence of the state of Delaware.

Contact Time /Date

5. Concurrence of the Emergency Response Manager.

Emergency Response Manager Time /Date B. Contact the listed individuals / agencies and report the following message THIS IS .

                                                                                                                                 . AT SALEM NUCLEAR (Name)                                                                            (Title)

GENERATING STATION UNIT NO. . THIS IS TO NOTIFY YOU THAT THE (1 or 2) GENERAL EMERGENCY AT THIS FACILITY HAS BEEN TERMINATED EFFECTIVE . (Time-24 Hr;

                         . REPEAT, THE GENERAL EMERGENCY AT SALEM NUCLEAR GENERATING (Date)

STATION HAS BEEN TERMINATED. O CONTACT CALLER TIME

1. State of New Jersey (Bureau of Radiation Protection)

2. State of Delaware (Division of Emergency Planning and Operations)

3. NRC (ENS Line)

 *4. Station Manager
 *5. NRC Resident
 *6. General Manager -

Information Services

 *7. BPU
 *8. QA
 *9. DOE (New Jersey)

NOTE: The EDO is responsible for compl6 ting Part A of this Attach:nent. Part B may be completed by any designated individual.

 *See Addendum No. 1 for the required phone numbers.

Reviewed By: Emergency Duty Officer Date Forward completed sheets to the Assistant to Manager. Page 12 of 16 Rev. 1

EP I-4 ATT. 5 O ATTACHPENT 5 PREDETEPJ11NED PROTECTIVE ACTION PICOPt'ENDATIONS DI RECTIONS : If any of the following cases occur, immediately convey the protective action reconnendations as required to State / County of ficials via the " Initial Contact Message Form" (Attachment No. 1). These recommendations shall be made in l parallel with that which may have already been made in accordance with l Procedure EP IV-108. Cases I through IV consist of probable combinations of , l 2 or more fission product boundry failures (Core, RCS, Containment failure). l The specific plant conditions indicating these failures are: DEGRADED CORE A. 5 or more core exit thermocouples indicate greater than 1200*F SE B. 2 or more wide range hot leg RTD's indicate greater than 700*F S.! O C. One of the following:

1) Rapidly diverging AT SE

2) No AT(T h ~TC" EE

3) R - 31A or 31B Offscale O

Page 13 of 16 Rev. 1

EP I-4 ATT. 5 I,OSS OF CONTAINMENT INTEGRITY O A. Containment 2H c ncentration greater than 44 OE B. Indication of Containment pressure greater than 47 psig and increasing (2/4) SE C. The following:

1) Indication of Containment pressure greater than 23.5 psig and increasing (2/4)

M

2) There are less than 3 Fan Coil Units available, with only 1 Containment Spray train capability SE

3) There are less than 5 Fan Coil Units available, with no containment Spray train capability.

O e i O Page 14 of 16 Rev. 1

                                                                                                                   "P I-4 ATT. 5 I4SS OF COOLANT O  A. R-21 indicator greater than 20 R/HR, and 2 of 4 of the below listed monitors reading offseale:

1) R2

2) R7

3) R10A

4) R10B M

E. Inadequate sub-cooling, as indicated by P-250 strip-chart recorder or manual calculation and the plant in modes 1, 2, or 3. E C. Potential, Unisolatable steam line break outside of containment with indication of a primary to secondary leak in the affected generator. O OR D. Either of the following:

1) 2 out of 5 Fan Coil Unit Drainage Alarms Actuats M

2) Indication of Containment pressure greater than 4.0 psig (2/4) g BOTH CF THE FOLLOWING:

3) Containment Sump level greater than 81'3" 2

4) There is 3 indication of an In-containment steam line break O

Page 15 of 16 Rev. 1

p)

\.

PREDETERMINED PROTECTIVE ACTION RECOMMENDATION Case I 0 - 2.0 mile evacuation in all four quadrants N2 'S 10 Core Degradation with potential for LOCA and failure of Containme E Boundary

                                                                                                                                                                               ,b Case II                                                                                                                                                                  =-~~-- Vr5WIR 0 - 5.0 mile evacuation in downwind quadrant                                                    j5  10 Core Degradation and LOCA with no immediate poteistTal for                                                                                                                                                .gp, Containment Boundary Failure                                                           0 - 5.0 mile sheltering in unaffected quadrants' 8      A N
 $   Case III w

Core Degradation and LOCA with 0 - 5.0 mile evacuation in all four quadrants l

                                                                                                                                                                ~~4 MIN

10 n likely Failure of W ntainment 4h . ~ MM 5

 "   Boundary as judged by Senior                                                                                                                              'E,&

5.0 - 10.0 mile evacuation in downwind quadrant NF g Shift Supervisor /EDO g Case IV ====/A' Core Degradation and LOCA with 0 - 5.0 mile sheltering in all four quadrants A =W" imminent Failure oT Containment w g Boundary as judged by Senior Shift Supervisor /EDO 5.0 - 10.0 mile sheltering in downwind quadrant _ _- IM 10

                                                                                                                                                                                  .MF NOTE:    Recommendation revised from Case III to providefailure.                                              protection to the general public in the event the evacuation is incomplete upon imminent LEGEND:                                                                                                     f!fff M = Evacuation
                                                                  = Sheltering                                        /                                            M Nominal Wind Direction       .

_ g2 .

  ?                                                                                                                                                                               .

EP I-5

,                                        EMERGENCY PROCEDURE t

O Ee i-s PERSONNEL EMERGENCY ACTION LEVEL (CIRCLE APPROPRIATE ONE)

1) on-site serious accident, such as a severe laceration, broken bone, severe burn, resulting to an individual which requires emergency treatment and admittance at a hospital. ,

i i

2) On-Site accident or incident where an individual M or may have been exposed to radiation in excess of 10CFR20 limits.

3) On-Site accident or incident where an individual has a contaminated wound which cannot be properly treated by station personnel.

NOTE 1 In conjunction with EP I-1, otf-site notification must be made only if the injured party required admittance to the hospital and the estimated stay time is > 48 hours. NOTE 2 To summon first aid:

1. Use the PA system or telephone to notify the Senior Shift Supervisor.

2. Give location of injured person (s).

3. Use fire alarm pull station as a last resort.

4. Prior to starting work check area for nearest page and insure its operation.

ACCIDEUT DESCRIPTI E (BRIEFLY DESCRIBE) O : 1 1 Page 1 of 5 Rev. 1 l _. - -

EP I-5 I M INITIAL ACTION LEVELS 1, 2 AND 3 The Senior Shift Supervisor or designee shall:

1. When First Aid Team is required - pass word over the page for First Aid Team to respond (give location) .

2. Record names of individuals requiring emergency treatment, their location, and if possible, the extent of the injuries.

NAME, COMPANY, LOCATION AND EXTENT OF INJURY O

3. Insure that the affected individual receives emergency first aid treat-ment as required.

4. Notify the Safety Supervisor.

5. If necessary call the LAC Dispatcher at (609) 935-7300 to request ambulance service or use the station ambulance to transport the affected individual to the Salem Memorial Hospital.

l

6. If the station ambulance is to be used, notify the Guardhouse (Ext. 500 or 600), where a key is located. A backup key is located in the Safety Supervisor's Office. A guard will drive the vehicle to the location indicated by the Senior Shift Supervisor. The First Aid Team, designated by the Senior Shift Supervisor, will then place the patient in the vehicle for transport to the Salem Hospital.

l l () Page 2 of 5 Rev. 1

                                                                                                                                                                                   --l I

I EP I-5 l l ng INmR O SCTION LEVFIS L 2 AND 3 (CONTINUED)

7. l If the ambulance is used, a person will be designated by the Senior (

j Shif t Supervisor, or designee, to accompany the patient. A worker or supervisor from the patient's department should be selected, if possible. If no one is available from the First Aid Team to drive, a guard will perform this function. 8. If emergency vehicle is used, notify the Salem Memorial Hospital as follows: Call the Sales Memorial Hospital at e the fouowm , stat.nent . hen cont."' INFORMATION

                                                                                                        *This is an emergency, please connect me with the Nursing Supervisor."

l Provide the following information to the Nursing Supervisor: number of persons requiring emergency treatment, degree of injuries and medical status, contamination and radiation status, type of transportation to be O used to transport injured, who will secompany injured, expected time of arrival at hospital, and if the Radiation Management Corporation will be notified. NOTE Insure the Nursing Supervisor understands whether the injured have been contaminated and/or overexposed since she must implement the Bospital Radiation Emergency Plan if required. ACTION LEVFIR 2 AND 3 ONLY The Senior Shift Supervisor shall 1. Contact the Shift Radiation Protection Technician (RPT) . Instruct the Shift RPT to initiate EP IV-119 (Personnel Decontamination). PRNACY AC" 2. Call the Radiation Management Corporation (RMC) at (emergency calls - 24 hours a day) if the Senior Supervisor-naciation Protection recommends that outside aid is required. Page 3 cf 5 Rev. 1

EP I-5 l l I,uig INITIAL ACTION LEVF19 2 AND 3 DNlY (CONTINUED) 0 - This phone will be answered by M C personnel during business bours and messages will be recorded after hours. The Philadelphia Electric Company Imad Dispatcher periodically elicits information from the tape recorder and relays amergency calls to M C as , i

                 )  g needed. If the M C emergency phone number is out of order, call the Philadelphia Electric Icad Dispatcher's
                '{l st       .
                            /

t Office at I and ask for the Supervisor L of Icad Dispatching. Provide the following information: a) Type of incident b) A phone number for a return call from MC 3. Erposure of an individual to radiation in excess of 10CFR20 limits is a Reportable Occurrence and requires action to be taken in accordance with Administrative Procedure No. 7. ' O 4 Notify the Station Manager. 5. Ensure other notifications are made in accordance with EP I.1,

                                           " Notification of Unusual Events", if necessary.

Forward this completed form to the Assistant to Manager. Attach any referenced completed EP's. Senior Shift Supervisor /EDO Data O Page 4 of 5 Rev. 1

l ., I l l EP I-5 t O A Prepared By: ,m, h Reviewed By: /6f 76 f VI jfa e t Head ' Dath Raviewed By: /c [26 !?l A4siWtant to Manager Lcte , Reviewed By: Station Quality Assurance Engineer h /b!1b[Wk

                                                                                                                                                                     'Date SCRC Meeting No.:                                                  h / - ///                                                                               /O!27      /
                                                                                                                                                                  ' Da'te Approved By:

Manager'- S pam Generating Station

                                                                        /  ,

N[d /[/_? Dater W Approved By: - Manager - Daergency Preparedness

                                                                               >MJ         jd*                                                                   ! 2-#!8 Date M

O1 O l Page 5 of 5 Rev. 1

EP I-6 l EMERGENCY PROCEDURE O Ee i-8 PAD 10 ACTIVE SPILL l ACTION LEVEL (CIRCLE APPROPRIATE ONE)

1) As reqetred sy an Emergency Procedure.

2) A liquid and/or airborne radioactive release that results in an area being classified by Radiation Protection as an " airborne radioactivity area" and/or results in loose surface contamination, in excess of station

contaminated area" limits, which cannot be readily controlled.

NOTE Describe problem: ACTION STATEMENTS bd M INITIAL The Senior Shift Supervisor / Emergency Duty officer (EDO) shall:

1. Insure the actions required of Emergency Instruction I-4.16 (Radiation Incident) are or have been taken.

2. Advise the Shift RPT of the extent of the problem.

3. Request that necessary radiation surveys be initiated.

4. Insure that all persons have evacuated the affected area. To the extent necessary, account for personnel in accordance with EP I-8.

5. Upon receipt of survey results and/or under the accompaniment of a Shift RPT attempt to isolate the spill. Secure ventilation if possible in the affected area.

Page 1 of 3 Rev. 1

EP T-6 ACTION STATEMENTS (cONThNUED) IJ2gl INfTfAL

6. For spills in the Auxiliary Building or Fuel Handling Building maximize ventilation flow and cut in HEPA/ charcoal filters where possible.

7. Ascertain from the Radiation Protection representative the extent of .

the radiological problem.

8. Restrict access to the affected area (s) as necessary.

9. Request that Radiation Protection begin personnel decontamination if it is found to be necessary.

10. Direct that cleanup and decontamination be done as determined by the Radiation Protection representative.

() 11. Upon receiving notification from the Radiation Protection personnel, release the affected area for general access. The completed copy shall be forwarded to the Assistant to Manager. Senior Shift Supervisor /EDO Date l O Page 2 of 3 Rev. 1

                                        -      ~

EP I-6 Prepared By: . yr h 9 q */ Reviewed By: . /Of2G!9/ Depar e Head Date Reviewed By: /OfElafPl istant to Manager Date , Reviewed By: Station Quality Assurance Engineer Th[ Date l SORC Meeting No.: bI- /II /C[T7!P/ Date Approved By: / h Manager' - S(lem Generating Station

                                                           /'Da[/t6 M Approved By:           -

g ((1, I l-O 8W

Manager - Emergency Prepafedness Date O 1 l b t? Page 3 of 3 Rev. 1

EP I-7 EMERGENCY PROCEDURE O- EP l-7 STATION FIRE ACTION LEVEL one or more of the following conditions exist

1) Any fire of greater than 10 minutes duration (Unusual Event) .

2) A fire potentially affecting any safety system (Alert) .

3) A fire affecting any safety system (Site Area Emergency) .

ACTION STATEMENTS JJjfj[ INITIAL

1. Fire Brigade responds as detailed in " Fire Fighting Guidelines".

2. Shift 'tadiation Protection Technician (RPT) responds and assures

{ dosimetry and protective equipment are used as detailed in EP IV-ll6.

3. Brigade Leader reports extent of fire, equipment involved, effect on plant operations, and if extra help is required.

Building Elevation Unit Room Equipment (involved) I Safety Related Radiation Level Outside Assistance

4. For a fire potentially affecting any safety system refer to EP I-2 (Alert).

O 5. For a fire affecting any safety system refer to EP I-3 (Site Area Emergency). t Page 1 of 6 Rev. 1

4 EP I-7 i ACTION STATEMENTS (c0NTINUED) 115E INITIAL 1

6. As necessary, shift the Control Room Ventilation System lineup in accordance with OI II-17.3.2 for operation during station fires.

1

7. Notify the assigned Emergency Duty Officer (EDO) of the fire and the Senior on-site Radiation Protection representative and Safety

] Supervisor. t 8. Account for personnel and/or evacuate the site in accordance with EP I-8 and/or EP I-12 respectively as determined by the Senior Shift Supervisor /EDO. t T 1

9. If any personnel have been injured, refer to EP I-5.

10. Assign additional qualified station personnel to the Fire Brigade as

() they are available. NOTE a Refer to Addendum No. 1 for any required phor.e numbers. 4

11. If off-site fire fighting assistance is required, call the Salem Fire f Company Dispatcher. Give the location and type of fire. Give location

, on access road where fire equipment will be met by station security personnel for specific direction to the fire.

12. Order the Guard Force to escort the outside fire company to the fire location.

4 4

13. The Shift RPT will ensure dosimetry and SCBA are used by off-site fire department personnel as required in EP IV-ll6.

! 14. Notify the New Jersey Department of Environmental Protection. i Page 2 of 6 Rev. 1

EP I-7 O ACTION STATEMENTS (c0NTINUED) M INITTAL

15. When possible return the Control Room Ventilation System to a normal lineup in accordance with oI II-17.3.2, " Control Room Ventilation operation".

16. For an uncontrolled fire greater than ten minutes duration make notification in accordance with EP I-l (Unusual Event) .

17. Complete an operational Incident Report in accordance with Administrative Procedure No. 6.

18. Insure a reflash watch is stationed when the fire is out.

19. Insure the Senior Maintenance Supervisor is aware that a fire has occurred.

O

20. Complete PSE&G form 95-0818, Fire Report.

Return completed forms to Assistant to Manager. Senior Shift Supervisor /EDO Date i lO l l l l Page 3 of 6 Rev. 1

j

EP I-7 1

1 4 n( Prepared By: j/M// 7 ~f h 1 Reviewed By: IO/2 6[P/

 !                                    Dephr en Head                    Date Reviewed By:                                            /Of26 ffI As istant to Manager               Date              ,

Reviewed By: [O'Datdd!$l g Station Quality Assurance Engineer SORC Meeting No.: bl- I/l /0!2,7!b/

                                                                   ' Dat'e Approved By:                                               /!/3 [v Manager - Silern Generating Station       Dats

] Approved By: - - ah e a jb' I 24 [F

Manager - Emergency PreTaITKiness Date O l i O i I l Page 4 of 6 Rev. 1

EP I-7 FIRE FIGHTING GUIDELINES ({]) The Fire Brigade shall be mustered by Control Room personnel via announcement on the station PA system. The words " Fire Brigade respond" following a coded alarm signal or a verbal report from the Control Room will key brigade members to respond as follows:

1. The Brigade Leader and Assistant Brigade Leader will report to the scene to assess the situation.

2. Other brigade members will report to the nearest protective equipment locker to obtain equipment end await further instructions from the Control Room.

3. The Brigade Leader and Assistant Leader will report to the Control Room the following informations a) Location, size and type of fire b) Equipment involved c) Extent of injuries, if any d) Need for assistance

4. If assistance of any sort is required, the Control Room will call the .mainder of the brigade to the scene. These members will respond with equipment appropriate to the type, size and location of the fire.

The Fire Brigade Leader shall combat the problem with every means available. All personnel on the site shall be under his control. The Senior Shift Supervisor is charged with the responsibility and authority to trip any unit or piece of equipment that he feels poses a hazard. A Control Operator, with permission from the Senior Shift Supervisor, should inform the Load Dispatcher of the situation if it is deemed necessary. The affected unit Control Operator shall call for any required outside assistance as directed by the Senior Shift Supervisor on advice from the Brigade Leader. A Control Operator shal) call the Guardhouse if off-site assistance is required to l l 1. Inform guards of the type of problem.

2. What type of equipment has been called for.

3. Where to direct this equipment when it arrives on site.

Page 5 of 6 Rev. 1

                                                              -4 EP I-7 Once the fire department arrives, the Senior Shift Supervisor and Fire Brigade Leader shall assume the responsibility for their safety. The Fire Brigade Leader shall remain in charge of the operation but relinquish control of the fire fighting technique to the fire department chief providing guidance when necessary.

Once the fire is extinguished, the Fire Brigade Leader sha11:

1. Post a reflash watch

2. Initiate a cleanup (The Senior Maintenance Supervisor is charged with this responsibility)

The Senior Shift Supervisor shall call the Station Manager, Chief Engineer and the Operating Engineer to inform them of the status of the plant. O l l lO I Page 6 of 6 Rev. 1

EP I-8 () EMERGENCY PROCEDURE EP l-8

         .                                                                                                                         PERSONNEL ACCOUNTABILITY ACTION LEVEL

1) As required by the Emergency Procedure.

2) Incidents, as evaluated by the Senior shif t Supervisor (or Emergency Duty Officer), require accounting of personnel.

ACTION STATEMENTS I1ME INITIAL

1. The Senior Shift Supervisor /EDU shall notify Security that personnel may be ordered to Accountability Stations by calling Ext. 500 or 600.

Advance notification should be given if possible. Direct Security to Laplement EP III-3. 2. O The Control Room shall sound the Radiation Alert Alann and make the following statement at least twice:

                                                                                                                               "ALL PERSONNEL REPORT TO YOUR ACCOUNTABILITY STATION."

3. Repeat the announcement in five (5) minutes.

NOTE a) The normal Accountability Stations are:

1) Operations - Operational Support Center

2) Radiation Protection - Control Point (Service Building)

3) Non-contract personnel in Controlled Access Area - Control Point (Service Building)

4) Contract personnel in the Controlled Access Area - Control Point ("A" 3uilding)

5) Clerical and Secretarial - Clerical Office Administration Building Page 1 of 4 Rev. 1

EP I-8 O ACT10ft STATEPENTS (c0NTINUED) G ligE fMITfAL f l NOTE (continued)

6) All other PSE&G personnel - Station Cafeteria ,

7) Outside Contractors -

(a) Contractors with ten (10) or more persons will report to their " start of work" location. (b) Contractors with less than ten (10) persons will report to the Cafeteria. b) If it is necessary for personnel to proceed to locations other than the normal stations or to ( avoid certain areas, the Control Room personnel

  ,_s will make the necessary announcements.
 \~)

c) The Senior PSE&G representative at each Accountability Station will assume control of the assembled group. The senior contractor will assume control at each Contractor Accountability Station. d) PSE&G management / supervisory personnel shall provide assistance to the Security force when performing accountability. el Normally, the telephone and public address (P. A.) system will be used for connunication between the [ Security force (Guardhouse) and Operations (Control ( Room). The Emergency Communications System will Provide a backup system. l f) The senior person at each Accountability Station will insure that the persons under his direction will remain orderly and be prepared to receive and carryout further instructions. O G Page 2 of 4 Rev. 1 <

EP I-8 i ACTION STATEPENTS (CONTINUED) O TIME INITIAL

4. The Senior Shift Supervisor /EDO or his designee shall be notified of, and maintain a list of unaccounted for personnel.

5. If perscnnel are unaccounted for the EDO shall designate an individual w!.o sitall attempt to locate the individual (s) as soon as possible, in the following manners:

al Page the individual (s) over the P.A. system, b) Notify missing individual (s) supervisor. c) Verify through the person in charge of the Guard force that the

person is in fact on the property.

() d) Attempt to call the individual (s) at home. e) As personnel are located, the list in Item 3 above shall be updated. Attach the completed list to this procedure for record purposes.

6. If necessary and practicable, the Senior Shift Supervisor /EDO shall initiate Search and Rescue Operations in accordance with EP I-9.; 7. As necessary, the Senior Shift Supervisor /EDO shall relocate personnel to other areas as required or evacuate the site in accordance with EP I-12.; 8. If evacuation is not required, maintain personnel at Accountability Staticas as the situation dictates.
NOTE l

If personnel are to remain at Accountability Stations, periodically announce over the P.A. the status of the emergency. Page 3 of 4 Rev. 1 i

EP I-8 ACTION STATEMENTS (c0NTINUED) l M INITIAL l

9. The Senior shift Supervisor /EDO shall release personnel from Accountability Stations as the situation dictates.

Forward completed copy to the Assistant to Manager. Senior Shift Supervisor /EDO Date

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

Prepared By: M /_ _ /), M R Q Reviewed By: N _ l6 f Zl, f YI Depaf ent Head Date Reviewed By: s l0 [ 2[a f Pi v Assfs W t to Manager ~Date Reviewed By:

                            ' Station Quality Assurance Engineer
                                                                                     /Of2GM Date SORC Meeting No.:                     bI ' //l                                 10f 27 ! P/

Date Approved By. -

Manager ,6alem Generating Station Date Approved By: . > > n r ; o f/L ~2.4 Ek Manager - E:nergency Preparedness 'Date

l l O Page 4 of 4 Rev. 1

EP I-9 EMERGENCY PROCEDURE O- EP I-9 SEARCH AflD RESCUE OPEPAT10flS ACTI0fl LEVEL

1) As required by an Emergency Procedure.

2) Situations, as deterr.ined by the Senior Shif t Supervisor (or Emergency Duty Officer), that warrant Search and Rescue Operations.

NOTE For Survey, Repair and Corrective Action, use EP I-17. ACT10f1 STATEMEflTS M INITIAL

1. Radiation exposure limits shall be limited to those values specified in Administrative Procedure No. 24 except as specified by the following O c' ~ "-

CAUTION Accidental or emergency exposure of volunteers to radia-tion in excess of the values recommended in 10CFR20 may be accepted as follows, however, in all situations every reasonable effort shall be made to minimize exposure. a) 25 rem whole body once during the lifetime of an adult for non-life saving activities. b) 75 rem whole body if saving a human life will result.

2. The Senior Shift Supervisor /EDO shall assemble, or direct the OSC Coordinator to assemble, Search and Rescue Team (s) as needed.

Personnel who are trained in First Aid, familiar with the missing individuals, their work locations and the plant should be chosen l for the team (s).. Recommended personnel include the following: O l Page 1 of 5 Rev. 1 l l t-__-____-_---._..--____.

EP I-9 ACTION STATEMENTS (CONTINUED) [) IlgE INITIAL i Dayshift l Maintenance or Technical Supervisor Radiation Protection Technician , Electrician Station Mechanic Equipment Operator Utility operator or Technical Helper Back Shifts Equipment Operator Utility operator Radiation Protection Technician

3. The Radiation Protection Technician shall insure team (s) meet the minimum dosimetry and protective clothing requirements.

4. The teams may obtain any needed emerg.ency equipment from any emergency locker or equipment supply location.

5. Two-way radios shall be obtainel in accordance with EP I-19, "0SC Activation".

6. The team leader shall maintain communications with the Senior Shift Supervisor /EDO.

( 7. The Senior Shift Supervisor /EDO, with advice from the Radiation Protection Engineer or Senior Supervisor-Radiation Protection, shall determine if EP I-15, " Stable Iodine Thyroid Blocking", is necessary.

8. Prior to any access to a high or potentially high radiation area, the following procedures must be addressed. Concepts of ALARA are still necessary to ensure that personnel exposure to radiation is utilized l

effectively under all conditions. Page 2 of 5 Rev. 1 1 1

EP I-9 eCTION STATEmlTS (CONTINUED) 113E INITfAL a) Any planned personnel radiation exposure greater than 2500 mrom/ quarter requires an emergency exposure authorization. Any planned exposure greater than 3000 nrem/ quar'ter must be incurred by volunteers only. The recommended upper limits for emergency exposure to volunteers are 75,000 mrems to save a life and 25,000 mrams for non-lifesaving missions. Criteria for emergency exposure authorizations to exceed 3000 mroms/ quarter are as 7 follows: Non-Lifesaving - 25 rems See EP I-17, " Survey, Repair and Corrective Action Teams" Lifesaving - 75 rems

1) Any and all actions necessary to save and preserve life

() including, but not 10mited to, removal of iajured persons, providing first aid, personnel decontamination and providing ambulance or medical treatment services. 2 ). Injured personnel shall be moved only by qualified first aid personnel unless a life-threatening situation exists. b) An emergency exposure authorization for Search and Rescue may be requested by the Senior Shift Supervisor /EDO or the OSC j Coordinator. The request shall be reviewed by the Radiation Protection Engineer, or in his absence a Technical Supervisor, Emergency Duty Officer, Senior Reactor Operator or Shift RPT. c) The Station Manager, or his designee, shall determine that an , emergency exposure authorization is necessary and that adequate provisions have been made to maintain exposure ALARA. (Refer to EP IV-106)

9. The Shif t RPT shall ensure that all team members' exposures are ccrrectly monitored and documented.

O Page 3 of 5 Rev. 1

EP I-9 4 i fLTION STATEENTS (CONTINUED) J M INf71AL

10. The Senior Shif t Supervisor /EDO or OSC Coordinator shall brief each l team prior to entry. The briefing shall supply the following i

informations a) Identity of each missing individual 3 b) Last known location of each missing individual t i j c) Any significant plant status that may affect the search, and i special instructions. I I 1 d) What functions or jobs each missing individual was working on last. l i T e) Insure they know not to exceed 75 rem whole body-(or lower limits i as dictated by the EDO). l

11. The team shall proceed to last known location of missing individual (s).

As necessary, expand the search throughout the adjacent areas.

12. The team leader shall inform the Senior Shift Supervisor /EDO inseadiately upon locating missing personnel.

!                                  13. The team shall provide emergency first aid treatment as required.

(EP I-5) i 4

14. The Senior Shift Supervisor /EDO shall release the Search and Rescue Team (s)

a i a) Upon locating the miss'ing individual (s) and rendering necessary first aid, or y , b) On a site evacuation' order, or ( e r Page 4 of 5 Rev. 1 i - . - _ --

EP I-9 1 ACTION STATEMENTS (CONTINUED) i M INITIAL c) when the missing person is found.

15. If the missing individual cannot be located, inform the Senior Shif t Supervisor /EDO for further action.

Return completed form to the Assistant to Manager. Prepared By: /MZ &ma

7 , Reviewed By:

                                                                                    /0 24 [f'/

ta t Head ' Date Reviewed By: ' Ass 3tanu to Manager /0 [2( [P/ Date . Revtewed By: 'l b _ Z.0 [D U Station Quality Assurance Engis.eer Date SORC Meeting No.: O/ * /// / C f 2 7 !$~ / Dat. Approved By: d

                                                                                      //M       V Manager - Sdlem Generating Station                     // Date Approved By:             *

J A A l f e l/> '

Manager - Dnergency Preparedness LO N Date l l

   '.                                                                                                             a l                                                         Page 5 of 5 L                                                                                                         Rev. 1     .

l EP I-10 EMERGENCY PLAN

EP I-10 CONDUCTING AN INVENTORY OF EPIRGENCY EQUIPPENT ACTION LEVEL

1) Inventory of emergency equipment as required by an Inspection order. This will be the responsibility of the Radiation Protection Engineer. ,

2) Inventory of emergency equipment as ordered by the Assistant to Manager or the Radiation Protection Engineer.

8CT10N STATEMENTS INITIAL

1. If an Insp9ction order has been received, record the date and Inspection order number.

Date ,,,, _ Inspection Order No. O

2. List below the names of individuals directly assigned to perform the inventory at each location (i.e. , Senior Shif t Supeevisor's file crom, First Aid Room, EOF, Main Control Point, "A" Building Control Point, and the date of the inspection.

Name Location Date Emergency Vehicle __ TSC Control Room Main Control Point First Aid Room

                                                                                             ' R* Building control Point EOF

3. Obtain a copy of Tables I through and including VII of this procedure to be used by individuals performing the inventory.

m Page 1 of 21 Rev. 1

I EP I-10 l ACTION STATEPENTS (CONTINUED) O INfTIAL PAIN CONTROL POINT AND "A" BUILDING CONTDOL POINT NOTE This procedure is to be completed by the individual (s) actually performing the inventory, and reviewed by the Senior Sapervisor-Radiation Protection. Record all discrepancies on Attachment 1. 4 4, Using Table I or II provided, conduct an inventory of the emergency equipment located at the control points.

5. Check calibration dates and perform a battery check (if applicable) on all portable instruments.

l O 6. Replace the batteries in the Dosimeter Charger and verify operability.

7. Verify that each On and off-Site Survey Log contains the items listed on their respective inventory lists.

FIRST AID ROOM NOTE This procedure is to be completed by the individual (s)

actually perfoming the inventory, and reviewed by the Safety supervisor.

Record all discrepancies on Attachment 1.

3. Using Table III provided, conduct an inve:ntory of the emergency equipment located in the First Aid Room.

O Page 2 of 21 Rev. 1

EP I-10 ACTION STATEliENTS (c0NTINUED) INITT At_ FIRST AID ROOM (CONTINUED)

9. Check calibration dates and perform a battery check (if applicable) on all portable instruments.

10. Verify all bottles of KI Tables are not within three (3) months of their shelf life.

SENIOR SHIFT SUPERVISOR FILE ROOM NOTE This procedure is to be completed by the individual (s) actually performing the inventory, and reviewed by the O Senior Supervisor-Radiation Protection. Record all discrepancies on Attachment 1.

11. Using Table IV provided, conduct an inventory of the emergency equipment located by the Control Room.

12. Check calibration dates and perform a battery check (if applicable) on all portable instruments.

13. Replace the batteries in the Dosimeter Charger and verify operability.

14. Verify each on and off-Site Survey Log contains the items listed on their respective inventory lists.

15. Verify the operability of the Emergency Radio.

O G 16. Verify all bottles of KI Tables are not within three (3) months of their shelf life. Page 3 of 21 Rev. 1

EP I-10 ACTION STATEMENTS (CONTINUED) fNITIAL EFERGEflCY VEHICLE I NOTE This procedure is to be completed by the individual (s) actually performing the inventory, and reviewed by the Senior Supervisor-Radiation Protection. Record all discrepancies on Attachment 1.

17. Using Table V provided, conduct an inventory of the emergency equipment located in the emergency vehicle.

18. Check calibration dates and perform a battery check (if applicable) on all portable instzuments. Verify Radiation Protection Department has calibrated SAM-2 Analyzer.

O-

19. Replace the batteries in the Dosimeter Charger and verify operability.

20. Test run and load the Generac 6330 Alternator or equivalent.

EMERGENCY OPERATI0flS FACILITY NOTE , This procedure is to be completed by the individual (s) l actually performing the inventory, and reviewed by the Senior Superviscr-Radiation Protection. Record all discrepancies on attachment 1.

21. Using Table VI provided, conduct an inventory of the emergency equipment located j at the emergency Operations racility.

22. Check calibration dates and perform a battery check on all portable radiac.

                  -Verify Performance Department has calibrated SAM-2 Analyzer.

Page 4 of 21 Rev. 1 l

EP I-10 ACTION STATEMENTS (c0NTINUED) JNITIAL EMERGENCY OPERATIONS FACILITY (CONTINUED) J

23. Replace the batteries in the Dosimeter Charger and verify operability.

24. Test run and load the Generac 6330 Alternator.

25. Verify that each on and off-site Survey Log contains the items listed on respective inventory lists.

1

26. Verify the operability of the Emergency Radio and Walkie-Talkies.

27. Replace the batteries in, and verify the operability of, each portable lantern.

O

28. Verify all bottles of KI Tablets are not within three (3) months of their shelf life.

29. Verify operability of the air sampler (s).

TECHNICAL SUPPORT CENTER NOTE l i l This procedure is to be completed by the individual (s) j actually performing the inventory, and reviewed by the Senior Supervisor-Radiation Protection.

30. Using Table VII provided, conduct an inventory of the emergency equipment located at the TSC.

() 31. Check calibration dates and perform a battery check on all portable radiac. l l 32. Replace the batteries in the Dosimeter Charger and verify operability. 1 Page 5 of 21 Rev. 1

                                                                                                 - - ~

EP I-10 ACTION STATEMENTS (CONTINUED) O INITfAL JECHNICAL SUPPORT CENTER l (CONTINUED) i 33. Verify each on and off-Site Survey Log contains the items listed on respective inventory lists. 34 Verify the operability of the Emergency Radio.

35. Replace the batteries in, and verify the operability of, each portable lantern.

36. Verify all bottles of KI Tables are not within three (3) months of their shelf life.

{ I

37. Verify operability of the air sampler (s).

DOCUMENTATION NOTE This procedure is to be completed by the Senior Supervisor-Radiation Protection and the Safety Engineer.

38. Complete and return one copy of the Inspection order to the Performance Depart-ment in accordance with Administrative Procedure No. 10.

39. The Senior Supervisor-Radiation Protection shall be responsible for repairing, replacing and calibrating all items related to radiation protection which are deficient. If any deficiencies require a work order be issued, he shall issue one and note it on Attachment 1.

l

40. Take corrective action as required to resolve all deficiencies listed on Attachment 1. The Safety Supervisor is responsible for all items other than l radiation protection equipment.

I f Page 6 of 21 Rev. 1 i

I EP I-10 l 6CTION STATEFENTS (c0NTINUED) ( INITfAL DOCUMENTATION (CONTINUED)

41. The completed copies of Attachment I and Tables I through VII should be forwarded to the Assistant to Manager for follow-up action if required and for record maintenance.

Salem Safety Supervisor Date Radiation Protection Engineer Date Assistant to Manager Date O Prepared By: WL, A ;#.</1 - r ' - Reviewed By: '

                                                                                              / O /E[e     /

De aY ent Head ' Date Reviewed By: /0 f2 G f &I Assisfant to Manager ' Date Reviewed By: GStationQualityAssuranceEngineer k !N Date 50RC Meeting No. bl~ /I[ (O f 27 bI

                                                                                                ' Date Approved By:                                  ,

Managet 4 Silem Generating Station

                                                                                                /M
                                                                                                  'Date Approved by:                      .       -       W r;i3I                                       LO FV Manager - Emergency Preparedness                                  ' Date l

lO i l l Page 7 of 21 Rev. 1 1

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

l EP I-10 ATTACHMENT 1 ATT. 1 O is v 2 E a t-U<

3 D

i 5 4 b m M 5 s i: E B 3 t i i i D 5 m, E l M E N O ; - e i I Page 8 of 21 Rev. 1

                         -w                                                          *w %                                                      'N
                            ,                                                       (/                                                                   \

EMERGENCY EQUIPMENT INVENTO'tY MAIN CONTROL POINT NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK l_OC\ TION SPECIAL INSTRUCTIONS 1 RO2 or RO2A 2 Locker 2 PIC 6 or Teletector 2 Locker 3 E520, PRM4 or PM14 2 locker 4 High Range Dosimeter, 0-5 R or 0-10 R 10 locker 5 low Range Dosimeter, 0-200 mR or 0-500 mR 10 Control Point 6 Dosimeter Charger 1 Control Point 7 TLDs 10 N/A Incker 8 Air Sampler 2 Incker 9 Charcoal Cartridges for A/S 20 N/A locker ao 5 10 Silver Zeolite Cartridges for A/S 20 N/A lacker 3 V $ l

11 Particulate Filter Papers for A/S 100 N/A Incker g l 6 H

' " 12 Survey Logs or Data Sheets 1 Book N/A Incker 13 Portable Lanterns w/ Battery 2 locker 2 replacements for Spare Batteries for Instruments

Locker each instrument 14 ,

15 Sample Containers or small Bags 20 N/A Locker i 16 Kim Wipes 1 Box N/A Incker j 17 Rad Info Signs 6 N/A Incker 18 Stanchions 4 N/A locker 19 Barricade Rope or Ribbon 1 Roll N/A locker 20 Tage 2 Rolls N/A Incker l 21 Large Plastic L'ags 20 N/A locker l 22 Plastic Sheeting 1 Roll N/A Locker 23 Absorbent Material 1 Box N/A Incker Q 24 SOP's 20 N/A locker NY Ho DATE OF INSPECTION PERFORMED BY REVIEWED BY

b) O b) b- V V EMERGENCY EQUIPMENT INVENTORY MAIN CONTROL POINT (continued) NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK LOCATION SPECIAL INSTRUCTIONS 25 Paper Coveralls 20 N/A Locker 26 Shoe Covers 20 Pairs N/A Locker 27 Rubber Gloves 20 Pairs N/A Locker 28 Cotton Gloves 20 Pairs N/A Locker 29 Hoods or Caps 20 N/A Locker 30 Respirators and Charcoal Cartridges 10 N/A Locker 31 Radiation Protection Emergency Procedures 1 N/A Control Point a E OH re EN 2 [" DATE OF INSPECTION PERFORMED BY REVIENED BY HM N $9 N" ! m ?

( Q./ % ./ N EMERGENCY EQUIPMENT INVENTORY "A" BUILDING CONTROL POINT NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK IDCATION SPECIAL INSTRUCTIONS 1 902 or RO2A 2 !acker 2 PIC 6 or Teletector 2 Locker 3 E520, PRM4 or PM14 2 Incker 4 High Range Dosimeter, 0-5 R or 0-10 R 10 Incker 5 tow Range Dosimeter, 0-200 mR or 0-500 mR 10 Contrcl Point 6 Dosimeter Charger 1 Control Point 7 TLDs 10 N/A tocker _ 8 Air Sampler 2 Locker 9 Charcoal Cartridges for A/S 20 N/A Locker

                                                                       #3 4         10     Silver zeolite Cartr.idges for A/S                20                    N/A     Locker                                                    H p      11     Particulate Filter Papers for A/S                100                    N/A     locker                                                    Q
                                                                       $      12     Survey Logs or Data Sheets                      1 Book                  N/A     locker                                                    U U      13     Portable 1,anterns w/ Battery                       2                           locker 2 replacements for Spare Batteries for Instruments

tocker each instrument 14 15 Sample Containers or Small Bags 20 N/A Incker 16 Kim Wipes 1 Box N/A Locker 17 Rad Info Signs 6 N/A locker 18 Stanchions 4 N/A Locker 19 Barricade Rope or Ribbon ) 1 Roll N/A Incker i

20 Tape 2 Rolls N/A Incker 21 Large Plastic Bags 20 N/A locker 22 Plastic Sheeting 1 Roll N/A Incker 23 Absorbent Material 1 Box N/A locker om 24 SOP's 20 N/A Incker Qy N DATE OF INSPECTION PERFORMED BY REVIEWED BY e .

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EMERCENCY EQUIPMENT INVENTC"Y "A" BUILDING CONTROL POINT (continued) NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK LOCATION SPECIAL INSTRUCTIONS 25 Paper Coveralls 20 N/A Locker 26 Shoe Covers 20 Pairs N/A Incker 27 Rubber Gloves 20 Pairs, N/A Locker 28 Cotton Gloves 20 Pairt, N/A Locker 29 Hoods or Caps 20 N/A Incker 30 Respirators and Chatcoal Cartridges 10 N/A Locker 31 Radiation Protection Emergency Procedures 1 N/A Control Point 5 EH $ 85 - CR " !~ o g, - DATE OF INSPECTION PERFORMED BY REVIENED BY q to b R" y ~5

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EMERGENCY PLAN EMERGENCY EQUIPMENT - FIRST AID ROOM ITEM EQUIPMENT QUANTITY LOCATION SPECIAL INSTRUCTIONS 1 Splints 1 Set Locked Cabinet 2 Tongue Depressors and tlasal Swabs 1 Box 'ach Locked Cabinet 3 Thermoluminescent Dosimeters 4 Locked Cabinet 4 Polyethane 1 Roll Locked Cabinet 5 Kraft Paper 1 Roll Locked Cabinet 6 Plastic Aprons 12 Locked Cabinet Disposable Type 7 Bath Towels 6 Locked Cabinet 8 Thermal Blanket 2 Locked Cabinet 9 Plant and Hospital Procedures 1 Manual r3 g 10 Tourniquet 2 Locked Cabinet [ 11 Emergency Oxygen Kit 1 Locked Cabinet N S 12 Ambu Bag 1 U 13 Decon and Sample Taking Kit 1 With Bioassay Materials 14 K! Tablets 2 Bottles Check Expiration Date 15 Protective Clothing 2 Sets 16 Plastic Rags 12 17 Assorted Bandages and Dressing -

                       , 18  Examination Table                       1 HM N
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EMERCENCY EQUIPMENT INVENTO7Y CONTROL ROOM NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK LOCATION SPECIAL INSTRUCTIONS 1 RO2 or RO2A 2 locker 2 PIC 6 or Teletector 2 Locker 3 E520, PRM4 or PM14 2 Incker 4 High Range Dosimeter, 0-5 R or 0-10 R 10 locker 5 Iow Range Dosimeter, 0-200 mR or 0-500 mR 10 locker 6 Dosimeter Charger 1 Incker 7 TLDs 20 N/A Incker 8 Air Sampler 2 locker 9 Charcoal Cartridges for A/S 20 N/A Locker w 10 Silver Zeolite Cartridges for A/S 20 N/A locker [ 11 Particulate Filter Papers for A/S 100 N/A locker N

     $                   12   Survey Logs or Data Sheets                     1 Book                   N/A    locker U                   13   Portable Lanterns w/ Battery                       2                           Incker 2 replacements for 14   Spare Batteries for Instruments

Incker each instrument 15 Sample containers or Small Bags 20 N/A locker 16 Kim Wipes 1 Box N/A Locker 17 Rad Info Signs 6 N/A Locker 18 Stanchions 4 N/A Locker 19 Barricade Rope or Ribbon 1 Roll N/A locker 20 Tape 2 Rolls N/A Locker 21 Large Plastic Bags 20 N/A locker 22 Plastic Sheeting 1 Roll N/A Locker 23 Absorbent Material 1 Box N/A Incker Q 24 SOP's 20 N/A Incker NY 4 N DATE OF INSPECTION PERFORMED BY REVIENED BY

O l N %/ EMERGENCY EQUIPMENT INVENTO7Y CONTROL ROON (continued) NOMINAL QUANTITY OPERABILITY Ifi:M NO. EQUI PMEh' ? QUANTITY FOUND CHECK LOCATION SPECIAL INSTRUCTIONS 25 Paper coveralls 20 N/A Locker 26 Shoe Covers 20 Pairs N/A locker 27 Rubber Gloves 20 Pairs N/A locker 28 Cotton Gloves 20 Pairs N/A Locker 29 Hoods or Caps 20 N/A Incker 30 Respirators and Charcoal Cartridges 10 N/A Locker 31 Radiation Protection Emergency Procedures 1 N/A Control Point _ 32 KI Tablets (Date ) 1 Bottle 5 nd 3 81ll t: EN a [ U DATE OF INSPECTION PERFORMED BY REVIEWED BY N" a H

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O O EMERGENCY EQUIPMENT INVENTOTY O EMERGENCY VAN (continued) NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK LOCATION SPECIAL INSTRUCTIONS 25 PaFer Coveralls 20 N/A 26 Shoe Covers 20 Pairs N/A 27 Rubber Gloves 20 Pairs N/A 28 Cotton Gloves 20 Pairs N/A 29 Hoods or Caps 20 N/A 30 Respiratore ard Charcoal Cartridges 5 N/A 31 Radiation Protection Emergency Procedures 1 N/A 32 San II, RD-19, Battery and Cables 1 33 Radio I w - $u 34 Large Area Map 1 N/A Og

E g H 35 NJ and DE Road Maps - 1 Each N/A N

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c N Q 36 Station E:mergency Procedures 1 N/A 4 DATE OF INSPECTION PERFORMED BY REVIENED BY HM b

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                                                                          %.)                                                      u EMERGENCY EQUIPMENT INVENTO9Y QUINTON TRAINING CENTER EOP NOMINAL    QUANTITY OPERABILITY ITEM NO.                      EQUIPMENT                    OUANTITY     FOUND     CHECK    IDCATION          SPECIAL INSTRUCTIONS 1     RO2 or RO2A                                           1 2     PIC 6 or Teletector                                   1       ,                               __

3 ES20, PRM4 or PM14 2 4 High Range Dosimeter, 0-5 R or 0-10 R 10 5 Iow Range Dosimeter, 0-200 mR or 0-500 mR 10 6 Dosimeter Charger 1 7 TLDs 100 N/A 8 Air Sampler 2 9 Charcoal Cartridges for A/S 20 N/A

10 Silver Zeolite Cartridnes for A/S 20 N/A

  %      11      Particulate Filter Papers for A/S                 100                   N/A                                             N e                                                                                                                                      4 es     12      Survey Engs or Data Sr.'ets                      1 Book                 N/A                                             M 11      Portable Lanterns w/ Battery                         2 2 replacements for 14      Spare Batteries for Instruments

each instrument 15 Sample containers or Small Bags 20 N/A 16 Kim Nipes 1 Box N/A 17 Rad Info Signs 6 N/A 18 Stanchions 4 N/A 19 Barricade Rope or Ribbon 1 Roll N/A 20 Tape 2 Rolls N/A 21 Large Plastic Bags 20 N/A 22 Plastic Sheeting 1 Roll N/A

,. 23 Absorbent Material 1 Box N/A E 24 SOP's 20 N/A NY DATE OF INSPECTION PERFORMED BY REVIENED BY

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                                       +V                                                       t N                                                          U EMERGENCY EQUIPMENT INVENTO;Y TECHNICAL EUPPORT CENTER NOMINAL     QUANTITY OPERABILITY                                                 l ITEM NO.                                   EQUIPMENT                  QUANTITY     FOUND      CHECK     IDCATION        SPECI AL INSTRUCTIONS 1    RO2 or RO2A                                       2                           Incker 2    PIC 6 or Teletector                               2                           Locker

) Incker 3 E520, PRM4 or PM14 2 4 High Range Dosimeter, 0-5 R or 0-10 R 10 Incker 5 tow Range Dosimeter, 0-200 mR or 0-500 mR 10 Locker 6 Dosimeter Charger 2 locker 7 TLDs 20 N/A Incker l 1 8 Air Sampler "2 Incker 9 Charcoal Cartridges for A/S 20 N/A Locker av

 $u                                10    Silver zeolite Cartridges for A/S               20                    N/A     locker                                        i w                                11    Particulate Filter Papers for A/S              100                    N/A     Locker                                    N Q                                12    Survey Ings or Data Sheets                    1 Book                  N/A     locker                                    [
  "                                      Portable Lanterns w/ Battery                     2                            Incker 13 2 replacements for 14    Spare Batteries for Instruments

tocker each instrument 15 Sample containers or Small Bags 20 N/A Locker 16 Kim Wipes 1 Box N/A locker 17 Rad Info Signs 6 N/A Locker 18 Stanchions 4 N/A locker 19 Barricade Rope or Ribbon 1 Roll N/A Incker I

20 Tape 2 Rolls N/A Incker 21 Large Plastic Lags 20 N/A Inck er 22 Plastic Sheeting 1 Roll N/A Locker 23 Absorbent Material 1 Box N/A locker $ 24 SOP's 20 N/A locker NY y 40

 <                                                                                                                                                               M DATE OF INSPECTION                                                      PERFORMED BY                                BEVIEWED BY
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           \__                                                                                                                                        b EMERGENCY EQUIPMENT INVENTORY TECHNICAL SUPPORT CENTER (continued)

NOMINAL QUANTITY OPERABILITY ITEM NO. EQUIPMENT QUANTITY FOUND CHECK LOCATION SPECIAL INSTRUCTIONS 25 Paper Coveralls 20 N/A Incker 26 Shoe Covers 20 Pairs N/A Incker 27 Rubber Gloves 20 Pairs N/A Incker 28 Cotton Gloves 20 Pairs N/A Incker 29 Hoods or Caps 20 N/A Incker 30 Respirators and Charcoal Cartridges 10 N/A Locker 31 Radiation Protection Emergency Procedures _ 4 N/A Table 32 Sam II, RD-19, Battery and Cables 1 Iocker 33 Radio 2 Table

 %                                                                                                                                                               n 34      Large Area Map                                   2                      N/A         Nall U      35     NJ and DE Road Maps                            1 Each                    N/A         locker                                                         N e                                                                                                                                                               c <:

a 36 Station Emergency Procedures 1 N/A Table y i U 37 KI Tablets (Date ) 1 Bottle locker DATE OF INSPECTION PERFORMED BY REVIENED BY HM

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M V

EP I-ll EMERGENCY PROCEDURE O Ee i-11 COMMUNICATION EQUIPPENT The procedure is intended to delineate the variety of equipment available for communications on and off-site. Each section describes the equipment's purpose, location, testing requirements and any special instructions for proper use.

I. BRC - EMERGENCY NOTIFICATION SYSTEF - (ENS) NETWORK (RED) NRC (ENS) is a direct line to both the Operations Center in Bethesda, Maryland and the Regional Office. This phone is to be used for all, emergency notifications to the NRC associated with this Emergency Plan. A. Location

1. Senior Shift Supervisor's Office

2. Control Room No. 1

3. Control Room No. 2

4. Resident NRC Office

5. Technical Support Center (TSC)

6. Emergency Operations Facility (EOF)

B. Testing

1. A test is initiated by the NRC as follows:

a) The NRC duty officer calls Salem Nuclear Generating Station and identifies himself. b) The party answering is required to identify himself. Both parties hang up, c) Salem Nuclear Generating Station personnel waits 10 seconds and then picks up ENS line. d) NRC will ask caller to hold while a party conference is established with the Regional Office. e) After the quality of the connection is noted, the test is terminated. () f) All corrective action is initiated by the NRC. Page 1 of 8 Rev. 1 es

l EP I-11 C. Special Instructions The ENS line has an automatic ringing feature. ' Pick up the receiver, identify your- I self (name, title, Salen Generating Station) and request the NRC Dispatcher to tie into the Region I Office. i when any one of the INS extensions are found imoperable, notify the NRC Operations Center by cosamercial telephone er relayed message within one hour for corrective action.

11. NRC - HEALTH PHYSICS NETWORK GPN) INFORMATION The NRC (HPN) phone has the capability of linking all nuclear facilities, all NRC Regional Offices and the NRC Operations Center together. Its primary purpose is to support the Health Physics activities during a nuclear incident.

A. Iocstion

1. TSC

2. Control Point

3. Resident NRC Office

4. EOF B. Testing Testing of this line is the responsibility of the Resident NRC Inspector.

C. Special Instructions To place a call lift the receiver. No dial tone is heard. Dial the two (2) digit code labeled on each phone to contact the Operations Center or the Regional Office. The audible ringing signal heard by the called party is not heard by the caller. If no contact is made in 30 seconds, repeat the procedure. For additional capabilities of this system refer to the EP Network Description Manual located in the TSC and Radiation Protection Office.

         !!!. [ MAS LINE GLUE) 1 The NAWAS line provides direct line coesmun%ation with the Delaware Department of energency Planning and Operations via the Delaware State Police.

9 l l l l Page 2 of 8 Rev. 1

EP I-il A.

() Location l

1. Senior Shift Supervisor's office ,

2. TSC

3. EOF B. Testing ,

Testing is initiated in accordance with the operations Directive Manual (ODM). C. Special Instructions operating instructions for the National Warning System (NAWAS)

 ;               1. Depress the bell ringer button with the receiver on the cradle for approximately ten (10) seconds.

2. Pick up the receiver and state, "THIS IS SALEM GENERATING STATION. I RAVE A MESSAGE FOR THE DELAWARE STATE POLICE. DELAWARE, ARE YOUR READY To COPY?"

Wait approximately fif teen (15) seconds. If no answer hang up the phone and

   /""                 repeat steps 1 and 2.

O) IV. [4EW JERSEY STATE POLICE (NJSP) LINE (GRAY) sais phone provides a direct tie to the NJSP Communications Center in Trenton. A. Location

1. Senior shift Supervisor's office

2. TSC s J. Guardhouse 1

4. EOF

5. Testing f Testing is initiated in accordance with the CDM.

I l d("*\ Page 3 of 8 Rev. 1

i - EP Z-ll V, UEW JERSEY EMEPGENCY OPEDATIONS FACILITY LINE (NJEOC) O This phone provides a direct link with the State EOC in Trenton. It also can be used as an alternate line for the State Police in Tre6 ton. A. Location

1. TSC

2. EOF B. Testing Testing is initiated in accordance with the ODM.

VI, DELAWARE EMERGENCY OPERATIONS FACILITY LINE (DELAVADE EOC) This phone provides a direct link with the State EOC in Delaware City. It also can be used as an alternate line for the Delaware State Police. A. Location

1. TSC

() 2. E0r B. Testing Testing is initiated in accordance with the ODM. Vll. LOWER All0 WAYS CREEK (LAC) LINE (YFil09) This phone provides a direct tie to the LAC Dispatcher. A. Location

1. Senior shift Supervisor's Office

2. TSC

3. EOF B. Testing Testing is initiated in accordance with the CDM.

O Page 4 of 8 Rev. 1

EP I-ll y!!!, CONFERENCE LINES (WHITE) Five dedicated automatic ringing conference lines are available at the TSC. They are as follows: A. 1. TSC/ Senior Shif t Supervisor's Office

2. TSC/ Senior Shift Supervisor's Office / Newark Engineering Department

3. TSC/No. 1 Control Room J 4. TSC/No. 2 Control Room

5. TSC/ Senior Shift Supervisor's Office /Ecr B. Testing 4

1 Testing will be initiated in accordance with the ODM. NOTE i Most of the available phones are equipped to allow the use of the normal handset or a headset W11ch plugs into the rear of the phone. To operate refer to the instructions supplied with each headset. IX. COUNTY EOC LINES (RED) Four separate direct tio lines exist between EOC's of the four counties within the 10 mile EP2, Salem, Cumberland, Kent and New Castle and various PSE&G locations. A. Locations (PSE&G)

1. Senior Shift Supervisor's office j 2. TSC

3. EOF I Testing S.

Testing will be initiated in accordance with the ODM. X. EMERGENCY RADIOS (BASE STATION) The base radio transmitters provide communication with the Security, PSE&G survey teams and DEP survey teams. Since the same frequency is used jointly, correct ccnversation () procedures must be followed. Rev. 1 Page 5 of 8

i EP I=ll l A. Location O O 1. Senior Shift Supervisor's Office

2. TSC

3. EOF

4. EDO cars ,

5. Emergency Van (s)

6. Portable Units B. Special Instructions In order to properly use these radios refer to the following guide.

1. The Senior Shift Supervisor or the Emergency Duty Officer (EDO) shall contact the officer posted at the CAS text. 117) and direct him to activate the transmission capabilities of the Senior Shift Supervisor's base station and the TSC's base station. At the same time the officer posted at the CAS shall be directed to switch his base station from frequency 1(F1) to frequency 2(F2).

() 2. Establish communication between the TSC and the Senior Shift Supervisor's office as soon as practicable.

3. The emergency vehicle is equipped with an emergency radio. This radio as left on Channel F1 continuously. It can be used to cynmunicate with the TSC and the Senior Shift Supervisor's Office.

4. The person (s) assigned to the off-Site Survey Team shall establish communication with the TSC and/or the Senior Shif t Supervisor's Office as soon as practicable.

5. If other portable radios are required, they can be obtained fras the Guardhouse.

Radios obtained from ;.%e Guardhouse, which are to be used for emergencies shall be operated on Channt. F1.

6. Those persons assigned to act as canmunicators shall log aprecpriata communica-tions on the sispplied NRC type memo pads.

7. The following are guides to be used in emergency conditions to insure effective communications are maintained between all stations and to alleviate confusion.

O v Page 6 of g Rev. 1 l l

1 i l EP I-ll I a) When transmitting, always speak clearly and distinctly. I O b) When transmitting to a specific station, always identify who is transmitting and to whom the transmission is directed. Examples: " Control Room this is the Red Team, do you copy?"

                                                           " Red Team, this is the Centrol Room, we copy you loud and clear."                                                    ,

c) When receiving information or data, alvsys repeat the information or data baci to the caller to verify correctness. C. Testing Testing of the radio system is the responsibility of the station security force. XI. EMERGENCY RADIOS (PORTARIF) ?! Portable radios to be used for on-site and off-site survey teams are stored in the Main Guardhouse. These radios, dedicated for emergency use only, are capable of communicating with the on-site TSC from anywhere within a ten (10) mile radius of the station. Routine testing of portable radios is conducted by the Station Security force. O V XII. EMRAD TRANSMITTER (NJSP) The EMRAD radio located on 1RP7 in No.1 Control Room has two tunctions. First, in accordance with OI IV-12.3.2 this unit is the means to actuate the warning sirens in LAC. The radio's second function is to provide direct verbal communications with the New Jersey State Police at their Port Norris barracks. A l O i i Page 7 of 8 Rev. 1 l l

EP I-11 l Prepared By: W /t h d > VJ Reviewed By: lC f Z(, f YI De r e Head 'Date Reviewed By

                                                           /0f2/,!9' Assistant to Manager             'Date' Reviewed By                   -

h

                      ' Station Quality Assurance Engineer        Date SORC Meeting No. :           h f ~ llI                  IOf 27 !I/

I Da1(e Approved By: / Manager - Salem Generating Station Dtte Approved By: -

LJA./)rsa 3 82 M W Manager - Dnergency Preparedness Date O

O , l Page 8 of 8 Rev. 1

EP I-12 (3 EFERGENCY PPOCEDURE U EP l-12 SITE EVACUATION ACTION LEVEL

1) See Table I, II, III and IV.

2) Other emergency situations may be dictated as determined by the EDO.

NOTE The EDO may direct the Technical Support Supervisor to coordinate site evacuation activities. SETION STATEMEHTS IL5E INITfAL

1. The Senior Shift Supervisor /EDO shall evaluate the situation to deter-mine the extent of evacuation and location of assembly area as follows:

O a) The Senior Shift Supervisor /EDO shall reviys the onsite survey data and Table I with assistance as needed from the Shift Radiation Protection Technician. b) The Senior Shift Supervisor /EDO will select an assembly area where the projected dose is less than 0.5 rem. c) Personnel shall be evacuated to the SNGS parking lot, Hope Creek parking lot, or the Quinton Township School from determinations made in step 1.b.

2. The Senior Shift Supervisor /EDO or designes shall notify the following listed individuals / organizations that a site evacuation is underway and evacuation site.

l a) EDO l O b) PSE&G Guardhouse (ext. 500 or 600). Inform Security of assembly area to be used. (SNGS parking lot, Hope Creek parking lot or Quinton Township School.) Page 1 of 8 Rev. 1

EP I-12 A m 0N STATE?E!!TS (CONTINUED) Ijpg INITIAL c) The local LAC Police Department ) to coordinate control of SNGS traffic. INFO NA".0 N . d) New Jersey State Police (direct line) P ACi e) Direct the Salem Visitors Center to evacuate calling ext. 541 or

l. Visitors are to be sent home.

f) Notify Bechtel (Hope Creek) by calling ( . Inform Bechtel of assembly area to be used. (SNGS parking Act, Hope Creek parking lot, Quinton Township School.)

3. The Control Operator, on instruction from the Senior Shift Supervisor /

EDO shall sound the radiation alert alarm and at least twice make the following announcement over the P.A. System. O

                                                                               " ATTENTION, ATTENTION, ALL NON-EMERGENCY PERSONNEL EVACUATE THE SITE THROUGH THE NORMAL EXITS A'ID REPORT TO THE:

(Choose one)" j SNGS PARKING LOT HOPE CREEK PARKING LOT QUINTON TOWNSHIP SCHOOL 4 Site personnel shall proceed as follows: a) Exit through Guardhouse, not stopping at turnstiles or portal monitors, turning in the PSE&G security badge. b) When traveling by car, close vents and windows. c) Proceed to the designated evacuation assembly area as follows: Page 2 of 8 Rev. 1

EP I-12 O 8CTION STATEMENTS (CONTINUED) 11gE INITIAL

1) SNGS Parking tot (a) Proceed by foot to outer lot and standby for Radiation .

Protection Technician to complete personnel contamina-tion survey and release. (b) Non-contaminated personnel will standby for further instructions. (c) Contaminated personnel will report to the decontamina-tion center as indicated in Table IV.

2) Hope Creek Parking Lot O (a) Establish three or four person car pools.

(b) Proceed cautiously to Salem-Hope Creek wye, turn left and proceed to Hope Creek parking lot. (c) Standby for contamination survey by Radiation Protection. (d) Contaminated personnel shall report to the decontamina-tion center as indicated in Table IV.

3) Quinton Tcwnship School l (a) Establish carpools with minimum of three persons each.

(b) Proceed via the access road to the Quinton Township I l School Assembly Area on Route 49. Directions are found ! in Table IV. , 1 Page 3 of 8 Rev. 1 1

                                                   .. -                                    I

EP I-12 l

  . Q ACTION STATEMENTS (CONTINUED) 1  V lidE     INITfAL (c) Personnel will standby at Assembly Area for contamina-tion survey by Radiation Protection.

(d) Contaminated personnel will report to decontamination center as indicated in Table IV.

5. Bechtel (Hope Creek) personnel shall be evacuated in accordance with 1 SWP/P-B-4, " Site Procedure for Emergency Evacuations".

6. Senior Shift Supervisor /EDO or designated communicator shall notify the NRC and States of Delavare and New Jersey, using direct dial phones, that an evacuation has occurred.

7. The PSE&G security force, in accordance with the Security Plan shall O

o a) Until the municipal police arrive, establish traffic control at the end of the access road, assign a responsible individual to collect security badges and dostmetry as people leave the site. b) Place the turnstiles in free wheel and collect security badges. c) Assist personnel in forming three or four people car pools. d) Direct an orderly exit from the parking lots. e) Assign at least two members of the security force to be stationed " at the designated assembly area with a radio capability. fl Maintain evacuation traffic flow on access road in accordance with Table III. O g) Direct an orderly processing through the assembly area decontami-nation facility. Page 4 of 8 Rev. 1

EP I-12 O ACTION STATEMENTS (CONTINUED) 11gE INITTAL h) Maintain control of PSE&G and professional contractor personnel at the designated assembly until es trol can be transferred to the EOF.

8. Health Physics personnel, under the direction of a Technical Supervisor-Radiation Protection or a Radiation Protection Technician shall:

al Monitor personnel and vehicles for removable contamination at the off-site assembly area designated by the Senior Shif t Supervisor / EDO using EP I-18, Task 11. b) Release personnel from assembly area control as survey results allow (Table II of this procedure). () c) It is not expected that any station vehicle will be contaminated. If this occurs, the Radiation Protection Engineer will instruct his group to decon the vehicle in the parking lot before leaving the site. Fire hoses can be used for this purpose. If there is no time to perform this work, the vehicle can be either detained at the site or sent to a state controlled decon center. NOTE Forward all completed forms to the Assistant to Manager (SCS) . Attach any referenced completed EP's or attachments.

    .______._______.=           .__.________.......==            .__._____________________ _____________        _ _ _ _ _

l !O Page 5 of 8 Rev. 1

EP I-12 O I Prepard By: _ c/ duc.d _._

TJ { Reviewed By: / O !Zla PI Dep n Head ' Data Reviewed By: /c f 2la!I/ A sistant to Manager ' Date , Reviewed By: MM l tation Quality Assurance Engineer Date SORC Meeting No.: h[ - / / [ /0/27!k' / Datte Approved By: A M hr ' Manager 4 Salset Genefrating Station

                                                                   / /_.2 M Date~

Approved By:

22 A A I 2 2 A $1 S=4) W Manager - Emergency Pr'oparehiss Date O

l l Page 6 of 8 Rev. 1

l l l EP I-12 TABLE I

 'O             PROTECTIVE ACTION RECOMPENDATIONS FOR LOCAL PLANT ENVIRONMENT ON-SITE (1)

WHOLE BODY DOSE AIRBORNE ACTIVITY CONSIDER EVACUATION MR/HR X MPC WITHfN HOURS 2-10 1-4 48 10-50 4-20 10 50-100 20-40 5 100-500 40-200 1 500 200 Immediate NOTES: (1) Depending on conditions, the Emergency Duty Officer (EDO) may elect to allow select personnel to exceed those dose guidelines. (2) Based on MPC values in Column 1, Table I of Appendix B 10CFR (MPC's for occupational protection purpose) . Evacuation criteria based on personnel not wearing respiratory equipment. (3) EP IV-104 or 105 for other guidance for evacuation of TSC and Control Points. TABLE 11 ({]) PERSONNEL RELEASE LIP.lTS NORMAL RELEASE LIMITS WITH EDO PERMISSION ( EXTREME EMERGENCY 2 DPM/100 CM DPM/100 CM DPM/100 CM 10y 20y 200y 500 , 8 1000 , 8 10,000 , 8 NOTES: (1) Limits can be used to release personnel and personnel vehicles with the Emergency Duty Officer's permission. (2) Extreme emergency limit can be used when the EDO determines the situation dictates this to be the best Course of action, e.g., clean-up would involve a potentially higher risk or a high population density of construction workers. (3) All limits are not DPM (background subtracted). O V l l Page 7 of 8 Rev. 1

l l l EP I-12 r--)/ TABLE Ill

   \~                            ARTIFICIAL ISLAND ACCESS ROAD CONS!DEDATIONS CONSIDERATIONS                                          ACTIONS

1. Accident blocking one or both Push disabled vehicle of f access road (Security lanes of traffic on access road. Responsibility).

2. Access road within plume path. Calculate projected dose to evacuee while on access ,

road for both 5 minutes (normal driving time) and 30 minutes (traffic problems). If the projected dose for 5 minutes exceed 0.5 rad then consider evacuation to North end of Artificial Island. Consider past and forcast wind shifts before making this recommendation.

3. Anticipated traffic problem due Stagger the evacuation of the Hope Creek and Salem to necessity of evacuating both Sites. Call Hope Creek at 935-2080.

sites. TABLE IV DIRECTIONS TO ASSEFBLY AREA AT 0VINTON TOWNSHIP SCHOOL Proceed via access road to the Alloways Creek Neck Road going towards Hancocks Bridge through to Buttonwood Cuff Road, a Make a left hand turn onto Salem-New Bridge-Canton Road going north through Quinton-Harmersville Road toward Cuinton. Make a right on Route 49 and proceed immediately on right to the Quinton Township School. Decontamination will take place at the Quinton Fire House located on Main Street and South Lake Avenue approximately 2 blocks west of the Quinton Township School on Route 49. I i s_ t Page 8 of 8 Rev. 1

l l l EP I-13

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EP I-14 EFERGENCY PROCEDURE k-s) EP l-14 INITIATION OF RECOVERY OPEPATIONS ACTION LEVEL i 11 As required by Emergency Procedures EP I-2, EP I-3 and EP I-4. ACTION STATEMENTS 11gE INITIAL
1. The Senior Shif t Supervisor / Emergency Duty Officer shall ensure that conditions in the plant have stabilized and degradation isn't anticipated.

2. The Senior Shift Supervisor /EDO shall verify that all necessary f aarch and Rescue Operations have been completed per EP I-9. If not, t se Senior Shift Supervisor /EDO shall initiate any required operation in accordance with EP I-9.

3. The Senior Shift Supervisor shall direct the OSC Coordinator to assemble and dispatch radiation and damage survey teams in accordance with EP I-17.

4. The Senior Supervisor-Radiation Protection shall instruct the team to determine radiological conditions in accordance with RP I 12.331 and to isolate and post any areas which exceed 10CFR20 limits.

5. The Team Leader shall ensure that all survey team observations and data are presented to the OSC Coordinator and to the Senior Shift Supervisor.
I
6. The Senior Shift Supervisor shall relay all observations and data to the EDO, the Chief Engineer, the Station Manager and the Radiation Protection Engineer along with recommendations whether to enter recovery phase. The EDO will forward information to the Emergency Response Manager.
() 7. Concurrence to enter the recovery phase shall be obtained from the following: Page 1 of 3 Rev. 1 l t
EP I-14 ACTION STATENErlTS (CONTINUED) 11gE INITIAL a) Emergency Response Manager (Contact) (Date/ Time) b) Station Manager (contact) (Date/ Time) - c) Chief Engineer (Contact) (Date/ Time) d) Radiation Protection Engineer (Contact) (Date/ Time)
8. If concurrence is not received, the Senior Shift Supervisor /EDO shall conduct additional survey operations in accordance with EP I-17. Rela) data as specified in Statement 5 and 6.

9. The OSC Coordinator shall initiate recall of personnel in accordance with EP I-16.

10. Radiation exposure limits for recovery operations shall be in accordance with 10CFR20 limits and ALARA concepts. Normal Radiation Protection procedures and instructions and the normal REP system will be in effect during recovery operations.
~~NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments.~~
~~.....-- ----.== ........ ....--. ........................---------.. =----- ---- =......--~~
l l l l O) l l Page 2 of 3 Rev. 1
EP I-14 1 Prepared By: /M/ '
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~~Reviewed By: .~~
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Dephrtment Head ' Date Reviewed By: /C!2/o h/ Assistant to Manager / Date , Reviewed By: _ [ th! l Station Quality Assurance Engineer ' Da t e ' SORC Meeting No. b - //f /0!27!$f [
' Date ' ' ' I Approved By: / - / // V Manager -'SalemI Generating Statica / / Date *. , . proved By:
Mhv f g,*
~~Manager - Emergency Preparedffis~s~~
~~/ Ld A " Dat"e O .~~
I O l Page 3 of 3 Rev. 1 i
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~~' EP I-15 I~~
EFIRGENCY PROCEDURE O- EP l-15 l STABLE 10 DINE THYROID BLOCKlHG I i ACTION LEVEL
1) Whenever a calculated iodine dose of 10 rem or greater to the thyroid gland is likely to be received by emergency response personnel. ,

2) If possible, prior to undertaking a life saving operation where high levels of radio-iodine are suspected and no current air analysis is available. Lack of KI should not be a factor if lifesaving actions are necessary.
NOTE Refer to rigure 1 of this procedure to determine thyroid dose as a function of the airborne Iodine 131 concentration. ACTION STATEMENTS 11gE INITIAL O 1. The Senior Shif t Supervisor / Emergency Duty Officer (EDO), acting on advice from the Radiation Protection Engineer, shall designate when and who shall receive Iodine Thyroid Blocking.
~~2. The Senior Supervisor-Radiation Protection or designee shall:~~
a) obtain bottle (s) of Potassium Iodide Tablets from emergency kit (s). Emergency kits are located as referenced in EP I-10. b) Dispense one (1) tablet to each individual that could enter a high level radio-Iodine environment. (Public Service Medical Depart-ment prescription) NOTE Once taken and the concentration is verified or the calculated dose determined, the tablets s should be continued for ten (10) days. One (/ table should be taken once a day. The Medical Director shall approve any further dosage. Page 1 of 3 Rev. 1
EP I-15 g 4 ACTI fl STATEMEf1TS (CONTINUED) C') y M INITIAL c) Insure that records are maintained for those people who were administered the tablets. Infor:n the Company Medical Department that KI has been administered and that records will be forwarded. d) Inform the Safety Supervisor (Ext. 139) that the Potassium Iodide Tablets were used so that adequate supplies are maintained. NOTE KI Tablets may be taken up to four (4) hours after an exposure and still affect up to 50% reduction in dose. NOTE Foward all completed forms to the Assistant to Manager (SCS). Attach any referenced completed EP's or attachments. Prepared By: /M///
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Reviewed By: /O!30 / par ent Head Date ReviewsS By: /O!Z/,!fr/ Assistant to Manager ' Date Reviewed By: _- [ l y " Station Quality Assurance Engineer Date" SORC Meeting No.: b ~ I /0 E7
~~/ Date Approved By: ///?[M Ddte Manager - 02;em Generating Station Approved By:~~
~~M Z-~~
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Manager - bergency Preparedness Dath Page 2 of 3 Rev. 1
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EP I-16 EMERGEtlCY PROCEDURE O Ee i-1s RECALL OF EVACUATED SITE PEP.SONNEL ACTION LEVEL This procedure shall be implemented when recall of specific evacuated site personnel from the designated evacuation assembly area is necessary following site evacuation. PROCEDUREOUTLINE I. Recall of Evacuated Site Personnel Prior to EOF Activation. II. Recall of Evacuated Site Personnel After EOF Activation. 8CTION STATEMENTS IJE INITIAL
1. RECALL OF EVACUATED SITE PERSONNEL PRf0R TO EOF ACTfVATf0N O 1. The Operations Support Center Coordinator shall advise the Emergency Duty Officer (EDO) of the need for recalling specific individuals and/or job types from the evacuation assembly area.

2. The EDO or designee shall review this OSC request and shall notify the Security Force Shift Sergeant.

3. The Security Force Shift Serq= ant shall notify the Security Force at the designated wacuation assembly area.

4. The Security Force at the evacuation assembly area shall notify i
~~the designated site personnel and dispatch these individuals as l directed to return to the station and report in as designated in l Table I.~~
11. RECALL OF EVACUATED SITE PERSONNEL AFTER EOF ACTIVATION l

1. The Operations Support Center Coordinator shall advise the Senior Shift Supervisor of the need of site personnel required.
Page 1 of 3 Rev. 1
EP I-16 eCTI0fl STATEEilTS (CONTINUED) Ilg[ INfTfAL RECALL GF EVACUATED SITE PEDSONNEL AFTER EOF ACTIVATf 0N (CONTINUED)
2. The Senior Shift Supervisor shall review the needs of the CSC, designate the specific individuals and job types requiring recall and notify the Emergency Duty officer (EDO) .

3. The EDO shall review the need for evacuated site personnel and advise the Site Support Manager (SSM) of the need of additional site personnel.

4. The SSM shall notify the Administrative Support Manager (ASM) of specific individuals and job types requiring recall.

5. The Administrative Support Manager shall notify the required
() evacuated individuals who may be located at the designated evacuation assembly area or at their residences. Personnel shall be instructed to report in as designated in Table I. TABLE I PERSONNEL REASSEMBLY LOCATIONS WORK CATEGORY LOCATION Reactor Engineering Technical Support Center Radiation Protection Control Point Chemistry Control Point Instruments & Controls Operations Support Center Store Room Personnel Operations Support Center Maintenance operations Support Center Operations operations Support Center Newark Personnel Emerg. Operations Facility All Others Outer SNGS Parking Lot NOTE [}
~~'~'~~
Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. l Page 2 of 3 Rev. 1
l EP I-16
% Prepared By: / M // h i f f f~ , l Reviewed By:
~~Department Head~~
~~/ O!D0 !W Date Reviewed By: >~~
~~Assistant to Manager~~
~~/O!34 M/~~
~~Date , Reviewed By: Station Quality Assurance Engineer 2~~
~~/O'DaZ[#!kf te~~
~~SORC Meeting No. bl ~ / / / /d 2 7 /~~
Date Approved By: / //3 PV ManaqAfr ~ .dalem Generating Station Dat6
~~' Approved By: ' * ! h# [V Manager - Emergency Preparedness ' Date O~~
i i l Page 3 of 3 Rev. 1
EP I-17 EP.ERGENCY PROCEDURE ([]) EP l-17 RADIATION PROTECTION - E11ERGENCY ACTION ACTION LEVEL l l
~~1) Situations, as determined by the Senior Shif t Supervisor (or Emergency Duty Officer), that warrant the dispatch or survey, repair or corrective action teams.~~
~~NOTE For Search and Rescue use EP I-9. ACTION STATEMENTS I1ME INITIAL~~
~~1. Radiation exposure limits shall be limited to those values specified in Administrative Procedure No. 24, except as specified in the following caution:~~
O
\s ,/ CAUTION Accidental or emergency exposure by volunteers to radia-tion in excess of ths values recommended in 10CFR20 may be accepted as follows, however, in all situations every reasonable effort shall be made to minimize exposure.
~~a) 25 rem whole body once during lifetime of an adult for non-lifesaving activities. b) 75 rem whole body if saving a human life will result.~~
2. The Senior Shift Supervisor /EDO with concurrence of the Radiation Protection Engineer (or in his absence a Technical Supervisor) shall direct the OSC Coordinator to establish and dispatch the necessary survey, repair and corrective action teams.
l l l 3. The Radiation Protection Technician shall insure team (s) meet the minimum dostmet ry and protective clothing requirements. If the team is performing post radiation incident operations, full PC's, a respirator (} and a high range dosimeter shall be worn by er.14 team member. l l Page 1 of 5 Rev. 1 l
EP I-17 ACTION STATEMEllTS (CONTINUED)
~~,O IlgE INITfAL~~
4. The OSC Coordinator shall organize teams consisting of at least two (2) persons for each mission. A Radiation Protection Technician shall be a member of any team which enters any area where radiological controls are required.

5. The OSC Coordinator shall designate and identify one member of the team as Team Leader.

6. The teams shall utilize equipment for the Control Room. Cmergency Locker as needed to gain access to any other required equipsvtt such as for repair or maintenance.

7. Two-way radios shall be obtained in accordance with EP I-18, "OSC Activation".
O 8. The OSC Coordinator shall brief each team prior to entry. The briefing shall covers purpose of mission, conditions expected to be encountered, exposure limits, REP requirements, abort points and situations which may justify overriding abort points.
9. The Team Leader shall maintain communications during the mission with the OSC Coordinator and/or the Sanior Shift Supervisor /EDO. Two-way radios shall be used on all missions into hazardous areas or locations.

10. The Senior Shift Supervisor /EDO, with advice from the Radiation Protection Engineer or Senior Supervisor-Radiation Protection, shall determina if EP I-15, " Stable Iodine Thyroid Blocking", is necessary.

11. Normal radiation protection procedurer shall apply exceot as authorized in pargraph 12. Adherence to ALARA criteria shall be maintained.by all survey, repair and corrective action teams at all times including emergency conditions.
O 1 1 Page 2 of 5 Rev. 1
EP I-17 ACTI0ff STATEMENTS (CONTINUED) 115E INITIAL l l
~~12. Waiver of a REP during emergency conditions by survey, repair or corrective action teams may be made as follows:~~
The Radiation Protection Engineer, Technical Supervisors or, if neither is available, a Radiation Protection Technician may substitute continuous coverage by Radiation Protection personnel in lieu of a REP, for situations requiring immediate access. These instances shall be documented upon completion of the job. NAME TITLE of individual authorizing WARNING () RTP or Emergency (EREP) requirements may not be waived in High Radiation Areas.
~~13. Prior to any access to a high or potentially high radiation area, the following procedures must be addressed. (EP IV-106).~~
Concepts of ALARA are stil_ accessary to ensure that personnel exposure to radiation is utilized effectively during emercency conditions. a) Any personnel radiation exposure authorization greater than 2500 mrens per quarter is considered an emergency authorization. Any planned exposure greater than 3000 mrams per qusrter must be i incurred by volunteers only. The recommendvd upper limits for emergency exposure to volunteers are 75,000 mrems to save a life and 25,000 mroms for non-lifesaving missions. Criteria for emergency exposure authorizations to exceed 3000 mrems per quarter are as follows: i g-s Life saving - 75 rems U See EP I-9, " Search and Rescue Teams" Page 3 of 5 Rev. 1 1
EP I-17 ACTION STATEMENTS (CONTINUED) 11gg INITfAL Non-Lifesaving . 25 rems Repair or operation of equipment necessary to mitigate a situation which has or may have the potential to cause projected off-site . doses which would require protective action. Corrective Actions necessary to prevent plant safety status from further deteriorating or to effect significant Lmprovement in plant safety status. Corrective actions necessary to cause significant reductions in in-plant radiological hazards, b) An emergency exposure authorization shall be requested by a department head and reviewed by the Radiation Protection Engineer (or in his aboence a Technical Supervisor) . In the event one or more of the authorizing personnel cannot be contacted, they may rs be replaced by an Emergency Duty Officer, Senior Reactor Operator, or a Radiation Protection Technician.
/
c) The Station Manager, or his designee, shall determine that an Emergency Exposure Authorization is necessary and that adequate preplanning has been conducted to ensure that the anticipated exposure received under the Emergency Exposure Authorization is ALARA. d) The Radiation Protection Engineer (or in his absence a Technical Supervisor) shall assist the department requesting an Emergency Exposure Authorization for all radiological control matters and ! ensure the radiation exposure received during the emergency situation is properly monitored and documented.
~~14. All dose records shall be maintained and recorded for each team member by the Radiation Protection personnel.~~
NOTE a Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. Page 4 of 3 Rr e. 1
gp g,g7 iO t Prepared By: /MT/// (
~~# =r i~~
~~3. vie.ed By:~~
~~Department Head~~
~~/o/zc/s/~~~
~~Date~~
~~..vi..ed ,y fo/zc/w Date~~
~~1stant to Manager ,~~
~~Reviewed By: _ l h~~
' Station Quality Assurance Engineer !N 'Date" SORC Meeting No.: bI-l/l 10- 2 7 l Dat6 Approved By: /* , d Manager -/salmen Gen'erating station ///3 Date Approved By: * *= 1 A_)LA e a s [ b 2J /b Manager - Dhargency PreparednTsi 'Date O
~~I Rev. 1 I Page 5 of 5 )~~
~~- -- - . - - _ _l~~
~~=_ .- - . - - - -- -_ - - - ____ _~~
EP I-18 O EMERGENCY PROCEDURE EP l-18 OPERATIONS SUPPORT CENTER ACTIVATION i 1 i ACTION LEVEL l Declaration of Emergencies starting at the Alert Level. s 1 ACTION STATEMENTS l i 11ME INf71AL
1. OSC Coordinator reports to Senior Shift Supervisor at the OSC in hall-way between Control Rooms.

2. OSC Coordinator removes and initiates the OSC Logbook from the locker in the Senior Shift Supervisor's Office and logs in on OSC status board.
(} 3. When an individual becomes available, the OSC Coordinator will designate one to be communicator and maintain the status board and running inventory of equipment in the OSC.
4. OSC Coordinator will call in personnel in accordance with EP I-16 and direct personnel to log in as they arrive.

5. With concurrence of the Senior Shift Supervisor and Radiation Protection Engineer, the OSC Coordinator will dispatch personnel to security at the main gate to obtain three (3) portable 2-way radios.

6. OSC Coordinator will assure that a REP is initiated whenever it is required that an individual pass through a high radiation area or contamination area in order to reach a destination. If the dosimetry and PC supplies at the Control Point can't be reached without exposure, the dosimetry and PC's in the Senior Shif t Supervisor's Office locker shall be used. (Refer to EP I-17)

7. The Search and Rescue, curvey, repair and corrective action teams shall
() be controlled in accordance with EP I-9 and 17. Page 1 of 2 Rev. 1
EP I-18 i
~~$CTION STATEMENTS (CONTINUED)~~
~~Q( Ilyl INITIAL 1~~
~~8. When directed by the Senior Shift Supervisor, the OSC Coordinator will deactivate the OSC.~~
Senior Shift Supervisor Date N:M'E Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. Prepared By: /M/// /L v ; g- t i-Reviewed By: ) Depfrtment Head
/O!20!f"/ 'Date Reviewed By: /O!30 I 'A istant to Manager ' Date Reviewed By: .. . /22 h " Stab on Quality m surance Engineer /h N !
~~Date6 SORC Meeting No.: hf~lIf /0/37!h"/~~
' Date Approved By: /// L-Manager - Sale 6 Generating Station ' Date Approved By: . . L4AA u l/2 Mb Manager - Emergency Prepa'reandiss Date q /
Page 2 of 2 Rev. 1
EP I-19 EMERGENCY PROCEDURE
~~> EP l-19 ACTIVATION / EVACUATION OF THE TECHNICAL SUPPORT CENTER (TSC)~~
ACTION LEVEL Declaration of an emergency classification at Alert level or above, or by direction of Senior Shift Supervisor /EDO. . ACTION STATEMENTS IlME INITIAL
1. The Senior Shif t Supervisor /EDO will direct the Shif t Radiation Protection Technician and the Shift Technician-Instruments & Controls to activate the Technical Support Center.

2. The Senior Shif t Supervisor /EDO shall brief the Shif t Radiation Protection Technician and the Shift Technician-I&C on any adverse radiological conditions which may be encountered in transit to the TSC.
~~O v~~
3. The Shift Radiation Protection Technician and the Shift Technician-I&C shall utilize protective clothing, respiratory protection and dosimetry and doserate meters as needed during transit. Equipment and instrumentation may be obtained from the nearest emergency locker, if necessary.

4. The Shift Radiation Protection Technician shall report to the Tsc and initiate activation in accordance with EP IV-101.

5. The Shift Technician-Isc shall report to the TSC and activate the trend analysis equipment in accordance with instructions posted at the equip-ment.

6. The Shift Radiation Protection Technician shall remain st the TSC and l complete duties as specified in EP IV-101.
l
- 7. The Shift Technician-Isc shall remain in the TSC, at the discretien of x,,) the Senior Shif t Supervisor to monitor the trend analysis system and relay information to the EDO.
~~Page 1 of 3 Rev. 1~~
~~. _ _ . = .~~
~~EP Z-19 [) ACTION STATEMENTS (CONTINUED) Il5E INITIAL~~
8. If radiation levels exceed:

a) Instantaneous dose rate of 1000 mr/hr, or ,
~~b) dose rate of 100 mr/hr averaged over one hour which is expected to persist for 24 hours, the Senior Shift Supervisor /EDO shall consider evacuation of the TSC.~~
9. If required, and at the dizaction of the Senior Shift Supervisor /EDO, surveys shall be conducted in accordance with EP IV-110.

10. The primary alternate TSC is the Control Room. If the EOF has assumed control, communications and dose assessment functions should be reassigned to the EOF.
1
~~11. When an emergency has beer. terminated, the Shif t Radiation Protection Technician, at the direction of the Senior Shift Supervisor /EDO shall check TSC supplies and replenish as necessary.~~
NOTE Forward all completed forms to the Assistant to Manager (SGS) . , Attach any referenced completed EP's or attachments. O I l Page 2 of 3 Rev. 1
.~
~~EP I-19 9 Prepared By: g/N/ aM- ) Reviewed By: D4partment Head~~
~~/O!20!N Date Reviewed By: /0 20 h[ ' Assistant to Manager Date .~~
~~Reviewed By: Xtation Quality Assurance Engineer N!~~
'Date*
~~soRc n.eting so.: 8I- I / / /o/> 7 /& / Date Approved By: # Manager - Salefn Genef ating Station~~
~~/!/3 ' Dat's F~~
Approved By: *
~~u s) 8 Manager - Emergency Preparedness~~
~~'!MDate b"~~
O O Page 3 of 3 Rev. 1
ADDENDUM 1 (q , EFIRGENCY PROCEDUPE ADDENDUM 1 ( FASTER PHONE LIST EMERGENCY ASSISTANCE AND NOTIFICATI0fl INDEX PEE . 1 STATION RESP 0NSE............................................................................ CO R PO RATE RE S P0 N S E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . GOVERNMENTAL RESPONSE FEDERAL................'...............................................................11 12 STATE OF NEW JERSEY................................................................... 13 SALEM C0UNTY.......................................................................... 13 CUMBERLAND C0UNTY..................................................................... 13 LOWER ALLOWAYS CREEK.................................................................. 14 STATE OF DELAWARE..................................................................... 14 KENT C0UNTY........................................................................... 14 NEW CASTLE C0UNTY..................................................................... 14 STATE OF MARYLAND..................................................................... 14 STATE OF PENNSYLVANIA................................................................. 15 MISCELLANEOUS OFFSITE RESP 0NSE............................................................. pd EOF COMMUN I CAT I ONS LAY 0VT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
~~18 TSC COMMUNICATIONS LAY 0UT..........................................................'........~~
~~ENS COMMUN I CAT I ON S LAY 0UT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .~~
~~. . . . . = _ _ -_ = .............~~
~~PREPARED BY - N // - - ._ fim<_ REVIEWED BY~~
/O ' D - E I F Dept en Head Date REVIEWED BY /0~ 37
~~b itant to Manager Date REVIEWED BY Ytation Quality Assurance Engineer~~
~~_ /O 7 f~~
/ Dato SORC MEETING NO. 8 /- /// /C!27 Date !Ir/ . APPROVED BY ' /!/ '/ Date Manager / Salein Generating Station - ' / J-t P'2-mg APPROVED BY ' Date Manager - Emergency Preparedness
~~[q l Rev. 1~~
~~- = _ _ _ _ _ . - - - . - _ - - . _ _ - __~~
~~1 EMERr,ENCY PROCEDUDE - ADDENDUM 1 PASTER PHONE LIST O EPERGENCY ASSISTANCE AND NOTIFICATION PSE8G PERSONNEL SJTION RESP 0flSE i~~
PR VACY ACT O IN

0RMA"l0N O
~~Page 1 og 19~~
~
Add ndum 2 e ADDENDUM 2 SUPPLEMENTAL STATION STATUS CHECKLIST NOTE The intent of this addendum is to provide a uniform format for data transmission between state and company personael knowledgeable in radiation dose assessment. Examples are: 1) New Jersey Bureau of Radiation Protection, 2) Delaware's Accident Assessment Advisory Group, 3) the , Dad!ation Emergency Manager at the EOF, and 4) the Radiation Protection Engineer at the TSC. Reactor and Unit No. Transmitted From TSC/ EOF By: Name Position Time Of Reactor Shutdown: Time Of Release To Containmenti: Time Of Release From Site: AIRBORNE RELEASES: Actual Potential NOTE: RELEASE (ELEVATED OR GROUND LEVEL) IODINES ELEVATED RELEASE GROUND LEVEL RELEA9E (Ci/sec) (Ci/sec) SPECIFY IF DATA IS AVAILABLE I-131 I-132 I-133 I-134 I-135 NOBLE GASES ELEVATFT RELEASE GROUND LEVEL RELEASE (C1/sec) (ci/sec) SPECIFY NUCLIDES IF AVAILABLE Kr - 8 5 Kr - 85 m Kr - 87 Kr - 88 Xe - 133 Xe - 133 m Xe - 135 Xe - 135 m Page 1 of 5 Rev. 1
Add ndum 2 l 2 PARTICULATE RELEASE: Actual Potential (n), PARTICULATTS ELEVATED RELEASE GPOUND LEVEL RELEASE (Ci/sec) (Ci/sec) I-131 Cs - 137 Sr - 89 . Sr - 90 - ESTIMATE OF SURFACE RADIOACTIVE CONTAMINATION: Location In-Plant Onsite Offsite Radionuclide Composition Activity 2 xp sure Pate dpm/100cm mR/Hr ,es, L) Additional Remarks: 5 () Page 2 of 5 Rev. 1
~~,,- .~ . - . . ~ . . .-. .. - . _ = . ._ .~~
~~1 4~~
' I ' Addendum 2' '- :2*
~~.. s l~~
~~1 9~~
~~% - EXPOSURE / DOSE RATE MEASUREMENTS AND ESTIMATES -~~
i Dose (Rem) Sector Zones Exposure Dose Rate Adult Child Location (1 - 16) (0 - 10) (R/hr) (rem /hr) WB Thyroid Thyroid Site Boundary , Piume Centerline Peak 2 Miles
\
i i 1 r 5 Miles i 10 Miles i i i i I Other Locations: - I- (Describe) ; i r i i O 1 i 4 l
~~Measured Calculated l~~
!O l i ! Page 3 or 5 Rev. 1 i _ . - - - - _ . , , , , , - . - - ,m,,. -
Addandum 2 l
~~~ .. .. .. - -~~
1 I ESTIMATED IMPACT TIMES: i O AIRBORNE / PARTICULATE REI. EASES I Location (Distance mi) (or description) Sector Zone (s) Time To Impact: Hr Min (circle) 1 I
]
t i l b O i t , i I k I i O l l t Page 4 of 5 Rev. 1 I ,
~~. - - , * ,-r- , , , , . , -.---,--,.w--- --~~
m-r -
Add:ndum 2 [~\ V; WATERBORNE RELEASES Location (Distance Mi): Public Water Intake, Beach Private Time To Impact: Hr Min (circle) (circle) Recommended Protective Actions (RPA): (1) Evacuation Yes No (2) Take Shelter Yes No (3) Food, Water, Milk and/or live stock feed control Yes No (4) Other (specify) Distance Quadrants or sector Zone (1) (2) (3) (4) 0 - 2 mi
~~/7 ~s]~~
2 - 5 mi 5 - 10 mi Other (specify): l Additional Remarks: 1 (" C' Page 5 of 5 Rev. 1
FIGURE 1 FIGURE NO. 1 O EMERGENCY PLAN EDO CHECKLIST ACTION LEVEL This checklist shall be implemented by the EDO as a guide to assist the turnover of responsibilities of EDo from the Senior Shift Supervisor. , ACTION STATEMENTS -
~~1. EMERGENCY PROCEDURES CURRENTLY IMPLEMENTED (check appropriately) l l EP I-l b EP I-9 b EP I-2 l l EP I-12 EP I-3 l l EP I-13 1~~
~~EP I-4 EP I-15 b l l EP I-6 b EP I-18 O EP I-7 EP I-19 EP I-8 EP II-4 l l~~
~~2. METEOROLOGICAL CONDITIONS Nominal Direction (From)~~
~~El. 33 El. 300 (Toward) El. 33 El. 300 t Average Speed El. 33 El. 300 l~~
~~3. CURRENT MEA DOSE RATE (Plume center line - maximum)~~
~~Calculated mr/hr !. Measured ar/hr I O I l Page 1 of 2 Rev. 1 n-~~
+
~~FIGURE 1..~~
~~4. ' STATUS OF PROTECTIVE. ACTION RECOMMENDATIONS 7s None b Sheltering ./~~
~~, Sector (s) / Distance Evacuation / '~~
Sector (s)/ Distance CONVEYED TO: (check appropriately) State of New Jersey l l Cumberland County State of Delaware Kent County Salem County New Castle County
~~5. ESSENTIAL CONTACTS ESTABLISHED (check appropriately)~~
I New Jersey Bureau of Radi~ation Protection l l Delaware Department of Emergency Planning and Operations 1 () l l Manager [__l Chief Engineer [__j Secondary *EDO l l Emergency Response Manager (if required)
6. Insure all of the required data in accordance with EP I-13, Post Accident Low Pressure Injection Monitoring, is being appropriately recorded and evaluated.

7. Copies of all Emergency Plan Procedures and data sheets are turned over.

8. Mechanism is established to transmit data via Figure 3 (Operational Status Board) and Figure 4 (Radiological Status Board) to the TSC as this data becomes available.
i
~~9. TURNOVER COMPLETE l~~
Date/ Time-2400 hours i l Senior Shift Supervisor EDO Page 2 of 2 Rev. 1
O O O [0MPUfflCAT10NS/E0F PANillNC, NAME PHONE SHIFT UM Emergency Response Manager Tzchnical Support Manager Eng. & Const. Support Manager ,, , Site Engineer Support Manager Prod. Dept. Support Manager Administrative Support Manager y RIdiological Emerg. Manager e
~~$ Public Information Manager u~~
u Public Information Tech. Liaison SIATE AND LOCAL NJ Bureau of Radiation Protection Rep. Del. Emergency Operations Rep. NJ State Police Rep. 4 Salem County CD Rep. LAC Twp. Rep. EEDERAL Nuclear Regulatory Commission Rep. FEMA Region II (NJ) FEMA Region III (Del.) FRMAP Rep. N O
l SNGS OPERATIONAL STATUS BOARD - EFERGENCY !O !~ DATE/ TIME OF UPDATE: / 2400 HRS UNIT NO. I. PRIMARY COOLANT SYSTEM III. CONTAINMENT INTECRITY
a.
~~Th - LOOP 1 *F a. CONT. PRESSURE PSIC~~
b. Th - LOOP 2 'T b. CONT. TEMP (AVC) 'T

c. Th - LOOP 3 'T c. CONT. DEW POINT *F i

d. Th - LOOP 4 'T d. CONT. H CONCEN.
~~l 2~~
e. Tg,g (AUCTIONEERED) 'F e. CONT. IS01ATION STATUS

f. PRZ. PRESS. PSIG $A 45

g. PZR. LEVEL (HOT) %

h. SUBC00 LING MARGINS IV. SAFETY INJECTION SYSTEM l AP . PSIG a. CENTRIFICAL CHRC. & LMP FIDW CPM AT *F b. S.I. PLHP FLOW CPM

i. RCS FIDW c. RHR PLMP FIDW CPM FORCED NATURAL d. R.W.S.T. LEVEL TEET

j. RCP's IN SERVICE (CIRCLE) e. S.I. ACTUATION 1 2 3 4 YES NO 2400 BRS

k. RCS BORON PPM

1. NEUTRON FLUX CPS V. C.V.C.S.

a. LETDOWN FIAW CPM i
~~II. SECONDARY COOLANT SYSTEM b. CHARGING FLOW CPM~~
a. NO. 1 S.C. LEVEL (WIDE) %

b. NO. 2 S.C. LEVEL (WIDE) %
~~c. NO. 3 S.C. LEVEL (WIDE) % VI. SIGNIFICANf PLANT EVENTS~~
~~d. NO. 4 S.C. LEVEL (WIDE) % ITEM TIME I~~
~~l e. FC. 1 S.C. PRESS. PSIC l~~
f. NO. 2 S.C. PRESS. PSIC l

g. NO. 3 S.C. PRESS. PSIC l h. NO. 4 S.C. PRESS. PSIC l

1. No. 1 S.C. FEED FLOW %

j. NO. 2 S.C. FEED FLOW %

k. No. 3 S.C. FEED FIDW %
1. O No. 4 S.C. FEED FLOW % l Figure 3 Rev.
I SNGS RADIOLOGICAL STATUS BOADD ; i Accident Type Time hours l l Site General Time Declared: b Alert Senior Shift Supervisor Primary EDO Secondary EDO Plant Status: Unit 1 Unit 2 ItADIATION M0f,ITOPING SYSTEM AIR MONITORS AREA MONITORS Date/ Bkgr./ Normal 1 Date/ Bkgr./ Normal [ Name mR/hr Time Data Time Name c/m Time Data Time i R-llA Contairment Part. R-1A Control Room R-12B Containment 1 /m R-1B Control Room-Intake Duct R-12A Centainment Cas ll R-2 Containment El. R-11A Vent Part. R-3 Radiochem. Lab R-128 Vent 1 /s j R-5 Fuel Handling Bldg. R-6A Sampling Room
~
R-12A Vent Cas R-16 Vent Cross Cas , R-20B Counting Room R-14 West Cas Eff. l f R-15 cond. Air Eject. - R-41A Containment Part. R-418 Containment 1 ,
\ R-41C Containment Cas R-43 High Range LIQUID MONITORS DOSECALCULATIONS j Date/ Bkgr./ Normal Name c/m Time Data Time RCS Activity UC1/cc i
Calculator Time 1st calc. comp. R-13_, Fan Coil Y Dose Excl. Area 3R/hr at hrs R-18 Liq. Waste Thy. Dose Excl. Area mR/hr at hrs R-19_ Blowdown y Dose LPZ mR/hr at hrs R-17_ Comp. Cool Thy. Dose LPZ mR/hr at hrs R-31A Letdown Cross , k 318 Letdown 1 /m Y Dose at mR/hr at hrs i R-31C 31B/31A Thy. Dose at mR/hr at hrs Meterological Data MPH Wind Direction to
from Release Rate (Ci/sec) Noble cas Iodine fCC01]NTABILITY Time Started Time 1st Count Complete Final Count Site or Bldg. Evacuation hours to Figure 4 Rev. O
EP II-l 4 EERGENCY PROCEDURE O EP Il-1 EMERGENCY RESPONSE MANAGER PREPARATION TO ASSUME ACTION LEVEL 1) As required by the need for long term energency response augmentation . l ACTIONSTATEFFNTS . l M INITIAL 1. Cor. duct a meeting with at least the Radiological Emergency Manager , Site Support Manager and any other appropriate members of the off-site (EOF) response organiution and ensure that they are prepared to assume their energency response responsibilities: a) Radiological Emergency Manager 8 b) Site Support Manager 2. Contact the Emergency Duty Officer ands a) Determine his knowledgethe Protective of States Action
~~' Actions. Reccumaandations made to b)~~
~~Assume the responsibility for the function of emergency coordinator which includes the nondelegatable duty to make the decision to notify and recomunend protective actions to New Jersey and Delaware.~~
~~3. Review past press releases.~~
PRLVACY AC.. 4. Contact State the (Director of the Office of Emergency Management - New Jers Police 3r and determine the status of implementation of previously reccennended Protection Actions O, . Iv I i Page 1 of 2 Rev. 1
IP II.1 O ACTION STATEMENTS (CONTINUED) -
\
M INITI Al_ PR VACY ACT 5. Contact the Director of the Division of Energency Planning and operations - Delaware or and determine the status of previously recommended Protective Actions. PRIVACY AC" 6, when time permits, contact the Senior vice President - Energy Supply and Engineering or or and give him a heinfing. NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced comepleted EP's or attactments. O Prepared By:
~~/ m f. n ua Reviewed By:~~
~~Department Head l@!9 l~~
' Dete Reviewed By: .gency' Planning / Security Engineer fo!f ' Ddte /
Reviewed By: - Station Quality Assurance Engineer Date SORC Neeting No.: 0$~El$ l0f)7 V Date Approved By: /' , C_ V Managefr - Kalan Generating Station /3
~~/ ' Date Approved By: * .~~
~~u2o ; u Manager - Bnergency Freparedness' [* # 2.4 [4~~
~~'Dete O~~
s __ m_ _ _ -
l EP II-2 r l O EMERGENCY PP0CEDUPE EP !!-2 SITE SUPPORT MANAGER PREPAPATION TO ASSUME RESPONSIBILITIES 1 ACTION LEVEL
~~1) As required at the direction of the Emergency Response Manager.~~
~~ACTION STATEMENTS 115E INITIAL~~
1. Establish the capability for communications with:

a. Emergency Duty Officer

b. Technical Support Supervisor
~~() 2. Receive a thorough briefing from the Technical Support Supervisor or EDO on the plant status, present operations and considerations for the future.~~
3. Initiate and maintain a status log of plant conditions on a chalk board (or other similar substitute).

4. Report to the Emergency Response Manager that he is ready to assume his responsibility for providing recommendations for Protective Actions based on plant conditions.

5. When authorized by the Emergency Response Manager, notify the Technical Support Supervisor that the Site Support Manager has responsibility for recommending Protective Actions based on plant conditions and that the Technical Support Supervisor should keep the Site Support Manager advised of all plant conditions and the entering of any Emergency Action Levels.
r l Page 1 of 2 Rev. 1 l
EP II-2 0( Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced ccumpleted EP's or attachments. Prepared By: /am sw - Reviewed By: -
~~// / / Deparptbent Head Date Reviewed By:~~
~~F Emer ency~ Planning / Security Engineer~~
~~/B!7 / Dkte N~~
Reviewed By: _ [O N vStation Quality Assurance Engineer ' Date SORC Meeting No. bl ~ Il l /O!d 7 6"/
~~/Date' Approved By: /3 b Manager ,/Salydh GenFPrating Station ' Gate' Approved By: .~~
~~L4 0 [f4 2./ M Manager . Einergency Preparedness 'Date 1~~
I e O Page 2 of 2 Rev. 1
EP II-3 l O EMERGENCY PROCEDURE EP 11-3 RADIOLOGICAL EMERGENCY MANAGER PREPARATION TO ASSUME RESPONSIBILITIES ACTION LEVEL
~~1) As required at the direction of the Emergency Response Manager. The Radiological Emergency Manager shall perform or cause to be performed the following: .~~
~~ACTION STATEMENTS 11gE INITIAL PREPARATION TO ASSUME RESPONSIBILITY '~~
1. The Radiological Dnergency Manager (REM), after being notified by the Production Department Support Manager to man the EOF, will contact members of the REM's staff and tell them to man the EOF per the notification list. The REM's staff will proceed to the EOF as soon as possible and set up their facility for use with equipment from the EOF
~~() i Emergency Locker.~~
2. The first person arriving at the EOF and qualified to act as the REM will report to the Emergency Response Manager (ERM) and notify the senior Radiation Protection Department person at the station.

3. The REM's staff will assist the Radiation Protection Department at the station until the REM's staff is assembled and able to assume its normal functions and until the EOF is declared operational by the ERM.

4. Determine that the staff on hand is adequate to accomplish the
( anticipated initial tasks and consists of at least the following personnel Two (2) qualified Radiological Assessment Staff Members Three (3) qualified Communicators fr ~g Two (2) qualified off-Site Radiological Monitoring Teams i k- / (Two (2) persons / team) l l l Page 1 of 6 Rev. 1
EP II-3 [])ACTIONSTATEMENTS(CONTINUED) 115E INITfAL PREPARATfoN TO ASSUME RESPONSIBILfTY (CONTINUED)
5. Determine if a sufficient amount of equipment listed in Table EP II-3-1 is on hand to accomplish the anticipated initial tasks. This equipment is located in the EOF Emergency Equipment Locker.

6. Determine that the following radios are in working orders

a. Two (2) portable radios to be used by survey teams

b. Base station radio to be used by a Radiological Emergency Manager Communicator to the survey teams
() 7. Determine whether a sufficient amount of pertinent site and environ-mental data is available to permit dose calculations to be made and to perform assessments. The required data would include the following: Radiation monitoring system data Meteorological data on-site field monitoring team data and locations off-site field monitoring team data and locations Protective action recommendations, if any Plant status l f l ! 8. Report to the Emergency Response Manager that the Radiological 1 Emergency Manager is ready to assume the responsibilities for off-site surveys, determining dose assessments and projections, and making Protective Action Recommendations. l l
~~9. When authorized by the Emergency Response Manager, notify the Radiation Protection Engineer / designee that the Radiological Emergency Manager has assumed his responsibilities.~~
O V Page 2 of 6 Rev. 1
EP II-3 ACTION STATEMENTS (CONTINUED) IlE 1H1I1&1. ASSUMPTION OF RFKPDNEfBffITfFt 1. The REM's office shall keep a log of all events and actions from the first notification of an emergency to the return of the station to , normal conditions. Log books for this purpose are in the Emergency Comusunications Cabinet at the EOF. 2 Control of the off-site radiation monitoring teams will be transferred from the TSC to the EOF. used. Procedures EP IV-109 and EP IV-110 will be Off-site radiation monitoring personnel may consist of station Radiation Protection Department personnel and/or EOF assigned personnel . 3. Responsibility for off-site dose projection will be transferred from the TSC to the EOF. Procedures EP IV-111, 113 and 114 will be used. These functions will be performed by the Radiation Assessment Staff . _ 4. Responsibility for recosusending off-site protective actions will be transferred from the TSC to the EOT. Procedure EP IV-108 will be used. Protective action recessendations should be made to the TheERM. states of New Jersey and Delaware should be informed of the basis for the roccessendations af ter they have been made. These functions will be performed by the Radiation Assessment Staff and Radiological Emergency Manager.
~~5. I Communications with the States of New Jersey and Delaware, the TSC ,~~
NRC, and the off-site radiation monitoring teams will be by telephone or radio manned by Connunicators. 6. Establish and maintain phone contact with the States for the purpose of transmitting Station Status Checklist and/or the Supplementary Station Status Checklist.
~~"'~"~~
r
~~', PR VACY ACT New Jersey INFORMATION l~~
Page 3 of 6 _ COh _ A_ ____ __---.---- -
EP II-3 O ACTION STATEMENTS (c0NTINUED) 11gE INITIAL ASSUMPTION OF RE9PONSIBftf71ES (CONTINUED) When authorized by the Emergency Response Manager, notify the States that future Statios Status checklists will be communicated by a Radio-logical Emergency Manager communicator. Station Status checklist updates will be provided to tr.9 States of New Jersey and Delawere approximately every 15 minutes by the Communicators. This frequency is an objective and may vary based on existing conditions. (Station Status Checklists provided initially for declaring any one of the four emergency classifications will be sent from the station.)
~~7. Establish contact with the following organizations and put them on a standby status to provide support as needed:~~
~~Radiation Management Corporation (Addendum No. 1) O Research and Testing Laboratory (Addendum No. 1) NRC - HPN~~
8. Post two TLD control badges and two self-reading control dostmeters in two locations in the EOF, one at the reception area and the other in the REM's office. Log the dosimeter numbers, time issued, and place-ment location.

9. Issue a TLD badge and self-reading dosimeter to EOF managers, alternates, and off-site radiation monitoring team personnel who may have occasion to enter radioactive areas. Log the dosimeter numbers, time issued, and persons name.

10. If the EOF is in the radioactive plume and the population around the EOF has been evacuated, issue TLD's to all personnel in the EOF.
O Page 4 of 6 T.ev. 1
i l EP II-3 (c """'") O 8c" S'^"'S IlgE INITIAL ASSUMPTION OF RESPONSIBILITIES (CONTINUED)
~~11. If the Ecr may become contaminated, access to the EOF should be ,~~
~~controlis4 as necessary by activation of a frisking station at the main entrance to the EOF. All other entries should be secured and posted.~~
12. The REM will initiate long term environmental monitoring and coordinate such monitoring with on-site actions and conditions. Long term assistance may be drawn from other nuclear power utilities and contractors.

13. Samples from the radiological environmental monitoring stations shall be collected by the Research and Testing Laboratory and analyzed by Radiation Management Corporation. The Radiological Emergency Manager will contact the Research and Testing Laboratory when it is determined
~~() that these samples should be analyzed.~~
~~14. The REM or station's senior Radiation Protection Department person will~~
. establish communication with the medical assistance facilities and personnel of Radiation Management Corporation to put the Emergency Medical Assistance Plan into operation if necessary. Contact will be established as defined in the D.ergency Medical Assistance Plan.
~~LONG RANGE PRE?tPATION AND TERMINATION OF EOF USE~~
1. After the emergsacy is under control and evacuation of the public is l no longer likely to be necessary, the Radiological Emergency Manager's l office shall assist _ station personnel to determine ef forts which may be used to further reduce exposures to the stati.on operating personnel and to the public.

2. Individual and population radiation exposure doses should be evaluated after the incident.
~~l O l l V~~
~~3. The REM's office will be secured at the direction of the ERM.~~
i l Page 5 of 6 Rev. 1 i.
EP II-3 l NOTE t Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. Prepared By: Mar ' ~
~~/Jze<A ,~~
~~W Reviewed By: M /~~
~~- trent liead O Date Reviewed By: / / '~~
~~77 mergency Planning / Security Engineer / Date Reviewed By: W Station Qual.ity Assurance Engineer~~
'Date SORC Heeting No.: 0l ~ liI IO f 27 f WI 'Date Approved By: ! I /!/ 3, k
, Manager .<5alep Generating Station 'pate O Approved By: e - tfS I I kl Manager - Emergency Preparedness Date O
~~-l Page 6 of 6 Rev. 1~~
~~1 EP II-4~~
~~'r~N ENERGENCY PROCEDUDE EP !!-4 NOTIFICATION OF CORP 0P. ATE EMERGENCY RESPONSE PERSONNEL ACTION LEVEL~~
1) Emergency classification level of ALERT or above.

2) The Senior Shift Supervisor shall perform or cause to be performed the following actions or action statements.
~~ACTION STATEMENTS IldE INITIAL~~
~~1. a) The Senior Shift Supervisor /EDO shall notify the Station Manager and/or Chief Engineer in order to initiate Corporate emergency notification.~~
~~EE O b) If the Station Manager or Chief Engineer is not available, the Senior Shif t Engineer /EDO shall notify the Emergency Response Manager.~~
2. The Station Manager or the Chief Engineer or the Senior Shift Supervisor /EDO shall notify the Emergency Response Manager.

3. The Emergency Response Manager and the individual notifying the Emergency Response Manager shall determine the need for notification of Corporate emergency response personnel and activation of the EOF.
~~This shall be automatic under the Site Area and General Emergency classifications. l~~
~~4. The individual notifying the Emergency Response Manager shall also notify the General Manager - Information Services and inform him of the emergency and whether the EOF is to be activated.~~
l
~~5. The Emergency Response Manager shall notify the Production cepartment~~
~~-- Support Manager if further notification is required.~~
l Pege 1 of 3 Rev. 1 l
EP II-4 l
~~, ACTION STATEMENTS (c0NTINUED) 4 .~~
~~IldE INfTfAL~~
~~6. The Production Department Support Manager shall notify the following in the order of:~~
a) Radiological Emergency Manager b) Site Support Manager c) Corporate Engineering Support Manager d) Administrative Support Manager e) Licensing Support Manager O NOTE Refer to Addendum No. 1 for the individual names 1 and their corresponding telephone numbers.
7. The Corporate Engineering Support Manager shall notify the Site Engineering Support Manager.

8. The General Manager - Information Services shall notify the Public Information Manager and instruct him to activate the Emergency News Center.

9. Each Manager shall notify his staff members.
NOTE If any Corporate Emergency Response personnel cannot be reached at the telephone numbers listed in Addendum l () No. 1, the Emergency Paging Procedure given in EP II-5 may be used. l l l l Page 2 of 3 Rev. 1 l
~~.gp 77,4 NOTE~~
( Forward all ccanpleted forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. Prepared By: Z#T//L . /nm . Reviewed By: /# 7 [/ F taant Head # Datfe Reviewed By: V
/
~~e gency Planning / Security Engineer~~
~~/d!/ ' Date Reviewed By:~~
~~Station Quality Assurance 2ngineer~~
~~!O h!~~
~~Date SORC Meeting No.: 8I ~ III /O/27!P/~~
'Date Approved By: ///17 W Manager'- Salem Getierating Station ~ / Dant Approved By: . JAArfa f/f' # /b Date Manager - Emergency PrepXte'iiness i
1 () (./ Page 3 of 3 Rev. 1
EP II-5 / EPERGENCY PROCEDURE 3] EP 11-5 EP.ERGENCY PAGING OF CORPORATE EPEPGENCY DISPONSE PERSONNEL Pagers are provided for Corporate Emergency Response Organization Managers and alternates to help ensure that these individuals can be contacted to perform their duties as described in the Emergency Plan and Procedures. If at any point in the notification chain (see EP II-4), a Manager or one of his alternates cannot be reached by telephone, the caller may use the Emergency Paging System to attempt to complete the notification. Emergency Paging System should normally be used when telephone contact cannot be made. Anyone assigned Corporate Emergency Response notification responsibilities is authorized to use the Emergoney Paging System. The Pagers are to be programmed such that they can be activated either in functional groups or individually. These groups a2ai individuals and their pager telephone numbers are listed in Figure EP II-5-1. A person wishing to use the paging system will call the Senior Electric Dis; PRl W siv I Vu on or and give him the following information:
1. The Corporate Emergsney Response Group (s) by title (i.e., Site Support Manager) or the individual (s) to be paged.

2. The message that the Senior Electric Dispatcher-Supervising will give to the person (s)/
group (s) being paged. This message will normally give the name of the person requesting the page and a request to call that person at a given phone number or another definitive message. After receiving and logging the information on Figure EP II-5-1 the Senior Electric Dispatcher-Supervising will call the appropriate pager number liste6 in Figure EP II-5-1, and hang up the phone when a beeping tone is heard. The phone will not be answered as the system is controlled by computer. Three paging calls will be made at 15 minute intervals if the person (s) being paged has not called in. After that time, the person requesting the page shall be told that the page was unsuccessful. The Senior Electric Dispatcher-Supervising will keep a log of each request for paging and the results on Figure EP II-5-1. when an individual's pager sounds, he will call the Electric Dispatching Super PRIVAC 1 j IN 0RMA10\ ! O g The call will either be answered by the Senior Electric Dispatcher-supervising or recorded messages will be heard until the Senior Electric Dispatcher-Supervising is free to answer the call. All calls will be answered in the order in which they are received. l Page 1 of 5 p.y, 1
EP II-5 Upon contacting the Senior Electric Dispatcher-Supervising, the individual beincJ paged should ( give the Ioad Dispatcher his name and the Emergency Response Group to which he belongs. The Senior Electric Dispatcher-Supervising will then read the message to the caller. NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments.
~~-- -_-_ --- ---.--.= ... . .~~
~~Prepared By: /my /f% w w Reviewed By: V'~~
~~/ /p 7 [~~
De nt Head 4)ater ' Reviewed By: / // // er ency Planning / Security Engineer ' Ddte Reviewed By: _ Mvs
~~~StatR n Quality Assurance Engineer '~~
~~T,k Date~~
~~!k SORC Meeting No.: bI ~ II! / O!2 7!Il ' Date Approved By:~~
~~Manager - Salem Generating Station~~
~~///d Dater W~~
Approved By: * ( / 7-/ W Manager - Emergency Preparedness Date O Page 2 of 5 Rev. 0
O O O . FIGURE EP 11-5-1 EMERGENCY PAGING REQUEST PERSON REQUESTING PAGE: DAY DATE TIME PERSON TAKING PAGING REQUEST MESSAGE TO BE GIVEN TO PERSON (S) BEING PAGED: CROUP PERSON (S)/ CROUP (S) TELEPHONE NO. PACE (1) RESPONSE PACE (2) RESPONSE PACE (3) RESPONSE NO. TO BE PACED FOR PACING TIME _ TIME _ TIME TIME TIME TIME MESSAGE RECEIVED FROM PERSON BEINC PACED
~~1. EMERCENCY RESPONSE E HANAGERS $~~
~~H O R. A. uaerit. [ N C J. M. Zupko e C J. Boettger O~~
M
~~2. [] PRODUCTION DEPARTMENT g SI'PPORT MANAGERS m Q~~
~~C R. F. Steinke u - C R. L. Foster C H. R. Hontz [] C. W. Bowdren $ _ E N~~
~~3. O RADIOLOCICAL EMERCENCY O _~~
~~MANAGERS N (~]W.L.Britz _ g []R.P. Douglas O~~
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[] R. F. Yewdall N qm g Hw []N.C.Allman m .H
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EP II-6 f 1 EMERGENCY PROCEDURE EP !!-6 0FF-SITE ADMINISTRATIVE SUPPORT ACTION LEVEL 11 As required at the direction of the Emergency Response Manager. ACTION STATEMENTS IlBE INITIAL
1. The Administrative Support Manager shall provide the general of fice support functions, including typing, reproduction, office supplies and office furniture.

2. The Administrative Support Manager shall handle the arrangements for motel, airline and trailer locations, staff the EOF and perform the functions of registration and indoctrination.
~~O 3. The Administrative Support Manager shall meet the telephone require-ments such as mobile units and radio pages (beepers).~~
4. The Administrative Support Manager shall function as the EOF purchasing agent, procuring equipment and supplies for both on-site and off-site support.

5. The Administrative Support Manager shall administer the petty cash fund (Training Center Fund) and expense accounts as well as handling all payroll matters.

6. The Administrative Support Manager shall provide meals for all personnel at the EOF.

7. The Administrative Support Manager shall meet the manpower requests of the Emergency Response Manager and ensure that clerical support is available and provide labor relations assistance, as required.

8. 'The Administrative Support Manager shall provide vehicles for the EOF.
Page 1 of 6 Rev. 1
EP II-6 I ACTION STATEMENTS (c0NTINUED) I,1fiE INITIAL
~~9. Table EP II-6.1 contains pertinent information and contacts for services for use by the Administrative Support Manager. ;~~
~~NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach ar.y referenced completed EP's or attachments. Prepared By: N,~~
~~-r / -~~
h 7 Reviewed By: /d 7 f Date' D Dartment Head Reviewed By: - /# Cf Y/ Em e y Plannisfg/Seciurity Engineer 'Dat6 Reviewed By: ];> M [O d ( Station QUaliYy Assurance Engineer / Datd SORC Meeting No. : 6l' III / C/d 7
/
~~tace Approved By: _~~
//
Manager A Salem Geherating Station 'Date , Approved By: *
~~4 4 A 4 u e l #2 / 1/ b Manager . Emergency Preparedness Date O~~
Page 2 of 6 Rev. 1
1 1 EP II-6 TABLE II-6.1 O TABLE 11-6.1 aontaista^ rive sueeoar assouacts 1 PR VACY ACT O INFORMATION l l t l i ! O l Page 3 of 6 Rev. 1
EP II-6 TABLE II-6.1 0 31VACY ACT IN ORMATION i O ' O Page 4 ef r Rev. I
EP II-6 TABLE II-6.1 O r
~~)RIVACY ACT IN 0RMATION .~~
O O Page 5 of 6 g,y
EP II-6 TABLE II-6.1 O P1VACY ACT IN 0RMATION O l l 1 l O Page 6 of 6
~~,,,, y~~
~
EP II-7 EMERGENCY PROCEDURE , ()) EP !!-7 TESTING 0F EMERGENCY PROCEDURE EP !!-4
1. The purpose of this procedure is to test the effectiveness of EP II-4, " Notification of Corporate Emergency Response Personnel", and demonstrate a state of readiness to respond by Corporate personnel.

2. Testing of EP II-4 shall normally be dones a) Between 8:00 a.m. and 9:30 p.m. on weekends.
~~b) Between 6:30 a.m. and 9:30 p.m. on weekdays.~~
3. Testing shall be done at least quarterly.

4. Testing shall not be performed if the Electric Dispatching System is known to be under stress (e.g., storm) at the scheduled time.
O
5. There shall normally be no prior announcement of the time or date of a test.

6. The Manager - Emergency Preparedness / designee shall initiate the test by calling the Senior Shif t Supervisor, Salem, and inform him that THIS IS A DRILL and that he should proceed to implement EP II-4. The Manager - Emergency Preparedness / designee shall provide the Senior Shift Supervisor with a prepared message to be used during the test in the format shown in Figure II-7.1.

7. Each person contacted shall fill out a Drill Feedback Sheet and return it as soon as possible after the drill to the Emergency Planning and Security Engineer.

8. When the person (s) to be notified cannot be reached by telephone Emergency Procedure EP II-5 shall be used. .
~~l 1 l~~
~~9. The Manager - Emergency Preparedness shall review and retain the results of the tests for at least one (1) year.~~
A U ____________________________________________________ - ____________________________________ l l Page 1 of 4 Rev. O !
EP II-7 Prepared By: / m pf h Reviewed By: r ge artanent Head
~~//!7 Date Reviewed By: /* //~~
er ency"Plahning/ Security Engineer / Date . Reviewed By: h Station Quality Assurance Engineer OM ' Date' f SORC Meeting No.: h[ ' /I I /0 7 /
~~' Date Approved By: / /3 Manager - S41em Generating Station Date' Approved By: . -~~
ce d' / L/ 6 Manager - Dnergency Preparedness Date D J I l t l Page 2 of 4 Rev. O
EP II-7 TIG. II-7.1 1 0 ' THIS IS A DRILL, THIS IS A DRILL l The Drill Number is The date is , 4 The time is This is Name Title t Your instructions are to record the dri.?1 number, date and time of this message, name of person I calling and your name. Your are then to make the notifications as if this were a Site Emergency in accordance with the requirements of EP II-4. Forward your record of this drill to Emergency Planning and Security, 80 Park Plaza, 15A, Newark. Please give the persons that you call the i same instructions that you were given. This is the end of this message. THIS IS A DRILL, THIS IS A DRILL f O ! Page 3 of 4 Rev. O !
~~, ,-- . y -~~
~~l l EP II-7~~
~~! FIG. II-7.2 ?~~
DRILL OR EXERCISE FEEDBACK SHEET i Drill Number: Name of Recipient Dete: Timer . Name of Caller: Message Received: Action Taken: O Simulated Actions Taken Problems Noted i l l signature j Promptly return this sheet to the Emergency Planning and Security Engineer, 80 Park Plaza 15A, Newark. ,. L Page 4 of 4 Rev. 0 1
1 l l EP III-l f-- EMERGENCY PROCEDURE l EP 111-1 OPENING 0F THE TECHNICAL SUPPORT CENTER (TSC)
~~&CTION LEVEL~~
~~1) Upon the request of the Senior Shift Supervisor, Emergency Duty Officer or the Shif t Radiation Protection Technician to activate the TSC. ,~~
~~ACTION STATEMEllTS IldE INITIAL~~
1. The Security shif t Sergeant will Lumediately dispatch a security officer, with key, to unlock the TSC, located on the third floor of the "B" Building.

2. The security officer will remain posted at the TSC until the arrival of staffing personnel. Upon arrival of staffing personnel the officer may return to the guard house with the TSC key.

3. Upon notification from the Senior Shift Supervisor, Emergency Duty Officer, or designee, the security force member (SFM) posted in the Satellite Alarm Station (SAS) (Ext. 127) shall activate the transmission capabilities of the Senior Shif'c Supervisor's and the TSC's base radios. At the same time the SAS SFM will switch from Frequency il (F1) to Frequency 12 (F2).

4. The Security Force shall be notified to use F2 for the duration of the emergency. The Central Alarm Station (CAS) shall remain on Fl.

5. As requested, make available the portable radios to on/off site survey teams. Radios are located in the SAS and Main Guard House.

6. When the emergency is terminated, dispatch a STM to secure the TSC.
NOTE O Forward all completed forms to the Assistant to Manager (SGS) . l (,,/ Attach an, referenced completed EP's or attachments. l f 1 ...--------- ................--...--.........--....-- ........ = =.....----.......--... Page 1 of 2 Rev. 1
~~EP III-l~~
( Prepared By: ( V Reviewed By: /O!)[e!b"[ j Departh nt ead I Date 1 Reviewed By: /O!30!8"/ Assistant to Manager Date , Reviewed By: 1 ],gA h
~~' Station Quality Assurance Engineer~~
~~[O Dh f~~
/ Date SORC Meeting No.: b/ ' / / / /C/D!I/ ' Dat6 Approved By: __ / /d Y Manager - Sales (Genefatihg Station ~ Qate' Approved By: . . ((
~~Manager - Dnergency Preparedness l 2./ [k~~
~~' Date O -~~
o O Page 2 of 2 Rev. 1
EP III-2 ([]) j EMERGENCY PROCEDURE EP 111-2 OPENING THE EMERGENCY OPERATIONS FACILITY (EOF) ACTIOil LEVEL 1) As required at the direction of the Senior Shift Supervisor or Dmergency Duty Officer. ACTIOilSTATEPEi1TS . lihE INITIAL
~~1. The Senior Shift Supervisor /EDO shall notify the Security Shift Sergeant on Ext. 500 to open the Emergency operations Tacility (EOT) located at the Quinton Training Center.~~
2. The Security Shift Sergeant shall dispatch a Security Force Member (STM) to open the ECT. Keys for the front door of the EDT and for the D=ergency Cabinets are located in the Secondary Alarm Station. The
~~) ECT is located at,613 Salem-Quinton Road (Route 49), Salem, New Jersey.~~
~~The' normal telephone number is C> ! or Salam Ext. 556 or 557 IN:01V ATION~~
~~3. The STM shall bring the following radio equipment to the ECT:~~
~~a) Three (3) 20-watt portable radios with external antennas b) One (1) base station~~
4. The STM shall unlock the front doors.

5. The STM shall turn on all lights. Light switches are located in the hallways and inside each room.

6. The STM shall instruct any persons in the facility to wait fcr further instructions from the Emergency Response Manager.
~~.c l~~
Page 1 Rev. 1
EP III-2 l ACTION STATEMENTS (CONTINUED) M IMITIAL 7. The STM shall remove the telephones from the Emergency Comunications Cabinet and plug them into like jacks bearing their numbers. Taqure EP III-2-1 shows the location of these jacks. The STM shall check for a dial tone on each outside line. If there is no dial tone or the phone is malfunctioning in any other way, call 1 for service. IN ~0RV ATON NOTE Dedicated pick-up and ring type phones shall be tested by picking up the receiver and establishing contact with the other party or verify that a ring tone can be heard.
8. The STM shall insure that all doors with the exception of the front doors are locked.

9.
The STM shall station himself at the front door and ad-it persons with PSE&G identification or identification from New Jersey, Delaware or the NRC. The general public shall be denied entry. Press personnel shall be sent to the Emergency News Center.
10. The STM shall remain at the ECT until relieved by the Emergency Response Manager. NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. l et Q l l l l Page 7 ef 4 p,y, g
EP III-2 s a Prepared By: , # g_ w - a
* /C!3 (, f"/
Reviewed By: ' Datte Depart:ne t Head Reviewed By: /Of3/o!kl Assisftant to Manager 'Date , Reviewed By: j n /, 2 , (( [
~
~~Station UtfMItT Assufince Engineer / Datd SORC Meeting No.: bf' If /0!27Date~~
~~!k/~~
~~Approved By: ) /!/3~~
~~' Date V~~
Manager - Shle:n Generating Station Approved By: * * / 1/ f-Manager - Dnergency Preparedness Date O o 4 l Page 3 of 4 Rev. 1
QUINTON TRAINING CENTER LAYOUT AS EP III-2 EMERGENCY OPER ATIONS FACILITY FIG. III-2-1 76'-00 o' ' ' o , SPARE - SPARE CONFERENCE I orrec t toney oPrict mu , SPARE gggg 5TORAE.E OECicE - - PUSLic MRVICE WRC I PwSLIC sul'ORMATION PUSLIC IN50RMATION j% C0 @ _a
@ @@(9 @ .g* * .**, * , j RADIOLOGICAL k# * ** EMERGENCY MANAGER NRC 1 -
~~R ADIO LOG LCAL~~
$ TELEPHONE "*""" 6 g [
~~4 CABINET W wRC - wp Estar.tucy g - Q ;5 c~~
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9 W STORAGE NEW JER5EY .' i; ( ci ' 3r 6 e fj DELAWARE h i; ' F 9
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~~i: PRVACY ACT IN 01V'ATION I" e' E , I 22 9 ADMINISTR ATivE 23~~
~~EMERGENCY h SUPPORT 3 A~Aaa=~~
a'a n! 25 . 6 (it 29 32 I bh N 33 34 35 Sit E SUPPORT SITE ENGINEERING 36 n gawaggg Su m RT
~~'T 37 MANAGE 8C 40 9 hb _~~
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~~= 56'- os --~~
Pace 4 Rev. 1
EP III-3 EMERGENCY PROCEDURE O' EP III-3 PERSONNEL ACCOUNTABILITY ACTION LEVEL
1) Upon receiving notification from the Control Room that personnel accountability is required.

2) The Security Shift Sergeant / designee shall complete this procedure.
~~ACTION STATEMENTS TIME INITfAL~~
1. Notify all guard posts that an accountability is in progress; specifying if this is a drill or an actual emergency.

a. During drills, all guards will remain on post. The guardhouse will contact the Control Point b=nediately af ter the start of the drill and report the locations of all guards on the nuclear site.
O) (, Guards on vital area posts will utilize their radio or the nearest telephone to report their status to Security Control. All quards manning non-vital area posts will be contacted by the Assistant Sergeant responsible for their post for accountability purposes.
b. Actual emergency procedures require all guards posted within nuclear areas to leave their area of responsibility and report to the Control Point. Upon arrival at the Control Point, the guards will report their photobadge numbers to the individual collecting accountability information for that area. The guards will stand-by at the Control Point and await further instructions,

c. Guards posted within non-nuclear areas will remain at their post and report their status to Security Control via radio or the nearest telephone and await further instructions.

2. During both emergencies and drills, guards will instruct personnel in their areas to report to accountability stations which are listed below:
~~\ '" Operations - Operational Support Center,. Ext. 635/633 Radiation Protection - Control Point fl, Ext. 611 l~~
Page 1 of 7 Rev. 1
EP III-3 ACTION STATEt'ENTS (CONTINUED) 11gE INITIAL Non-Contract Personnel in Controlled Access Area - Control Point il (Service Building), Ext. 611 Contract Personnel in the Controlled Access Area -
~~"A" Building Control Point #2, Ext. 295 Clerical and Secretarial - Clerical Office, A&ninistration Building, Ext. 515 All other PSE&G Personnel - Station Cafeteria, Ext. 519 Outside Contractors -~~
~~Contractors with ten (10) or more persons will report to their " start of work" location. Contractors with less than ten (10) persons will report to the cafeteria. O~~
3. Request a badge check for the auxiliary guard house and start an immediate check of the badges filed in the main guard house. Dadges filed within the main aid auxiliary guard houses will be annotated on mylar accountability overlays which have been designed to alles quick correlation of badge informaticn. Overlays are also utilized at the Catalytic and cafeteria accountability stations. The annotated over-lays are aligned over a master accountability list which is kept current by the security secretarial staff and reflects photobadges not issued or kept on file. The auxiliary guard house accountability over-lays will be transported to the main guard house after completion.

4. The Sergeant will instruct SAS personnel to immediately initiate a roll call prantout of all personnel logged on station. At the termination of the accountability, the printout will be compared with the photo-badge numbers of personnel who reported to accountability station.
This will provide feedback on the reliability of the computer to accomplish an electronic accountability in the future. O \/ m l 1 Rev. 1 Page 2 of 7
EP III-3' m ig eCTf0f1 STATEt'E!lTS (CONTINUED) 11d1 INITIAL n'
5. Secure the guard house doors and vehicle gates at both the main and auxiliary guard house. With the exception of emergency vehicles, emergency personnel, authorized exempted personnel and radiation monitoring teams, no one will be authorized to enter / exit through the guard houses.

6. Post a sec- iard to handle communications in the main guard house and to dc _11 messages both outgoing and incoming regarding the accountability.
' 7. Sispatch two (2) security officers to the cafeteria with accountability overlays. These officers will check the badges of all personnel at the cafeteria accountability station and annotate them on the account-ability overlays. This will be completed as expeditiously as possible and the accountability overlays delivered back to the main guard house.
O U 8. The SPD/UE&C accountability station will be located at Building 902 (PSEEG Construction Office). SPD/UEEC will have an accountability list at their station and will be responsible for completing the list as expeditiously as possible. SPD/UE&C will also be responsible for transporting the list to the auxiliary guard house. The supervisor of the auniliary guard house will arrange for the transportation of the list to the main guard house. The phone nurber for the accountability
~~~ station at Building 902 will be Extension 452.~~
~~9. Health Physics personnel will call,the guard house and advise the badge numbers of non-contract personnel at the Control Point #1 account-ability station.~~
~~I r l~~
~~10. Health Physics personnel will call the guard house and advise the badge numbers of contract personnel at the control Point #2 ("A" Building) j accountability station.~~
~~l l i i~~
~~11. Operational Support Center personnel will phone the guard house and l advise the badge numbers of personnel at that location.~~
()N Page 3 of 7 Rev. 1
~~. - _ _ _ . -- - - _. _- -- - -_ .~~~
~~EP III-3~~
~~. ACTION STATEMENTS (CONTINUED)~~
~~M 11gE INfTfAL~~
12. Catalytic will have an accountability overlay et their accountability station and will be responsible for completing the overlay as expeditiously as possible. Catalytic will also be responsible for
~~' transporting the overlay .o the main guard house upon completion. .~~
~~13. Clerical personnel will call the main guard house and advise the badge~~
~~' numbers of clerical and secretarial personnel at the Clerical office accountability station.~~
~~14. Centractors wien ten (10) or more persons will phone the quard house and advise the badge numbers of personcel at their " start of work" location.~~
NOTE d () In the event the above badge information 12 not reported within 20 minutes after the initiation of the personnel accountability, the Shift Sergeant will initiate a phone call to the contractor. 1*. Assign a sergeant and security officer to transpose incoming badge information onto the main guard house accountability everlays. Over-lays received from the auxiliary guard house, cafeteria and Catalytic ' will be aligned with the Master Accountability List. )
16. A status report will be mad $ to the Cantrol Room no later than 20 minutes after initiation of the accountability. The report will include the status of the accountability and which stations have reported in thus far. After the initial call, status reports will be made to the Control Room every ten (10) minutes until termination of the accountability. The telephone numbers at the accountability stations are listed in Attachment 2.

17. An accurate documentation will be maintained of all events during the accountability. Listed below is informatien to be recorded:
b(N l 1 i Page 4 of 7 Rev. 1 f
EP 111-3 (q/ $CTION STATEf*EflTS (CONTINUED) 11gE INITIAL
a. Time accountability announcement received, by whom, how received and when terminated,

b. Time sacerity officers were in position at accountability posts in the cafeteria, auxiliary guard house and main guard house.

c. Time information received from operational Support Center, clerical Office, Control Point fl, Control Point 92 ("A" Building),
~~cafeteria, Building 902, auxiliary guard house, Catalytic and all other contractors with ten (10) or more persons.~~
~~d. Time Control Room notified of various stages of the accountability.~~
The photobadge number and name of each individual unaccounted for at each stage of the accountability will also be docum.ented. O The Accountability Check List may be utilized to coordinate documentation (Figure No. 11. NOTE The Master Accountability List will be the only account-ability list utilized at the main guard house for the i final badge count. At the termination of the account-ability, the Master Accountability List will be submitted to the operations Chief with the shift reports. The Master Accountability List will be maintained in the
" administrative office during the normal working day, and kept current by the secretarial staff. The Master List will be picked up by the "B" Shift Sergeant each day prior to the closing of the administrative office. The Master Accountability List may be picked up at the office if an accountability is called during a normal working day. Badges that are to be removed due to duplication, terminations, etc., will only be pulled upon request by administrative personnel.
f-~5 U l I . Page 5 of 7 Rev. 1
l l l EP III.3 (m) ACTION STATEMENT'5 (CONTINUED) 1 M INITIAL Guard force personnel who receive information of termination or badge duplication will forward said information to the administrative office. Administ.rative personnel will then coordinate the badge removal.
18. The Sergeant will initiate a check with CAS/SAS on status of each individual not accounted for during the accountability. Individuals found to be logged "off-site" will be considered accounted for, however, the infortnation regarding the missing badge will be documented in the log. Individuals logged "on-site" will be documented and reported " unaccounted for".
NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. O ____..__...__..__.........__.______.......__ ___..___....___....__....__....____..............__ Prepared By: / V
~
Reviewed By: /0!Z6 8- / pa rt' men H d ' Date Reviewed By: )O/Z6 !E/
~~' Date ' ' Assistant to Manager Reviewed Dy: h [ [// /~~
~~Station Quality Assurance Engineer Dat& SORC Meeting No.: b[ ~ / Il /O/27 !9 /~~
' Date Approved By: / k Manager - Sakem Generating Station ~Date M [, / 3 --
Approved By: . . Cate Manager - Emergency PrepEredness i ['T ( O i 1 i l l l Page 6 of 7 Fev. 1
EP III-3 FIG. 1 FIGuo.E 1 ({}} ACCOUNTABILITY CHECK LIST TIME IMITIATED TIME COMPLETED ACCOUNTABILITY EVENTS ACTIVATION OF ACCOUNTABILITY STATUS CHECK OF POSTS SECURE DOORS, TURNSTILES & VEHICLE GATES (AUX & PAIN GUARD HOUSES) CHECK OF BADGE DPAWERS (AUX & MAIN GUARD HOUSES) LOG OF EVENTS I OFFICERS TO CAFETERIA CHECK OF FISH HOUSES, I. A. , TRAILERS & TRAILER COMPLEX BUILDING REPORT FROM CONTROL POINT (AUX) REPORT FROM CONTROL POINT ("A" BUILDING) REPORT FROM CONTROL ROOM REPORT FROM CAFETERI A FIPORT FROM ADMINISTRATIVE OFFICE REPORT FROM CATALYTIC BUILDING 320 REPORT FRCM UE&C BUILDING 902 RIPOST_FROM SPD BUILDING 902 20 MINUTES INTO ACCOUNTABILITY 1ST MiPORT TO CONTROL ROOM 30 MINUTES INTO ACCOUNTABILITY IND REPORT TO CONTROL ROOM 40 MINUTES INTO ACCOUNTABIL1TY 3RD REPORT TO CONTROL ROOM AFTER ACTION REPORT O 1 Rev. 1 Page 7 of 7
EP III.A EMEP.GENCY PROCEDURE f)
~~'- EP 111-4 SITE EVACUATION ACTION LEVEL~~
~~1) Upon receipt of notice from the Senior Shif t Supervisor, Emergency Duty Officer er designee that site evacuation is necessary.~~
~~SCTION STATEMENTS 115E INITIAL~~
1. Security shift Sergeant shall assign security force personnel to:

a. Establish traffice control at the end ef the access road until the arrival of municipal police,

b. Place the turnstiles in freewheel mode,

c. Collect security badges at both guard houses.

d. Direct and assist exiting personnel to form three (3) and four (4) people carpools.

e. Direct an ordsrly exit of the parking lots.

2. Security Shift Sergeant shall standby for instructions regarding the disposition of his security force.
NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. Oi v Page 1 of 2 Rev. 1
EP III-4 Prepared By: j' 7 / Reviewed By: _
~~/ t'e ' D~pa me Head Reviewed By:~~
Assistant to Manager / Date/ Reviewed By: h, !b ~!h[ Station Quality Assurance Engineer 'Date SORC Meeting No. b[ ~ I/I /O!27 /
/Date Approved By: [ ///d/IW 'Date' Manager 4 Sa W Generating Station * / 2./ 72.,
~~Approved By:~~
~~Date Manager - Duergency Preparedness 1~~
1 O I l l Page 2 of 2 Rev. 1
EP III-5 () EMEPGENCY PP.0CEDUP.E EP III-5 EFERGENCY VEHICLE SUPP0P.T ACTION LEVEL
~~1) Upon notification from the Senior Shift Supervisor, Emergency Duty Officer, or designee regarding incoming or outgoing emergency vehicles.~~
~~ACTION STATEMENTS lidE INITIAL a 1. Incoming Vehicles 1/~~
~~a. The Security Shift Sergeant will dispatch two (2) Security Force Members (SFM) in the security vehicle to the Hope Creek "Y" on the access road.~~
l O b. The STMs will meet the incoming emergency vehicle at the "Y". One (1) SFM will lead the emergency vehicle directly to the scene of the emergency and remain with the emergency vehicle until it leaves the site. NOTE The incoming SFM shall notify the guard house to open the vehicle gate to expedite entrance to the site.
~~"Y" in order to direct any~~
~~c. The second SFM will remain at the further off-site emergency personnel who may be in transit. He/~~
~~she shall remain at this post until recalled by the Security Shift Supervisor or until relieved by a fire police representative. I 2. Station Ambulance j O (,,/~~
~~a. The Security Shift Sergeant will assign an Assis tant Sergeant to drive the station ambulance to the location of the emergency and j~~
~~to the hospital if required upon notification from the Senior Shift Supervisor, Emergency Duty officer, or their designee. Page 1 of 2 Rev. 1 l_~~
~~. EP III-5 NOTE rorward all completed foms to the Assistant to Manager (SGS) .~~
~~Attach any refrienced completed EP's or attachments.~~
~~=___...-- .....--.~~
h k Prepared By: , v v - Reviewed By: (C !) G M/ ep 'tm nt dead / Date Reviewed By: /O!3Io!h/ Assi tadt to Manager ' Date Reviewed By: _
/O T.h 5tation Quality Assurance Engineer (Date SORC Meeting No. : hl ~ / l/ /0!)7 / Dat/e /
Approved By: 4A M /[/3 Manager - Kale:VGenerating Station 'Uate' Approved By: - * / L/ N Manager - Emergency Preparedness Date (J Page 2 of 2 Rev. 1
EP IV-101 { O EMEP.GEflCY PROCEDUPE EP IV-101 ! TSC INITIAL RESP 0flSE ACT10ft LEVEL This procedure shall be followed whenever the Radiation Protection Emergency Organization is activated. ftESP0ilSIPLE INDIVIDUAL A. BACKSHIFTS AND WEEKENDS The predesignated individual or the Emergency Assignment Shift Schedule (normally the shift RPT). B. NCPy.AL DAY SHIFT (MONDAY - FRIDAY) The Senior Representative from Radiation Protection (normally the Radiation Protection Engineer). LIMIT ON AUTHORITY The approval of the Senior Sh$f t Supervisor /EDO shall be obtained prior to initiating the following:
1. Re-entry into evacuated areas.

2. The initial dispatching of off-site survey teams.
~~ACTION STATEMEtiTS TIME INITIAL~~
1. Check the dose rates in the TSC. If greater than 100 mr/hr, consider evacuation within one hour. If greater than 1000 mr/hr, consider immediate evacuation. Proceed to an upwind location to avoid the p3ume.
i Primary Alternatives: l a) Control Room O Page 1 of 4 Rev. 1
EP IV-101 i SCT10fi STATEMEfiTS (CONTINUED) M INITIAL secondary Alternatives: a) "A" Building c) Administration Building b) Hope Creek d) Main Gate See Procedure EP IV-201 for further guidance.
~~2. Establish contact with the Control Room and obtain a briefing on the incident. Record pertinent information in the log book. Synchronize your watch with the Control Room.~~
J. Contact the Senior Management member of the Radiation Protection Group. Provide him with the important details on the incident. The Radiation Protection Engineer should refer to EP IV-122 and decide on the number and level of personnel required to respond to the incident. O NAME _HOME PHONE WORK FXT. _, BEEPER MiVACY ACT IN:0 N A" 05 NOTE The contacted supervisor should call the remaining supervisors, who will in turn notify the rest of the organization. If no supervisors can be reached to initiate the call in process, use your discretson and call in the necessary personnel. If the phone system is inoperable, contact the police with the radio in the Control Room, request them to notify key members of the Emergency Organization. O Page 2 of 4 Rev. 1
EP IV-101 Q ACTIO!! STATEPEtlTS (CONTINUED) M INfTIAL
~
4. Contact the Control Point and ensure that on-shift personnel are accounted for. If dose rates are greater than 2 mr/hr at the Control Point, see the procedure, " Control Point and Equipment Evacuation" (EP IV-105). ,

5. Ensure that the NMC-CAM and RMS-2 monitors are operational in the TSC.
~~Backup instru=ents should be used if either monitor is inoperable or if the readings are contradictory.~~
~~6. Consider obtaining addition personnel assigned to other departments (i.e. , Chemistry, I&C, Maintenance and Administration) .~~
S
~~7. Inspect the TSC emergency equipment and ensure its readiness.~~
~~missing or inoperable items should be replaced with equipment z. e ;he Control Point. Tha SAM-2/RD-19 counter should be turned on and allowed~~
~~) to stabilize.~~
8. If a request (for surveys, re-entry, etc.) is received, use the appropriate procedure to carry out the task.

9. As the survey data is received, use the Dose Calculation procedures to obtain dose estimates (EP IV-lll or EP IV-113).

10. As personnel arrive from off-site, assign them to work locations.

11. When relieved by Radiation Protection supervision assume the responsibility for environmental monitoring.
NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. O V Page 3 pf 4 Rev. 1
EP IV-101 Q eTTACHPIflTS None l [CTUNICATIONS NEi E K I TSC Control Point MP Computer 200 611 Control Room 1 Control Room 2 ! SSS l 2o2 633 a2 641 635 623 PRVACY ACT DlSCUSSION INFORMATON Rapid manning and subsequent operations of the Technical Support Cent regaining control in an emergency situation. er are key parts of communications, personnel and material logistics, dose assessment,It is the heart The initial responses in an emergency have a great bearing on the finaland outecme. PA determinations, et Prepared B - Aw m Reviewed By: ,/ Def Ad d I ate' Reviewed By: {L __ [ ssistant to Manager J Date' Feviewed By: _ hCh _ !M L4th on QuIility Assurance Enganeer Cate 50RC Meet 1ng No.s 0$ ~ lI( (C f27 f k/ Date Approved By:
~~/k v Manager Sralev Generating Statton / /M/~~
Dater Approved By:

Jk -
~~Manager - Emergency Preparedness I / k~~
~~Date~~
{ l i O
EP IV-102 O EP.ERGENCY PROCEDURE EP IV-102 CONTROL ROOP INITIAL PESPONSE ACTION LEVEL This procedure shall be followed whenever the Radiation Protection Emergency Organization is activated. BESPONSIBLE INDIVIDUAL This procedure will normally be implemented by the Control Room Accident Assessment Liaison predesignated on the Emergency Shift Schedule. LIMITS ON AUTHORITY Re-entry into any evacuated areas shall be approved by the Senior Shift Supervisor /EDO. SCTION STATEMENTS 115E INITIAL O 1. Notify the Senior Shift Supervisor and the OSC Coordinator of your arrival.
2. Obtain a briefing on the incident.

3. Observe readings on the radiation monitors in the Control Room (refer to Attachments 2, 3, 4 and 5). Check airborne radioactivity concentra-tions in the Control Room. If the continuous air monitor is inoperable, initiate a low volume air sample. If any air monitors indicate significant deviation above normal trends, inform the Senior Shift Supervisor and the TSC immediately.
NOTE The air sample should be taken in a location that is representative of the breathine zone air. It sneuld not subject the operators to the distracting noise from its operation. Compare the air sample results to Attachment 1 for the recommended actions. Page 1 of 22 Rev. 1
EP IV-102 O SCTION STATE!'EilTS (CONTINUED) V 1151 INITfAL
4. Contact the TSC and brief the representative frem Radiation Protection on the incident and survey results. Inform them of the correct time and which extension shall be used for further communications.

5. Assist the Senior shift Supervisor as required (i.e., communications, data recording, etc.).

6. If dose rates exceed 100 mr/hr and are expected to remain at this level for greater than 4 hours, consider reducing the number of personnel in the Control Room to a minimum. Dose rates greater than 1000 mr/hr may
~~require short rotating shifts until the Control Room can be secured.~~
~~7. Maintain frequent communications with the TSC.~~
l () 8. Note any fluctuations due to component or equipment operations. Ensure that the Control Room Operations staff is advised when their actions result in increased levels of radiation. Operations may be able to ] delay an operation which results in increased radiation levels in occupied areas.
~~9. If requested to perform dose calculations, see Procedure EP IV-lli or EP IV-ll3.~~
~~ATTACHMENTS~~
1. Recommended Actions vs. Radiation Levels i 2. Unit 1 Area Monitors

3. Unit 1 RMS Process Monitors

4. Unit 2 RMS Area Monitors

5. Unit 2 RMS Process Monitors i
l l i l Page 2 of 22 Rev. 1 i ' - - -- - - _,,
1 ZP IV-102 Od v COM*L'NILATIONS NETWODK TSC CONTROL ROOM 1 CONTROL ROOM 2 S5S dP COMPT:TER 201 633 641 635 m ,a ,e ,a,e ,a,e Page PR VACY ACT DISCUSSION IN:0RMAT.0N In the event of a Radiation Emergency, a Control Room Accident Assessment Liaison from Radiation Protection shall be dispatched to the Control Room. He will be responsible for Radiation Protection related duties, e.g., tracking radiation monitors, Control Room radiation surveys, contamination survey or returning operators and escorting personnel as required. NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced ccenpleted EP's or attachments. Prepared Bv-
~~, <d O) - - -~~
1
/
~~9 Reviewed By: p tr t d ad~~
/OffIb If I Date Reviewed By: IO 20 4 astant to Manager Date Reviewed By: M_" "Starion Quality Assurance Engineer [h '1 *l 8Datei SCEC Meeting No.i h ~ [!! /O 7 .
Date Approved By: /r Manager'- Sedem Generating Station /!/3 [b Da t e ' Approved By: _ tlanager - Emergency Preparedness d /!2,; f"[ Date 1 P e se a 1 er 9,*
~~% n~~
~~EP IV-102 ATT. 1 Q ATTACHIST I RECOMENDED ACTIONS VS. PADIATION LEVELS CCNDITION ACTION~~
>l R/ hour gamma Don SCBA respirators. Immediate evacuation of any non-essential personnel. Notify TSC of levels and -5 pCi/cc I concentrations and continue surveying. Institute shifts >10 2 for remaining personnel. Evacuate if in cold shutdown
~~>10~~
~~-5 uCi/cc Cross Particulate mode and approved by Senior Shift Superviscr/EDO.~~
i
>100 mR/hr gamma Don SCBA respirators. Notify TSC of levels and concen-trations. Continue survey. Evacuate non-essential -6 personnel and institute rotating shifts for those >10 pCi/cc or 1000 MPC I 2 remaining personnel within one hour. > 10 ' 0 pCi/cc or 1000 MPC Gross Particulate t
~~i >2 mR/hr gamma Don respirators with charcoal canisters. Periodic resurvey of conditions. Notify TSC'of survey results.~~
-8 >10 uCi/cc or 10 MPC I' O >10 -8 uci/cc or 10 MPC Gross Particulate >2 mR/hr gamma Periodically check radiation levels and airborne concentrations. >10-9 'Ci/cc or 1 MPC I 2 ~ >10 ' UCi/cc or 1 MPC Gross Particulate i
i J O Fage 4 of 21 Rev. 1
J, O O ATTA0it1EllI 2 SilGS UNIT 1 RADIATION 110NITORING EDUlPt1EHT AREA RADIATION MONITORS (Gr1 TUBES) NOTP. All Area Radiation Monitor Channels alarm in the Control Room except R 23, 32A and 32B. All Area Radiat f ort Monitor Channels have an equipment failure alarm light (at RMS rack in equipment room tiehind Control Roomt except for R-2, 3, 4, 6A, 7, 8, 10A. AIARM DETECTOR LOCAL SETPotNT INTER-(FIDOR) READ-CHANNEL IDCATION 11EK RANCE IN mR/ifr DESCRIP110N ELEV. DUT BLIX:. No. NE CORNER I .0001-10 R/hr W= 2.0 122 YES AUX. 2.5
~~'o IR-IA CONTROL ROOM A= $to t~~
CONT. BEWEEN #12 & 13 FAN Coll UNITS .0001-10 R/hi- 15 130 A12 130 YES w- IR-2 CONTAINMENT El. NE tome WAI.L E WAI L, NEAR DUMBWAITER .0001-10 R/hr 2.5 4 100 YES AUX. ' u R-3 RAD 10CHENISTRY LAB n .0001-10 R/hr 15 , 84 YES AUX. S WAl.1., BEWEEN fil & 12 IR-4 CHARCING PUMP ROOM CilAkCING PIIMPS , E WALL, CENTFR OF SPENT Fl!EL PIT 2 .0001-10 R/hr W= 10 FUEL IIANDLING BLDG. 130 YES FUEL IR-5 A= 15 E WALL, NEAR InlMBWAITER 0001-10 R/hr 2.5 SAMPLING N00M 110 YES AtiX. R-6A CONT. COLUMN A-ll, ON OUTSIDE WALL, NE 0001-10 R/hr 15 1R-7 IN-CORE SEAL TABLE 100 YES 0001-10 R/hr 25 100 YES AUX. COI.UMN SF-13.8' 20' FROM IDADOUT i R-8 WASTE I. DAD OUT IWR, N WAI.L 2 .0001-10 R/hr W= 10 130 Y F.S FUFL E WA1.L CENTER OF NEW FUEL IR-9 FUI.L STORACE ARFA STORACE A= 15 YES CONT. N WALL, 4' FROM IIATCH 3 0001-10 R/hr 15 IR-10A PFRSONNFL IIATCil TO CONTAINMI:NT 100 EL. 100 1 0001-10 R/hr W= 10 pn 130 YES CONT. NW InfE WAl.L. 8' FROH HATCH IR-10B l'I RMINNEl. IIATCH To CONI AINMENI A= 15 Q 'O l'. l . . 130 *H N WAl.L .OINil-10 R/hr 2.5 uf 100 YES AUX. , w R-205 COUNilNG ROOM
~
N l t . . _ _ _
q
\
A1 ARM DETl_CTOR IFCAL INTFR- SETrolNT CHANNEL (fUUR) READ-RANCE IN mR/Hr ELEV. OUT BLDC. II) CAT ION IAWK No. DESCRIPTION TOP OF STAIRWAY, GILLMN A-6, 01-!(MM) R/hr W= 500 IR-21 CONTAINMENT EL. 410 A6 130 YES CONT. A* I,000 W IMWE WALL W WAIL, %)5' FROM IJ1ADOUT In0RS 0001-10 R/hr W= 15 R-22 SOLID WASTE AREA 100 YES AUX. A= 25 SERV. IN HAI.I.W AY, ON E WALL .0001-10 R/hr W= 2.0 R-2) MONITORING ROOM 100 YES 2.5 A= COLtHN NN 12.3, E OF CHARCING .01-1000 R/hr W= 5,000 1R-24A S OL WATER IN)ECTION FILTER 84 YES AUX. PUMP A= 10,000 COLUMN NN 12.3 .01-1000 R/hr W= 5,000 1R-24B SEAL WATER INJECTION FII.TER 84 YES AUX. A = 10,000 COLUMN NN 12.3 .01-1000 R/hr W= 5,000 SEAL WATER FILTER 84 YES AUX. 1R-25 A = 10,0(K) 100 YES AUX. COLIHN PtfNN .01-1000 R/br nJ = 5,000 1R-26 REACTOR COOLANT FILTER A= 10,000
*o AUX. COLUMN FKLL 13.6 #12 Il0LDUP .01-1000 R/hr W= 5,000 IR-27 64 YES
$W LIQUID WASTE FILTER TANK A= 10,000 YES AUX. U)LtHN MMNN 12.8 .01-1000 R/lir W= 5,000 1R-28 SPENT FUEL PIT FILTER 100 A = 10,000 m PlHP ROON NE CORNER .01-1000 R/hr W= 5,000 N SPENT FUEL PIT SKIMMER FILTER 100 YES f11EL 1R-29 A = 10,000 YES AUX. COLtHN .ljl(K 12.3 .08-1000 R/hr W= 5,000 1R-30 REFUELING WATER PURIFICATION 100 A= 10,000 Fil.TER FUf L BOTTOM OF CRANE WAI.EWAY 4 .0001-10 R/hr W= 10 1R-32A FL'EL HAN0 LING CRANE 154 YES A= 25 FDFL BOTTOM OF CRANE WAI.KWAY 4 .0001-10 R/hr W= 10 1R-125 CASK llANDLING CRANE 166 YES A= 15 AUX. COLIHN MMNN 11.2 (1 DETECTOR) 01-1000 R/hr W= 5,000 JR-33 ION EXCHANGER FIL1ER 100 YES A = 10,000 AUX. MECHANICAL PENETRATION AREA .01-1000 R/hr W= 500 JR-34 MECHANICAL. PINETRATION 100 YES A= 1,000 AREA EL. 100 W o w N
~
O o INTtRIJKES: 1 - Control Room Intake Duct Isolation (Air on full necirculattoi. and full chill water flow). Dampers autcoattcally closed: ICAA 1, 2, 3, 4, 14, 28, 19, 20, 31, 32, and 33. Dampers automatically full open: ICAA 5 and 17. NOTE: If dampers ICAA 1, 2 and I are manually opened, 4% outside air will be added to recirculated air. 2 - Fuel Handitng Vent to itF.pA and Charcoal + horns and lights activate:d. 3 - 1.oc al Rights outside Personnel Hatch Doos- activated. 4 - Interlock to prevent outuard motion. 6
~~'o fD da 6~~
~~4 O tt 9J ab s~~
> t1 en *o 65 . w us M e W o 4 u H
O O O ATTACirENT 3 ; SNGS UNIT 1 P.ADIATION PONITORING E0UIPPENT ; PROCESS PADIATION PONITOPS o l NOTE i . I All Channels listed below readout ano alarm in the Control Room. , TYPE OF DFTECTOR PONITOR lt) DEL AIARM IDCAL RAD. HEAS. CHECK SENSITIVITY SET 11)lNT READ CHANNEL IDCATION & DE1ECTOR (SAMPl.ER VOUJHEJ SOURCE c /m/pC1/cc RANCE (CPM) INTERLOCKS DtTT NAME NO. DESCRIPTION' AUX BLDC., ELEV. 130 CAS MD12C(V-II) NO 10 t o 10' WARN: 600 NO CONTROL 1R-18 ROOH INTAKE CONTROL :. OOH A IR 4 CM S-y 81.49X10* (4.66XIO' cc) #4.0X10' ALARM: 2,000.. CONTROL ROOH INTAKE DUCT CONDITIONING MGl SOUTH
'o WALL 't.87X1068a DilCT IS01ATION (AIR 3O '3.0317' ON FULL RfC!Rept.A- ;
TION, AND FUI.L en - CHILL WATER FIA)W)** O es so PRIMARY R-6B OUT OF SERVICE. WILL BE SAMPLINC DELETED. ROOM PART. AIR PART. HD5B CONTAINMENT ALL SIX CONTAINHENT NO CONTAINMENT IR-ilA NORTH PENETRATION ~ OR VENT ELFCTRICAL SIDE, WEST (PkWINC) y X 10 to 10' if:~ " ~ 45,000 VFNill.ATION ISOLA-WAI.L. El.EV. 78, NEXT TO SCINT. (6 to 3 cfm) 4.4X10'8 cpm A: 60,000. TION VALVFS (LVCl PARTICULATE DOOR TO HECHANICAL SIDE FOR "Rb HRoth:ll IVC 6) ARE IN A MA-1B (V-5) SAMPLER, (CAI.CULATED WASTE CAS VFNT 'IDSFD, NO Ald SAMPl.E TAKr.N FROM CONTAIN- FROM " Mn 5It ~ I,000 ENTERS OR I. EAVES HENT DONE WALL AT El.EV. CALIBRATION) A: 7,000. CONIAINMENT; 150' INCI. TIDES ISOLATION CONTAINMENT OF PRESSURE-VACUIN 1.F.AK, del t C T ION RELIEF VALVES W: 10,009 A: 20,lMM) . . . . . . . . . . . ** I ,131,3 2 , 85 3 , 135 Xe ' = = Co =
' n: = Sely = Xe Ca M * = THEORETICAL CALCUI.ATION
~~[g j~~
** = DAMPERS AU10MATICAll.Y CIAISED: ICAA 1,2,3,4,14.28,19,20,31,32 AND 33. DAMPERS AUTOMATICAI.I.Y ITLL OPEN: ICAA $ AND 17. IMIE: IF DAMPtRS 4 "h ^ , ICAA 1,2 AND 3 ARE MANUAL.l.Y OPENED, 4% OU1 SIDE AIR Wil.L bE ADDED TO RECIRCUI.A1ED AIN. - S 4
i
O O TYPE DE DE1ECTOR MONITOR MODEL AIARM IDCAL CHANNEL IDCATION & ILAD. MEAS. CilECK SENSITIVITY SET PolNT RfAD NAME N0. DESCRIPTION DET EL70R (SAMPLER VOLUME) S0tlRCE c/m/pCl/cc RANCE (CPM) INTERIDCES OUT CONTAINMENT 1R-12A NORTil PENETRATION ELECT- CAS hcl 2C X
~~NO i OR VENT HICAL SIDE, WEST WALL, CM B-y 8 4.2X10'* 10 to 10' CONTAINHENT ~~~
AI.L SIX CONTAINMENT NOBLE CAS ELEV 78. NEXT TO DOOR 10 (6514 cc) #2.4X10' U- 3,75 V5.NTILATION ISOLA- t MECHANICAL SlDC IN A '2.26X10'* A: 5,000 . TION VALVES IVCl HQ-2A (V-2) SAMPLER '2.1X10' l illROUCH IVC 6) ARE WASTE CAS VEN CIDSED, NO AIR W: 1,000 LNifRS OR LEAVES A: 30.000[.CONTAINHtNT; INCLUDES ISOLATION CONT _AINNENT OF PRt.SSURE-VACUUM LEAK DETECTION EF VALVES W: 900 A: 1,000,.........." CONTAINMENT 1R-128 NORTil PENETRATION ELECT- IODINE HDSC X M) OR VENT RICAL SIDE, WEST WALL, SCINT. y 10pC1/cc 10 to 10' CONTAINMENT IODINE ELEV. 78. NEXT 10 DOOR () to 6 cfm) /100 cpe/hr** cpm 'W:~ ' ~ ~ ~ ~5X10' TO MECilANICAL SIDE IN A '3.0110' A: 10'..........." , j g MQ-228 SAMPLER cpm /m/pCi/cc i M VENT--
~~$ W: 1,500 A: 15,000..........."~~
o et 4 g CONTAINMENT 1R-13A NORTH PENETRATION MECilAN- LIQUID MD50 X *1.2X10' 10 to 10' W: 800 , w #11 FAN ICAL SIDE, ELEV. 78. WEST SCINT. y *2.4X10** cpm A: 1,500 COIL COOL- WALL IN A 4i3 SAMPLER (5800 cc) ING WATER CONT. #12 1R-138 NORTH PENETRATION MECHAN- LIQUID MD50 X 10 to 10' W: 800 NO FAN COIL ICAL SIDE. ELEV. 78, WEST SCINT. y 't.1X10' A: 1,500 UNIT COOL. WALL IN A 41:3 SAMPLER (5800 cc) '2.4Xio'* 1 I WATER CONT. #13 1R-13C NORTH PENE1 RAT 10N MECilAN- LIQUID HD50 X 10 to 10' W: 800*** NO FAN COIL ICAL SIDE. ELEV. 78, WEST SCENT. y St.2X10' cpm A: 1,500 UNIT COOL. WALL IN A 4i3 SAMPLER (5800 cc) '2.4X10** WA1ER 1 , 131, 2 ,, 85 3 , L 35, 4 , 133 Xe S
=0 l17 6 , 60 m 7 =
~~I3I Ba = PPy~~
* = THEORETICAL cal.Clit.ATION * * = 100 CPM HUILDill* IN I HOLIR = 10 40 pCl/cc of IM I 'N$ .g 888 = WARNING AIARM NOT INSTAL.I.Els ON Of.DLR STY 1.E DRAWERS y
t.# a , i ~ - t (
__ _ - . - _ - _ _ - _ _ _ _ _ - _ _ _ _ _ - _ _ _ . _ _ . _ . . - _ ~ . . . ._ . _ . - _ _ O O O TYPE OF DETEC10R MONITOR MODEL AIAkN IDCAL CILANNFL IDCATION & RAD. MEAS. CliFCK SENSITIVITY SET POINT READ NAME NO. DESCRIPTION DETECTOR (SAMPLER VOI.tME} SOURCE c/m/ pct /cc RANCE (CPM). IN1 FRIDCKS OtrT CONT. A14 1R-13D NORTH PENETRATION MECHAN- LIQUID MD50 X 10 to 10' W: 700 NO FAN COIL ICAL SIDE, ELLV. 78. WEST SCINT. y 'I.lX10' cpm A: 1,500 UNIT COOL. WALL IN A 4s3 SAMPI.ER (5800 cc) ' 2. 4 X 10'
WATER CONT. #15 1R-13E NORTH-PENE1 RATION MECHAN- I.IQUID MD50 X 10 to 10' W: 800** NO FAN COIL ICAL SIDE ELEV. 78. WEST SCINT. y 't.3X10' cpm A: 1,500 UNIT COOL. WALL IN A 4s SAMPLER (5800 cc) '2.4X10'*
WATER WASTE CAS 1R-14 NORTH PENETRATION, ELEV. CAS JOHNSON BLUE X 10 to 10' NO EFFLUENT 100, UNDER fil & 12 FilB CM TUBE #GP-200x50 '2.7X10' A: 20,000..CASFOUS WASTE DIS-EXHAUST FANS INTAKE DUCT '2.4X10' CHARCE VALVE (MG-2A(V9) SAMPLER) , (!WC41) IS CIDSED s CONDENSER 1R-15 TURBINE BLDC.. ELEV. 115, CAS HD12C X 10 to 10' W: 2,000** NO AIR EJECTOR EAST SIDE BETWEEN #12 & CM S-y '4.2X10'* A: 10,000..NONE d 13 G NDENSERS (HQ-199) (1.54X10'cc) 81.00XID'*
" '2.26X10'* $ '4.5X10' o
n u PLANT VENT 1R-16 ELEV. 194, IN PLANT VENT CAS MD12C(v-7) X 10 to 10' W: 2X10'** No M EFFLUENT NORTH OUTSIDE WALL OF 4 CM 8-y 81.95X10* A: 5XIO'...NONE CONTAINMENT (2.65X10' cc) 'HX10**
~~'l.82X10* '3.6XIC #~~
COMPONENT 1R-17A AUX Bl.DC.. ElEV. 84, #11 LIQUID MD5B X 10 to 10' W: 1,000 NO CCOLING COMPONENT COOLING PUMP SCINT. 1 'l.1X10' cpm A: 2,000..SURCE TANK VENT LIQUID ROOM RIGHT HAND SIDE OF (148 cc) *t.5X10'* val.VE #10C149 IS
~~#11 COMPONFNT COOI.INC CIUSED PUMP (MQ-181 SAMPLIR)~~
COMPONENT 1R-175 AUX BLDG., El.FV. 84, #12 LIqulD MD5B X 10 t o 10' W: 1,000*** NO COOLING COMPONENT COOLING PUMP SCINT. y '1.1X10' cpm A: 2,000..SURCE TANK VENT LIQUID ROOM RIGHT HAND SIDE OF (148 cc) *!.5X10'* VALVE #10C149 IS
#12 COMPONENT COOLING CIDSED P1HP (MQ-181 SAMPl.tR) 1, I n , 2 , 85 y 3 , 135 xe ' - ' "xe 5 -
~~Il# Ca 6~~
- "C0 # - I "Ba 8 - 11, h%
o w * = TiiEORETICAL CALCULATION tJ 6
** = WARNING ALAPM NOT INSTAL.I.FD ON OLDt.R STYI E DRAWERS o M. ame = WARNING AI. ARM NOT PRESENil.Y INSTAL.l.En .
w 4
_ _ . - _ _ - - - . _ . - - - - . .-. . -. . _ _ _ . . .-_ .. - _ ,. ._..-.-.-. . . _ - ~
~~. . _ . . . . _. . ~ - -. . _ . . . - . _ . = . . .~~
J r O o o TYPE OF DETECTOR AIARM IDCAL lt0NITOR MODEL L SET PotNT RFAD IDCATION & RAD. MEAS. CHECK SENSITIVITY CHANNEL (CPM) INTERIDCKS Otti _( SAMPLER VOLUME). SOURCE c/mfyC1/cc RANCE NAME No. _ DESCRifT10_N _ DETECTOR . 10 to 10' W: 400,000 NO AUX BLDC. . ELEV. 86, bEST LIQUID MD5B X LlyUID 1R-18 800,000.. FINAL LIQUID WASTE WALL OF BLDG. BEHIND #12 SCINY. y *2.9X10' cpm A I WASTE. DISCHARCE VALVE DISPOSAL WASTE MON!10R PUMP (!!61 cc) '7X10'* (lWL51) l$ CIDSED , (MW-2P(V15) SAMPLER) I 10 to 10' W: 1,500..#12 BIDWDOWN TANK NO - AUX BLDC., ELEV. 100, LIQUID MD5C X f!! STEAM 1R-19A INI.ET VALVE TS I ' CENERAIOR STEAM CENFRATOR BIDWDOWN SCINT. y 'I.0X10' cpm
'2X10'* CIDSED+ l B14WDOWN ANALYSIS ROOM IN PANEL. (!!61 cc) A: 10,000..S.C. BIJWDtWN ISO-321 (MW-2)(V!5) SAMPLER) IATION VALVE IS i CIDSED++
~~10 to 10' W: 1,500. .fl2 BLOWDtWN TANK NO LIQUID MDSC X~~
#12 STEAM 1R-19B AUX bLDC.. ELEV. 100 82.8X10' cpm INLET VALVE IS I CENERATOR STEAM CENERA10R Bl.OWDOWN SCINT. y *2X10'* CIDSED+
BLOWIWWN ANALYSIS ROOM IN PANEL (!!61 cc) A: 10,000. .S.N. BIDWDOWN ISO- , 322 (MW-2P(V15) SAMPLER) LATION VAI.VE IS g CIDSED++ ) X 10 to 10' W: 1,500..#12 BLOWDOWN TANK
~~p. #13 STEAM 1R-19C AUX BLDC., ELEV. 100, LIQUID SCINT.~~
HD5C y '2.7X10 7 cpm INLET VALVE IS ; CENERATOR STEAM CENERATOR BIDWDOWN i ANALYSIS ROOM IN PANEL (1161 cc) '2X10'* CIDS ED+ I eg BLOWDOWN A: 10,000..S.G. Bl.0WlOWN ISO-y 323 (MW-2P(vl5) SAMPl.ER) 1AT10N VALVE IS e4 CIASED++ X 10 to 10' W: 1,500. .fl2 BUWIWWN TANK No
~~#14 STEAM IR-19D AUX Bl.DC., ELEV. 100 LIQUID MDSC IN1.ET VAI.VE IS l~~
h1EAM CENERA10R BLOWUOWN SCINT. Y '2.9X10' . cpm CENERATOR CIDSED+ l ANALYSIS ROOM IN PANEL (!!61 cc) '2X10'* BLOWDOWN A: 10,000..S.C. BlDWDOWN ISO-324 (HW-2P(Vl5) SAMPLER) IA110N VALVE IS CIDSED++ f CHIM LAB R-20A OUT OF SERVICE - BEING l del.lTI ED . l
! 2 , 85 3 , 135,, 4 , I D,, 5,W g, 6,w gg 7 , I n,, 8 , gs t 131, .
* = THEONETICAL CALCUI.ATION y e., l
+ = CHANNELS 19A-D: VALVES 11-14 CB 10 I CB 50 ami 11-14 08185 CIDSE 'jN j ++ = CHANNil.S 19A-D: VALVES 11-14 CB 4 CIDSED 'w.'3 'Af E .
t
_ _ __,_4 _ _ . _ . - _ _ O O O TYPE OF DETECTOR MONITOR MODEL AIARM IDCAL CHANNEL IDCAT ION & RAD. MEAS. CHECK SENSITIVITY SET POINT READ NAME No. DESCRIPfl0N DETECTOR (SAMPLER VOLUME) SOURCE c/m/pC1/cc RANCE (CPM) liff ERIDCKS OUT LETDOWN IR-31A AUX BLDC., ELEV. 90. ON LIQUID MD50 No 10 to 10' W: 100,000 No LINE LEllNNN LINE NEXT TO THE SCINT. y cpm A: 250,000..NONE (CROSS) WALL BE1 WEEN PANEL 210 (OPEN (2" DIAM. PIPE) '4.9X10' AND THE LETixWM HEAT WINDOW EXCHANGERS DE1EC10R BLTTTS >100 kev) 10 PIPE, FAILED FUEL i MONITOR (HQ-224 SAMPLER) LETDOWN 1R-315 USES THE SIGNAL FROM THE LIQUID MD5C NO '9.4X108 10 to 10' W: 5,000 NO LINE DETECTOR FOR 1R-31A, IODINE y cpm A: 10,000..NONE (IODINE) Fall.ED FUEL PRINITOR SCINT. (2" DIAM. PIPE) , LETDOWN IR-31C NO DETECTOR - COMPARES LIQUID MDSC NO 10 to 10' NO LINE THE RATIO OF THE SIGNALS CROSS I y cpm A: 15%..NGNE (IODINE / FROM 1R-3tA & B MQ-229 IODINE (2" DIAM. PIPE) O to 10 VOLTS CROSS) RATIO INDICATOR, FAILED IUEL MONITOR n'o 4 STEAM 1R-35 AUX BLDG., ELEY. 127 LIQUID MD5C X 10 to 10' W: 5,000 NO REAR OF THE BLDC, NEXT SCINT. y 52.8X10' cpm A: 35,000.. CONDENSATE RElt!RN U CENI.RATOR
~~'6X10'* HEADER IS isotATED~~
,o BLAMIMWN TO THE REVERSE OSMOSIS (!!61 cc) n FILTER PANEL. IN A NW-2P(V15) (INLET STEAM & OUT-DISCHARGE
~~' LET CONDENSATE u~~
N 1INES) BY CLOSikG VALVES IHS49, lHS293, AND IHS909 EVAPORATOR 1R-36 AUX BLDG., ELEV. 84, 6 LIQUID MD50 X 10 to 10' W: 15,000 NO
& FEEDWATER FEET FROM SPENT FUEL PIT SCENT. y 'I.2X10' cpm At 35,000..ODNDENSATE LINE PREHEATER HEAT EXCHANGERS, 4a3 (5800 cc) '2.4X10 val.VE SHIFTS 3 WAT CONDENSATE SAMILER BIAWluMN LINE VAI.VE ICB-74 10 THE WASTE HotDUP TANK AND 108112 10 THE BIDW-IMMN 1 ANK l CONDENSATE IR-40 CONDENSATE POLISHING ION X 10 to "A = '2.0EO..NONE TES FILTER BUILDING, EL. 100 NEAR 10' ar/hr INI.ET PIPING 1 , 131, 2 ,85 3 , 135 4 , 133 g 5 , 137g , h , 60 m # III 8 =m = h hQ t.,
2
=a '# = THEORETICAL CALCUIATION ~
e o N. a n - N
t u v a TYI'E OF l$1ECTOR HON 110R HOl>FL ALARM IJ1 CAL CHANNEL IJ) CATION & RAD. HEAS. CHF.CK SENSITIVITY SET I'OINT READ NAME PM). DESCPIPTION ___ DE1FCTOR (SAMPIJR Vol,UME) SOURCE c/m/pC1/cc RANCE (CPN) I NTLR t.OCK S OtJT VENT- R-4) ROOF OF TLTRBINE BLDC. , SHIELDFD Y NO RFFER TO l-10,000 W: 50 USED WHEN INSTAL. LED NO ENERCENCY HAliVAY BETWFEN ITNIT 1 CH T0bE 1A-62 INFRCENCY mR/hr A: 100 VENT HONITONS ARE HONITOR AND LHIT 2 VENTS PROCEDitkEe- INOPERABLE OR OFF IOSE CAI.CS. SCALE 1 ,131 g 2,M Kr = Xe
~~xe -~~
~~I Cs - CO = 'Ba = FPy 5o G e* u O e V% u~~
*u.:!
~~O u W~~
,m ,s ,a i \ ( ) '%) (Y' L)
ATTACHMENT 4 SNGS UNIT 2 RADIATION MONITORING SYSTEM AREA RADIAll0H f10NITORS - I DETEt. TOR LOCAL ALARM CHANNEL (F IDOR) READ- I NTI' R - SLT PtilNT ko. DESCRIPTION ELEV. OtrT Bl.liG. IDCATION lorK RANCE IN mR/Hr 2RIA CON 1ROL ROOM (CM) 122 YFS CONTROL #2 W N1ROL ROOM ON PANEI. 2RPI ! 10 -10 ar/hr 2.0 2R2 CONTAINMENT (C*t) 130 YES CONT. BE1MFEN #22 & 23 FAN COfL UNITS 1&5 10'I-10 mr/hr 1.5 N.E. DOME WALL 2R4 CllARCING Pla!P ROOM (CH) 84 YES AllX . 011ARCINC PlfMP ROOM, NOFill WAl.L. 5 10' -10 ar/hr 1.5 ACROSS FROM NO. 21 CilAkCING l'INP
~~'o 21L5 FUEL IIANDLING BUILDINC (CM) 130 YES 61JFl. EAST WALL, CENTF.R OF SPENT FUEL 2 10'I-10 er/hr 1.1 M~~
40 HAND. PIT 2R7 INCORE SEAL Trai.E (CM) 100 YES CONT. BY SP/1 TABLE ACCESS Ex10R 3&5 10'I-10 er/br 1.5 ' k U 2R9 FUEL STORACE AREA (CM) 130 YES FUEL EAST WAl.l., CENTER OF NEW FIIEL 2 10' -lb sa/hr 1.1 HAND. STORACE RACKS 2A40A PERSONNEL llATCl! EL. Iva (CM) 100 YES CONT. NORTH Wall., ACROSS FROM 3&5 10' -10 mr/hr 1.5 PERSONNEL. HA1Cil , 2X108 PERSONNEL llATCH EL. 130 (CN) 110 YES CONT. NORTH WEST DOME WALL, NEXT 10 3&5 10' -10 mr/br 1.5 IIATCH 2R21 CONTAINMENT HI RANCE (ION) 100 YES CONT. TO BE DFIETFD 10'-10 R/hr* l.0 2R24A SFAI. WA1ER INTECTION FILTER (IOR; 84 YES AlfX. IN !!Al.lRAY ADIACFNT TO CHARCING 6 10' -10 mr/hr 1.0 PlHP ROOM ON WEST WAl.L 2R24R SEA 1 WA1ER IN il CilON Fil.1FR (ION) !!4 Yl'S ALIX . ADIACENT TO 2H24A, ACROSS FROM 6 10-10 a.r/hr 1.0 p pg PANtl. 209-2 ' l '8 G
~~-l 4. t4 g 2R25 SEAL WATER FIL1lR (ION) 84 YES AllX. ADIACENT 10 2R24A & n 6 10 -10 mr/hr 1.0 g W~~
_- _ _. m _ = _ . m -_ _..__ . _ _ , _ _ _ _ _ . _ _ . m_ m _ -. . - . ._.__.--_.m_,=_ _ _ _ _ _ _ _ -._ _ m_ . ~ _ _ _ _ _ _ . _ O O DETECTOR IDCAl, AIARM (FIDOR) RFAD- IN1FR- SETrolNT CHANNEL No. DESCRIPTION ELEV. DUT Bl.IIG. IDCAT,10N LA CK RANCE IN mR/ltr 1' 2R26 REACTOR COOLANT Fil.TER (ION) H)0 Yr.S AUX. HOUNTED IN FILTER FIT, AT S.W. 6 10"I-10 er/hr 1.0 Q1RNER 2R27 LIQUID WASTE FILTER (ION) 64 YES AUX. SOUTil WALL OF WASTE Il0LDUP TANK 5 10-I-10 mr/hr 1.0 ARFA 2R28 SPENT FUEL PIT FILTER (IUN) 100 YES AUX. MOUNTED IN FILTER FIT. AT N.W. 6 10'I-10 mr/hr 1.0 CORNER i 2R19 SPENT FUEL SSW FILTER (ION) . 84 YES FUEL MOUNTED ON INSIDE OF LEAD 5 10'I-10 er/hr 1.0 HAND. SHIEl_ DING WALL, ADJACENT 10 FILTER 2R30 Rs"/UELINC WATER PURIFIER 100 YES AUX. HOUNTED IN PURIFIER FILTER FIT, 6 10" -10 mr/hr 1.0 AT S.W. CORNER *; FILTEE -(PN) ! v i 2R32A Fl!EL HANDLING CRANE (CH) 130 YES FUEL EAST LEC OF FUEL llANDLING CRANE 4 10" -10 mr/hr 1.5
~~" IIAND. NEAR F100R Y.~~
k 2R33 ION EFCHANGE FILTER (ION) 100 YES AUX, MOUNTED IN FILTER PIT. AT S.W. 6 10' -10 mr/hr 1.0 u CORNER j r N
-I U 2R34 HECHANICAL PENETRATION AREA 100 YES AUX. HOUNTED ON SOUTH WALL OF SotITil 5 10 -10 mr/hr 1.0 q
(ION) MECH. PENE., COLUMN llH ADJACENT l TO PANEI. 311-2 2R38 STEAM CENERATOR BlDWDOWN FILTER 322 YES AUX. MOUNTED ON WEST WAI.L OF ENCIDSFR 6 10~ -10 nr/hr 1.0 ' (ION) 0F STFAH CENERATOR BLOW 110WN FILTER 1 2R39. CHANNEL STRUCT. NOT FOUND FirTURE 2R40 CONDENSATE FILTF.R (ION) 100 YES COND. SOUTH Wall. OF CONDENSATE 5 10'I-lu'ar/hr 2.DI " POLISH. POLISillNC BUILDING AD.lACENT TO INI.ET PIPING I 2R42A 21 WAS1E DECAY TANK (ION) 64 YES t.tiX . EAST WAl.L. CAS DFCAY TANK ACCESS S 10-10 mr/hr 4.0 IIAI.LWAY , NEXT 10 'I ANK PI F >Q
,l +
~~ENTRANCE '~~
*a ill */. ? 3 N
r
~~- - ---- .+ - - . - - - _ _ - -~~
. . _ .. .. .- . . _ _ . m -m_._ . ~ ._ .~ ~__.m.m .__ _.. . -. ...m . . . _ . _ . . .._._...m.. .___ _ . _ _. . . _ _ , _ _m .m. . . . . . _ _ . . _ _
k' AIARM DET LCTOR IOCAL (Flamap) kEAD- INTER- SETPOINT CHANNEL' DESCRIPTION El.EV. DUT B!l)C. IDCATION IDCK RANCE _ IN mR/Hr
'NO. ~
2R42B 22 WASTE DECAY TANK (ION) 64 1 C. AUX. EAST WALL, CAS DECAY TANK ACCESS 5 10' -10 mr/hr - 4.0 liALIWAY, NEXT TO TANK PIT ENTRANCE ; 6 E4 ! 2R42C 73 WASTE DECAY TANK (IDN) 64 YES AUX. LAST WALL, CAS DFCAY TANK ACCESS 5 10-l-10 er/br- 4.0 . i HALLWAY, NEXT To TANK Pli ENTRANCE 1 2R42D 24 WASTE DECAY TANK (10N) ' 64 YES AUX. EAST WALL, CAS DECAY TANK ACCESS 5 10'I-RO ar/br 4.0
~~^ HALLWAY, NEXT TO TANK PIT ENTRANCE t~~
INTERIDCKS: 1 - IsotATES CONTROL RtMM VENTILATION. . '
~~. .o So~~
2 - FUEL HANDLING VENTII.ATlutt To HEPA AND CHARCOAL, WITH HORNS AND LICHTS. -
~~>u 6~~
~~Z 3 - (X.AL LICHTS OUTSIDE OF 100'. AND 130' PERSONNEL HATCH DOORS ACTIVATED. i S 4 - INTERIDCKED TO PREVENT Ol*%iARD HOTION WITH ALARM LICliT. N -~~
$3 5 - LOCAL BEACON AND HORN. ,
~~6 - UKAL BEACON ONLY.~~
/
b
>M *9 'O .l H ae .:e >*
tre 0 4 " 'I p e
s
% - a ATTACHf1ENT 5 SNGS UNIT 2 RADIATION PONITORING SYSTEP PROCESS RADIATION MONITORS HICll TYPE OF AI.ARH AI. ARM HONITOR DETECTOR PODEL (BArACROUND-CPH) COUNTING CllECE & EENSITIVITY TAF IN WARNING SET POINT IN1FF-CHANNEL IOCATION & RAD.-MEAS.
c/r/pci/cc SDM+S RANCE ALARM (CPM) LOCKS NAME NO. DESCRIPTION _ DETECT (Ht (SAMPLER Vol.UMEl SOURCE 843-22 / Xe-133 6.4E7 30 1-10' c/m 6.5E2 1.0E3 ISOLATES CONTROL 2-RIB
CONTROL M*'41 INTAKE DUCT BETA INTAKE ROOH IN- (RA-8343-2) El.EVATIO4 122 SCENT. BETA SCINT.
isCT TAKE . DUCT 843-22 / Cs-117=3.6F.5 10 1-10' c/m 2.9E4 4.3F4 ISOLATES CONTAIN- 2-RilA* ELEVATION 78 BETA Sr-90-6.7ES CONTAIN-ItENT (RA-4303-2) COLUMN 16.8FF SCINT. BETA SCINT. Hl.NT IVC PARTICt- CONF. = 0.1 ELECT. PENET. HOVING FILTER AT 1 INCH /HR 1 To 6 y LATE (NORMAL SPEED) A e es 843-27 / Xe-133=3.3E7 20 b 1 ' t' c/m 2.89E4 4.33E4 ISOLATES CONTAlth 2-R12A* ELEVATION 78 BETA U BETA SCINT. CONTAIN-g HENT (RA-4330-2) COLUMN 16.8FF HENT IVC
% NOBLE CONF. = 0.1 ELECT. PENET. 1106 u CAS LOW " RANCE CAHHA y NOT YET IPH ALLED 10'-10' N/A N/A roNTAIN- 2-R12-H* ELEV ATIOG4 18 c/m HENT (RA-4330-2) COLUH;4 16.8 FF CH TUBE NOBLE ELECT. PENET.
~~CAS HICH RANCE CH ATTENUATED DETECTOR~~
/ l-131=3.1314 10 1-10' c/m 8.0E4 1.2E5 1sotATES CONTAIN- 2-Ri/R* ELEVATION 78 CAHMA 843-34 ,
c/m/m/pC1/cc 180 c/m/ CONTAIN-HENT (RA-4313-2) Col.UMN 16.8FF Nat y SCA 5m HENT IVC IODINE CONF = 0.1 ELECT. PENET. 1 TO 6 LOW RANCE FAIL
*
~~CONF. FACTORS NOT SHOW4 ON Tills SHEET ARE ALL .9 WHICll HEANS THAT IN 9 OUT OF IAST 10 ONE 5)COND COUNTS. Tile Al. ARM LETrolNT HAS BELN REArilED.~~
~~SETPOINT OVER 60 SEC. NE N us Y N o~~
~
F*
O O O TYPE OF NIC1 MONITOR DElLCIOR MODEL (RACKCROUND-CPM) COUNTING ALARM . M ARM CilANN Ft. II) CATION & RAD. MEAS. CilECK & SENSITIVITY TIME IN WARNING SET .'OINT INFR-NAME N0. - DESCRIPTION DE'IECTOR (SAMPLER VOI.UME) SOURCE c/m/pCl/cc SECONDS RANCE ALARM (CPM) IOCKS IliCH 2-Rl2H-il* ELEVATION 78 CAMMA 843-34 NOT YET INSTAL.1 ED 10'-10' N/A N/A RANCE COLUMN 16.6fF CM TUEE WITil CollfMNATOR c/m ATTENUATED ELECT. PFEET. DETECTOR 21 FAN 2-R13A* ELEVATION 100, SOUTH y y / Co-60=1.69ES 30 1-10' c/m 6.5E2 1.3E3 NONE COLL (RA-3907-2) PENE1 RATION ARFA SCINT. Cs-137=8.83E7 COOL.ING WATER 2;/24 2-R13B* ELEVATION 100 SOUTH Y Y / Co-60=1.69E8 30 1-10' c/m 6.5E2 1.3L3 NONE FAN COIL (RA-3908-2) PENETRATION AREA SCINT. Cs-137=8.83E7 COOLING WATER 23/25 2-R13C* ELEVATION 100, SOUTil Y Y / Co-60=1.69E8- 30 1-10' c/m 6.5E2 1.3El NONE s N FAN COIL (RA-3909-2) PENETRATIol4 AREA SCINT. CS-137=8.83E7 j COOLING WATER e k CONDENSER 2-R15 ELEVATION 100, TURBINE BETA 843-22 / Xe- 113 = 5. 80E 7 30 1-10' c/m 3.5E4 5.3E4 NOhE u AIR (RA-4332-2) Bl.DC. VENT IN CENTER OF SCINT. BETA N E.IECTOR TUR8INE Blik'. ROOM PLANT 2-R16 192' ELEVATION HETA 843-22 / Xe-133=3.5E7 30 1-10' c/m I.OE4 3.4E5 NONE VENT (RA-8356-3) PLANT VENT DUCT SCINT. BETA BETA (ONE) DETECTOR (CROSS) COMPONENT 2-RI?t AUX. BLDC., CAMMA 843-32 / Cs-137=8.83E7 30 1-10' c/m 9.lE) 1.8E4 Cl.OSES COOLING (RA-4332-2) ELEVATION 84 SCENT. Y C(h60=1.69E8 COMPON-WATER ENT (21 IlX) COO!.INC SURCE TANK WENT val.V E
* = CONF. i'AC10RS NOT SilOWN ON THIS SilEET ARE AI.l. 9 WillCH HEAPS TilAT IN 9 OtrT OF l.AST 10 ONE SFCOND COUNTS lilE Al. ARM St.1 POINT llAS HFEN RFAClli p. Fall kh SETP0lNT OVER 60 SEC. lI g N b 3
~~._ _ _ _- - .~ .- .. .- _ _ . _ -. -~~
O TYPE OF HICH PRINITOR DETFCTOR MODEL ( B ACKCR0l'ND-CPM) COUNTING AIARM AIARM CllANNEL IDCATION & RAD. MEAS. CHFCK & SENSITIVITY TIME IN WARNING SET PolNT INil R-NAME NO. IrLSCRIPTION DETECTOR (SAMP!Ik Vol.lfME) SOURCE c/m/pCl /cc SECONDS RANCE ALARM (CPM) IKKS COMPONENT 2-Rl75 AUX. Bl.DC. CAMMA B43-12 / Cs-137=8.83E7 30 1-10' c/m 9.!El 1.8E4 Cli)SFS
.C001. LNG (RA-4333-2) El EVATION 84 SCINT. 1 Co-60=1.69E8 WMPON-WATER INT (22 IIX) Oull.ING Sl'RGE TANK VtNY VALn C LIQUID 2-R18 . AUX. BLDC. CAMMA 843-32 / Ca-137=8.81E7 30 1-10' c/m 2.0E4 3.0E4 SECURES RADWASTE (RA-4335-2) n.EVATION 84 SClNT. 1 Co-60=1.69E8 LIQP!D DIS-CllARCE, CIA)SES WL51 21' STEAM 2-R19A SOUTH MECilANICAL CAMMA 843-32 / Cs-137=8.83E7 30 1-10' c/m 5.4E1 2.6E4 AIARM-CENERATOR (RA-1626-2) PENETRAtl0N SCINT. Co-60=1.69E8 IS01A1ES
[ BIA1WlxNN j BLOWlhMN ELEVATION 78 val.VES; H WARN-e IS01ATts km , #22 BISMDOWN g M 1ANK 22 STEAM 2-R19B SOUTil MECHANICAL CAMMA 843-32 / Cs-137-8.8 3E7 30 1-10' c/m 5.LE3 2.6E4 AIARM-CENERATOR (RA-1627-2) PENE1mATION SCENT. Co-60-1.69E8 ISol ATES ELEVATION 78 BIA)WIXWN Bl.0Wil0WN , VA!VES; 2 WARN-I Sol.AT FS
#22 BLOWlu)WN TANK 23 STEAM 2-R19C SOUTH MECilANICAl. CAMMA .843-32 / Cs-137=H.83E7 30 1-10' c/m 5.4E3 2.6E4 AIARM-CENERATOR (RA-1628-2) PENETRATION SCINT. Co-60=1.69E8 ISol.A B ES BLAMIMNN El.EVATION 78 BifulM1WN VALVES; WARN-ISet.ATES *El ?s BuuixuN TANK
~~N-<~~
$ S
O O O li t CH TYRE OF ( B/ CKCROUND-CI'M) COUNT!hC AIARM AIAltM MONITOR DETECTOR MODEL RAD. MEAS. CllECK & SENSI1IVITY TIME IN WARNING SLT Pol %'T IN!bH-CllANNEL LOCATION & c /m/pCi /cc SECONDS RAN1E AIARM (CFM) IfMAS NAME NO. DESCRIPTION DETECTOR (SAMP!.FR VOLUME) SOURCE CAMMA 843-32 / Cs-137=8.83E7 30 1-10' c/m 5.4E3 2.6F4 ALAFM-24 STEAM 2-R19D SOUTil MECHANICAL Co-60=1.69E8 ISol.AT ES CENERAIOR (RA-1629-2) PENETRATION SCINT. B10 Win NN Bl.0WDOWN ELEVATION 78 V AI.v ES ; WAkN-ISotATES 622 PIDWIu NN TANK 1 l Fall 2-R31 AUX. BLDC. El.EVAT.10N 84 CAMMA 843-34M / 2" Pb l-10' c/m 3.29F5 6.58E5 NONE FUFL (RA-4316-2) I.ETDOWN PRESSURE CONTROL SCINT. y Cs-137=9.4'.5 ROOM OPEN WINDOW LEllRMN Co-60=3.2Ft> OPEN ?JIN!WJW 2-R35 AUX. Bl.!M:. CAMMA 843-32 / Cs-137=8.83E7 30 1-10' c/m 1.82F4 1.49E5 PRfVENTS S1EAM Hl owt u tWN SCINT. Y Co-60=1.69E8
.o CENERATOR (RA-8024-2) ELEVATION 122 froM Jc- BLOWDOWN FILTER e.E1 URN -
ING TO u DISCllARCE CON 11FN-O MONITOR o DIRECT-ING TO [ CVCS Ik11.1:UP TANK 2C1174, 112 EVAPORA- 2-R16 AUX. BLDG. El.EVATION 84 CAMMA 843-32 / Cs-137=8.83E7 30 1-10' c/m 1.77E4 2.65E4 PRFVENTS Co-60=1.69E8 CONDEN-TOR FEED (RA-8354-2) DETECTS I.EAKAGE IN BORIC SCINT. Y SAIL 6 PRE- ACID EVAPORATOR AND FFoM HEATER WASTE EVAPORATOR RETIIRN-CONDEN- ING 10 SATE TtIRBINE BLIM;. NON-RAD Ri7 NOT YET INSTALL.ED 1.lQUlb pg O 'o WASTE 3 Y. N
~~~ _~~
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EP IV-103 EFERGENCY PP.0CEDURE
~~" f)~~
EP IV-103 C0flTROL P0lflT INITIAL PESP0flSE ACTI0fl LEVEL This procedure shall be followed when the Radiation Protection Emergency Organization is activated. RESP 0fiSIELE IllDIVIDlJAL This procedure shall be implemented by the predesignated Radiation Protection individual on the Emergency Assignment Shift Schedule, delegated to the Control Point. LIMITS O!LAUTHORITY
1. Re-entry into any evacuated areas shall be approved by the Senior Shift Supervisor /EDO.

2. After evacuating the Centrol Point, the Senior Shift Supervisor /EDO shall be notified.
~~eCTIO!1 STATEMENTS A L/ M INITIAL~~
~~1. Survey and determine radiological conditions. Compare conditions with corresponding actions.~~
~~CONDITION ACTION~~
>l R/hr Gamma Immediate evacuation, notify TSC. -5 >10 uCi/cc I 2 -5 >10 pCi/cc gross particulate >105 mR/hr gamma Don SCBA respirators. Continuous air sampling, continuous monitoring of back- >10"6 uCi/cc or ground levels. Notify TSC of levels and 1000 MPC gross concentrations. Evacuate personnel particulate TLD's. Consider personnel evacuation in >100,000 dpm/100 cm 2 i >10 mR/hr Gcama Don respirators with charcoal canisters.
~~Periodic resurvey of airborne concentra-~~
-8 tions and radiation levels. Notify TSC >10 uCi/cc or 10 MPC I 2 of levels and concentrations. Prompt p evacuation of personnel TLD's. Consider
( (, >10
~~-8 uCi/cc or evacuation within one hour.~~
10 MPC gross particulate Page 1 of 4 Rev. 1 i
t EP IV-103 j l i l 1 ({])ACTIONSTATEMENTS(CONTINUED) 115E- INITIAL I CONDITION ACTION 1
~~>2 mR/hr gamma Don respirators with charcoal cartridges.~~
~~Notify TSC of survey results. Periodic~~
~~>10'9 pCi/cc or resurvey of radiation and airborne 1 MPC I 2 c neentration levels. Consider evacuation of personnel TLD's.~~
9
~~>10 uCi/cc or 1 HPC gross particulate~~
~~<2 mR/hr Periodically check radiation levels and i~~
~~-9 0 pCi/cc I 2~~
2. Maintain access control. Do not allow personnel into evacuated areas without the approval of the Senior Shift Supervisor /EDO.

3. Perform an accountability check of personnel in the controlled area.
l () . Note the names of personnel and their work locations and report information to Security Guard reporting to the Control Point or the Main Gate. Any personnel missing from the Radiation Protection Group should also be reported to the TSC.
~~4. If radiation levels at the Control Point are acceptable, remain, and as time permits, consider the following actions:~~
al Shutting the water tight doors to the Auxiliary Bay. l b) Continue to monitor the radiation levels at the Access Control Point, and document on the appropriate survey map. i l l i c) Perform operability checks on Counting Room instrumentation. Note any significant changes in background. d) Check the operability of Emergency Equipment. r-j.b-e) Get the high range dosimetry ready for issue. l Page 2 of_4_ Rev. 1
EP IV-103 ())) SCTI0il STATEMENTS (cONTINbED) T LME INITfAL f) Obtain briefings on the incident from TSJ. g) Contact the Control Room for radiation levels on the radiation monitors. h) Consider the evacuation of essential eq2ipment if radiation levels are increasing. 4 i) Brief yourself on Control Point Evacuation Procedures, and alternative Control Point locations. T NOTE Forward all completed forms to the Assistant to Manager (SGS). j O) (, Attach any referenced completed EP's or attachments. ATTACHMENTS None COINUN NATIONS NETWORK TSC CONTROL ROOM 1 CONTROL ROOM 2 SSS OFFICE ' CONTROL POINT SECURITY 201 633 641 635 614 500 200 611 642 623 551 DISCUSSION When an emergency situation arises, determination of habitability of the Control Point is essential to maintain personnel and materials access control. l -) l Page 3 of 4 Rev. 1 l 1
EP IV-103 O 1 Prepared By: . Reviewed By: f3 D&p r nt _ead / te Reviewed By: sist t to Manager
~~! iDate' ,~~
~~Reviewed By: ( [ 5Date'~~
~~4) l 5 tat 1Tn Quality Assurance Engineer SORC Meeting No. hf'lII /Of27 /~~
' Dath Approved By: d ///J/W / Dater Manager - S61em Generating Station Approved By: .
~~M[ / L/ b Manager - Dnergency Preparedness Date O~~
O Page 4 of 4 Rev. 1 l
EP IV-104 EMERGENCY PROCEDUPE (~') N/ EP IV-104 TSC EVACUATION ACTION LEVEL l Thts procedure shall be implemented at the request of the Senior Shift Supervisor lEDO). The l i following radiation levels are guidelines for evacuation: A. The instantaneous dose rate exceeds 1000 mr/hr. 03
~~3. The dose rate (when averaged over one hour) exceeds 100 mr/hr and is expected to remain at this level for 24 hours.~~
BESPONSIBLE INDIVIDUAL This proce(.ure shall be implemented by the Shif t Radiation Protection Technician or the Senior Superviser of Radiation Protection in the TSC. LinlTS ON AUTH00lTY lD Unless a life threatening situation exists, approval of the Senior Shift Supervisor (EDO) shall be obtained prior to evacuating the TSC. ACTION STATEf'EUTS TIME INITIAL
1. Upon receipt of the request to evacuate the TSC, contact the Senior Shift Supervisor /EDO and obtain permission to set up the TSC in new location. The primarv alternate location is the Control Room; other alternate locations include a) Main gate b) Administration Building c) Hope Creek d) "A" Building rm Page 1 of 4 Rev. 1
~~EP IV-104 Q GCTION STATEMEfiTS (c0NTINUED) INfTfAL l ligE~~
~~2. If time permits, take the following items with you:~~
~~a) Log book-b) Calculators c) Maps d) Removable phones e) Computer access equipment f) Radios g) Radiation Instruments / Dosimetry h) Respirators~~
3. Consider the use of protective clothing and respirators if the possibility of encountering significant radiation levels exists while enroute to the new location.

4. Proceed to the new location in an orderly fashion. Ensure a dose rate instrument is utilized during the transfer as unexpected radiation fields may be encountered.
i
~~5. Upon arrival at the new location ensure that Security, the Control Room and.other off-site agencies are aware of the new location and the phone numbers.~~
l
~~6. Personnel should be surveyed for contamination that may have been i~~
~~encountered during the transitiota.~~
~~7. If additional resources or personnel are required due to the transition, contact the Administrative Assistant, f~~
, ("')) l l l Page 2 of'4 Rev. 1
EP IV-104 /~ U' SCT101 STATEMENTS (CONTINUED) Ilhi INITIAL
8. Return to the initial response guide - EP IV-101. Ensure the remaining applicable steps are completed.

9. Note the radiation levels at the new location. If the levels are still significant, consider further evacuation or addition protective measures.
ATTACHMENTS None C0mVNICATIONS NETWORK MAIN GATE TSC CONTROL POINT RP OFFICE CONTROL POCM 1 CONTROL ROCM 2 SSS 500 200 611 623 633 641 635 600 201 623 642 3 644 (Q 642 551 NOTE Forward all completed forms to the Assistant to Manager (SGS). Attaen any referenced completed EP's or attachments. DISCUSSION The TSC may have to be evacuated if personnel are expected to receive excessive radiation exposure. If the TSC is abandoned, consideration should be given to the removal of vital ecuip-ment and documents. Prompt relocation will be essential for adequate interface between off-site agencies and the site. . ________________________ - ____________________-- ______________________________=-- = = _---
~~;O LJ Page 3 of 4 pey. 1~~
~~EP IV-104 G / Prepared By: / MC Reviewed By: ey J E,epaf a en ead~~
/ O ! 7 le b[ / Date Reviewed By: /, < ( /O!26 As tant to Manager 'Date ,
~~Reviewed By:~~
'L7 Yk tMt1Cn Quality Assurance Engineer iDate' SORC Meeting No.: b['/(( / O/E 7/ b / / Date Approved By: / /3 Ddte V
Manager - Salem Generating Station (> M t,4 3 M / Approved By: . s . Date Manager - !=ergency Preparedness O O Page 4 of 4 Rev. 1
EP IV-105 l) EMERGENCY PROCEDURE EP IV-105 CONTROL POINT AND EQUIPMENT EVACUATION SCTION LEVEL i A. Evacuation of the Control Point should be considered based upon radiological conditions noted in EP IV-103. BESPOP.31BLE INDIVIDUAL I BACKSHIFTS AND WEEKENDS The predesignated individual on the Emergency Assignment Shift Schedule (normally the Shif t RPT) . DAY SHIFT (MONDAY - FRIDAY) The Senior Supervisor of Radiation Protection or his designee. This procedure shall be implemented by the Supervisors of Radiation Protection for Dosimetry and Operations. n 6
~~) \J LIMITS ON AlJTHORITY Unless life threatening situations exist, obtain the approval of the Senior Shift Supervisor /EDO prior to initiating the evacuation of the Control Point.~~
~~ACTION STATEMENTS IldE INITIAL~~
1. The Shift RPT or the Senior RP Supervisor on site shall contact the Senior Shift Supervisor /EDO and obtain permission to setup a new Control Point. Alternate locations include REP Room area, Turbine Build..., and Main Gate.

2. Upon receiving approval from the Senior Shif t Supervisor /EDO the Shif t RPT or the Senior RP Supervisor on-site shall contact the Control Point and request them to implement Control Point and Equipment Evacuation.
Ensure that the TSC is aware of the new location for controlling access. l I i i i i Page 1 of 4 Rev. 1
EP IV-105 O action sr4Terents <courr~ueo) ligE INITIAL
~~3. The Dosimetry Supervisor shall re-establish the department's function at a new location and evacuate the fcilowing items:~~
~~a) Counting Room equipmint b) Dosimeters, Dosimeter cards and TLD's from the control point c) TLD readers d) Spare TLD's~~
~~4. The In-Plant Operations Supervisor shall re-establish access control functions and evacuate the following pieces cf equipment.~~
~~a) Emergency L'g Books~~
~~\m I b) Portable Survey Equipment c1 Survey materials (air sample filters, etc.)~~
d) SCBA and spare tanks e) Respirators and canisters f) Protective clothing g) Posting materials and barricades i 5. Ensure that the evacuated area is properly posted and locked, if necessary. j k
~~6. All personnel and equipment evacuated from contaminated areas should be sur. eyed prior to release to uncontrolled areas.~~
~~, /\ 7. Re-establish the operability of the evacuated equipment as soon as possible. { 1 Page 2 of 4 Rev. 1~~
~~\ -_____-~ _ .-+- , - . % p g n -- ,~~
~~' EP IV-105 O acri m st^TE"E"Ts 'co"'i~uto) 11g1 INITIAL~~
8. Ensure the TSC is aware of the new location fcr your group.

9. Request the Senior Shift Supervisor /CDO to notify personnel by page of, the Control Point change.

10. Continue to me-itor radiation levels at the group's work location.
~~Keep track of personnel exposures. Rotate personnel as appropriate to ensure dose limits are not exceeded.~~
~~11. Ensure all pertinenc information is entered in log books. 4 a~~
I 12. If additional materials or services are required due to relocation, contact the Administrative Assistant. O [0MMUNICATIONSNETWORK CONTROL ROOM 2 SSS CONTROL POINT 1 MAIN GATE TSC CONTROL ROOM 1 641 635 611 500 200 633 Page Page 623 600 201 Page page Page . NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. DISCUSSION Evacuation of personnel and essential equipment may be required if the radiation levels at the Control Point get excessive. Recover vital equipment w' aever possible. The cost-benefit b>..s for equipment recovery vs. exposure shall be evaluated by the supervisor responsible for the equipment. Page 3 of 4 Rev. 1
l
~~. . . . . . IP Iv-105 O~~
~~Prepared By:~~
~~/O 2 /, /~~
~~Reviewed By: Dep1r ent ' ead / Date' Reviewed By: ( \ /O!db!b/~~
~~' Date si tant to Manager ,~~
~~Reviewed By: ~~~
~~f. Station Quality Assurance Engineer~~
~~/dM Date~~
~~{ SORC Meeting No.: b[~ l! /C[d7 /~~
~~! Date Approved By: / , /!/3!~~
Manager - Sale:sr Generating Station D&te Approved By: * *
~~>M M l 21 [V Manager - Emergency Preparedness Date O~~
1 O Page 4 of 4 Rev. 1
EP IV-106 n) (, EVERGENCY PROCEDUDE EP IV-106 ALARA TASK REVIEW AND EnERGENCY EXPOSURE AUTHORIZATION ACTION LEVEL
1. Activation of the Radiation Protection Emergency Organization.

2. As needed by any other Emergency Procedure.
~~BESP00 SIDLE INDIVIDUAL~~
~~1. ALARA and task reviews may be requested by any of the following individuals.~~
~~Senior Shift Supervisor EDO Senior Supervisor of Radiation Protection 4 OSC Coordinator Dose Assessment-ALARA Supervisor Chemistry Senior Supervisor i~~
~~/""s 2. The Dose Assessment-ALARA Supervisor nornally implements this procedure.~~
NY
-LIMITS ON AUTHORITY Final approval for emergency tasks with an expected man-rem greater tbsn 10 rem requires the approval of the Senior Supervisor of Radiation Protection and the Senior Shift Supervisor /EDO.
~~ACTION STATEMENTS I I1ME INITIAL~~
1. The initiating individual shall contact the Dose Assessment-ALARA Supervisor and inform him of task details. A copy of his evaluation guide is included as Attachment 1. Details on the task should be supplied by the requesting individual (e.g., Chemistry Supervisor, Operations Supervisor, etc.). A REP form should be completed and attached to the ALARA form.

2. The initiating individual shall inform the Dome Assessment-ALARA Supervisor of the relative priority of the task and by what time the review must be completed. Conflicts between different task priorities shall be resolved by the EDO.
Page 1 of 5 Rev. 1
EP IV-106 ACTION STATEFENTS (CONTINUED) ., M INITIAL
3. In the event of planned erergency worx which may involve individual I personnel exposures higher than 2.5 rem, the Senior Shift Supervisor or OSC Coordinator shall request an Emergency Exposure Authorization from the EDO. (See Table 1)

4. The EDO shall determine need and priority of work proposed and nctify the Senior Radiation Protection Management Representative.
~~' 5. The Senior Management Representative of Radiation Protection shall~~
~~utilize ALARA concepts and Table I, " Emergency Exposure Criteria", to establish radiation protection criteria for the proposed mission.~~
6. Upon completion of the ALARA Task Review, it shall be approved by the Senior Supervisor of Radiation Protection (or his designee) . If the i estimated exposure exceeds 10 man-rem, the task also requires the
~~() approval of the Senior Shif t Supervisor /EDO.~~
7. If the task fails to obtain the necessary approvals, notify the requesting individual. If conditions change that may affect the task's priority, the requestor may submit a new or revised review request. If the task receives the necessary approval, notify the requestor and arrange a meeting between the requestor and the ALARA review group if requestor requires either special instruction or training.
NOTE Although a standard REP form-may be used in an emergency situation,.a distinct numbering system shall be instituted. 1 ATTACHMENTS ALARA Task Review Gaide COMMUNICATIONS NETWORK , CONTROL ROOM 1 CONTROL ROOM 2 ()
~~\~)~~
S UPERVISOR (TSC) 201 SSS 635 633 641 200 i Page 2 of 5 Rev. 1
EP IV-106 NOTE Fc rward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. i DISCUSSION During or after an accident, radiation levels can be expected to increase significantly over rou*.ine operation levels. Positive controls shall be exercised prior to commencing with duties, which require ALARA task review, to protect personnel from the increased radition levels.
~~----------.=-. ------------.-=== -- --~~
~~__ ._ _=---=_ _ ----==_ _ - - - - - - - - - - - - -~~
/
~~Prepared By- _~~
/
~~Reviewed By: b De art: 27 nt ead~~
/C 2b I/ ' Date Reviewed By: ( / O!2 [., [
~~ta to Manager ' Date' I Reviewed By: r Station Quality Assurance Enginee.~~
~~/h!'2 "Date 7[f[l )~~
~~SORC Meeting No.: hf~f[! /O 27!b/~~
~~/ Date' I~~
~~Approved By:~~
~~Manager - Salem Generating Station~~
~~/!/3 /Date Approved By: .~~
~~Manager - Emergency PrepErEdness~~
~~#Av k l 'L/ A 'Date' l~~
i i I l 1 l i v Page 3 of 5 Rev. 1
l I EP IV-106 ATT. 1. i ATTACHMENT l' . ([]) EFERGENCY JOB EVALUATION GUIDE
~~' Ext.~~
l. Job requested by

2. What work is to be performed?

3. Why is job required?

4. When will job start?

5. When is completion required?

6. Expected duration of job Expected man-rem

7. Number of personnel required

8. Name and current exposure of individuals on job 4
~~i 1~~
~~9. Dose rate and contaminati.on levels to be encountered during job.~~
~~, DOSE RATES CONTAMINATICN A/s Gen. Area Piping i~~
~~! Valves j 10. Are there other jobs that can be done at the same time? (Explain) i 4~~
~~11. What alternatives are available.~~
s
~~12. Special instructions of limitations Approved Disapproved i~~
~~ALARA Supervisor . Senior Supervisor / Pad. Protection~~
/"
~~(>) i, EDO (for >10 man-re.m) r l l f Page 4 of 5 Rev. 1~~
~~. _ m _ - -~~
i i l l EP IV-106 i I TABLE I () TABLE 1 EMERGENCY WORKERS EXPOSURE CRITERIA WADNING CRITERIA ARE FOR RADIATION EXPOSURE TO VOLUNTEERS ONLY. Emergency Exposure Authorization required. Exposures are to be "once in a lifetime". Life-Saving Non-Life-Saving Authorized Exposure: 75 rems whole body Authorized Exposures 25 rems whole body Any and all actions necessary to save or Repair or operation of equipment necessary to preserve life, including but not limited mitigate a situation which has or may have the to: potential to cause projected off-site doses which would require protective action. Removal of injured p*rsonnel First Aid Corrective actions necessary to prevent plant Personnel decontamination safety status from further deteriorating or to f-% k/ Ambulance services effect significant improvement in plant safety Medical treatment status. Corrective actions necessary to cause significant reductions in in-plant radiological hazards. 4 I i L i l O Page 5 of 5 Rev. 1
EP IV-107 1 EMERGENCY PROCEDURE G is,/ EP IV-107 RADIATION MONITOR EVALUATION ACTION LEVEL 4 This procedure shall be used whenever evaluation of the in-plant monitors wili be perfer ed. FESPONSIELE INDIVIDUAL The Control Room Accident Assessment Liaison will be responsible for the implementation of this procedure when directed by either the Senior Shift Supervisor /EDO or. the Senior Supervisor of Radiation Protection on site. He/she will monitcr those instruments pertinent to his/her duties. LlHITS ON AUTHORITY
~~1. All data shall be reported to the Senior Shift Supervisor /EDO or Senior Radiaticn Protection i Representative on-site.~~
i
~~2. No information shall be released directly to any off-site agency unless specifically approved by the Senior Shift Supervisor /EDO.~~
A
~~+ 1 SCTION STATEFENTS %d 11ge IN!T!AL~~
1. Receive pertinent information from the requestor (Senior Shift Super-visor /EDO or Senior Supervisor of Radiation Protection) regarding operational changes or possible sources of radiation which may have
~~' caused significant changes in readings of radiation monitors.~~
2. Determine which monitor or location is to be evaluated.

3. Determine immediacy of evaluation and what interpretation is desired.

4. Request that you be informed of pertinent changes in plant conditions that may affect the response of monitors.
~
5. If the meter has failed, use the chart recorder to determine the past trends. Adjacent monitors may be used to provide indirect indications on nearby locations.

6. If definitive trends are present, extrapolate them based on time and l_ estimate radiation levels for stay time and man-rem estimates.
Page 1 of 13 Rev. 1
EP IV-107 (,) ACTION STATEMENTS (CCNTINUED) 1 11gE INfTfAL
~~7. If any of the monitors indicate extremely high radiation fields, ensure '~~
~~the In-Plant Supervisor for Radiation Protection is notified.~~
~~8. For evaluation of specific monitors, see the appropriate attachment to this procedure.~~
~~GTTACHMENTS~~
1. Accident Assessment Instrumentation

2. Dose Assessment from Containment Monitoring System CCM UNICATIONS NETWORK TSC CONTROL ROOM 1 CONTRCL ROCM 2 SSS CONTROL PCINT 200 633 641 635 611 201 642 g
623 x_) NOTE Forward all co=pleted forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. DISCUSSION Whenever possible the area radiation monitors should be used instead of relying on technicians to obtain dose rates. Results from the radi;. tion monitors may be used in any of the follcwing situations:
1. To track the relative c.oncentrations of liquid waste being transferred from one location to another.

2. To ensure individuals entering evacuated areas will not be exposed to excessive radiatien 1svels.

3. To estimate the concentrations in various plant systems or components.

4. To evaluate the integrity of the core and system components.
F)
~~5. To estimate source terms and potential releases of f-site.~~
Page 2 of 13 Rev. 1
EP IV-107 Prepared B : . Reviewed By: ~ [ 9 [ epar en+ ead ' Date' Reviewed By: [ sistant to Manager Date' Reviewed By: / 14A h
' Station Qua'11ty Assurance Engineer /h 47 Yl iDate' SORC Meeting No.: $/ - /// 10 /2 7 f$ / ~ Date' Approved By: ///3((v' Manager ' Sale 16 Generating Station <Date Approved By: . * [S[ !2( PV Manager - E:nergency Preparedness # Da t'e
~~( P O Page 3 of 13 Rev. 1~~
EP IV-107 ATT. 1 1 ATTACHMENT 1 INSTRUMENTATION FOR ACCIDENT ASSESSPENT PURPOSES CH ANNE LS AVAILABLE RANCE PL'PPCSE INSTRLTENT A. Oeophysical Instrumentation

1. Selsmegraph 1 0.02 to 1 g Provides Indication of ground accelera-tion. Excessive acceleration would require that an emergency be declared.
~~Alarms in Control Room at 0.02 g.~~
2. River Level 1 0 to 20 ft. Provides surveillance of the water level of the Delaware River. If the water level is approaching 11.5 ft. an ALEFT is issued.

3. Onsite Meteorology

a. Wind Speed 3 0 to 1C0 mph The radiation dose received is inversely proportional to the wind speed. Wind speed data is used to determine when a plume would arrive at a specific location.
~~Wind speed is measured at three elevations.~~
b. Wind 3 0 to 540* In order to determine which sectors must Direction be monitored. Indication of the wind f<m \ direction is necessary. Wind directicn (d
is measured at three elevations. Lapse Rate 2 -10 to +10' Accident assessment requires that the c. C'/m dispersion of the plume be estimated. The lapse rate provides a universally acceptable method for indicating the dispersion characteristics of the
~~' atmosphere.~~
4. Offsite Meteorology

a. Wind Speed 1 0 to 100 mph These channels are used for assessment purposes. In the event that the onsite

b. Wind 1 0* - 360' meteorological wind speed and direction Direction indication is not functioning, this
' information is available from the nearest National Octanographic Atmospheric Administration (NOAA) weather station which 14 located at Wilmington Airport. PSti; has determined that the NOAA weather station data correlates favorably with its onsite weather tower. Weather forecasting is available at this location. 3 s. Page 4 of 13 Rev. 1 l
EP IV-107 ATT. 1 () INSTPUME!:T CHANNELS
~~,AVAILA3tE RANCE PUPPCSE B. Radiological In*trumentation~~
~~1. Area Monitors This channel indicates emergency measures.~~
~~4 It is available for accident assess ent~~
a. Channel 1 0 to 10 R/hr under all conditions. High radiaticn in R21 US. i t 1 this channel indicates the pcssibility cf 7
~~0 to 10 R/hr a LOCA. Monitor of this channel will aid Unit 2 in determining the severity of any accident. 4~~
b. Channels 2 0 to 10 mR/hr These channels can initiate emergency R5 and R9 measures. High radiation in this channel indicates that a fuel handling accident may have occurred. An alarm in this channel if confirmed, may lead to sn emergency being declared.

c. Additional Area Monitored for Radio-activity 4

1) Contain- 1 0 to 10 mR/hr During an accident, an operator would ment R2 need to have as much information on radiation levels through the plant as 4

2) Charging 1 0 to 10 mR/hr possible. Information supplied by 4
~~these channels will dictate much of his~~
3) Waste 1 0 to 10 mR/hr actions. For exan ple, if high alarms Load Out are noted on channels near the radio-O R8

4) Sampling 1 4
~~0 to 10 mR/hr chemistry counting lab, then Health Physics personnel will advise that samples must be counted in an alternate Room R6A location.~~
~~5) Radio- 1 0 to 10 mR/hr chemistry Lab R3 4~~
~~61 Control 1 0 to 10 mR/hr Room RlA~~
2. Process Radiation Monitors

a. Containment

1) Channel 1 0 to 106 cpm These channels can initiate emergency RllA measures. Under certain conditions they (Particulates) may be used for accident assessment.
~~High radiation in these channels indicate~~
2) Channel 'l 0 to 10 cpm 6 that excessive reactor coolant leakage could be occurring. In the event of a R12A (Noble Gas) LOCA with high temperature and pressure, those channels will isolate themselves

3) Channel 1 0 to 106 cpm from containment in accordance with the R12B General Design Criteria principles.
(Iodines) These channels can only be used to monitor containment if the temperature and pressures are not excessive to the point of damaging the detectors. O Page 5 of 13 Rev. 1
f EP IV-107 ATT. 1 i CHANNELS g/ INS"."RUMENT AVAILABLE RANCE PUPPOSE
b. Plant Vent

1) 2P41A 1 0 to 106 cpm These channels can indicate emergency .
(Particulates) measures. They are used for accident assessment. High radiation in these 21 2R41C 1 0 to 106 cpm channels indicate that a release of radia-(Noble Gas) sion is occurring through the plant vent. These channels operate continuously and
3) 2R41B 1 0 to 106 c; are used as tt.: basis for dose calcula-(Iodines) tions. PSE&G is modifying its plant vent' monitoring system to comply with the recommendations and time tables of N" FIG 0737.
4
c. Channel R43 1 0 to 10 mr/hr This channel is located outside the plant near the station vent. If inplans instrumentation should go off scale, this channel will monitor radiation levels in the environment attributable to the release. This channel complies with the USNRC interim quidance for high range RMS and is used for ms;essment purposes.

d. Channel R18 1 0 to 100 epm The liquid radwaste system isolates on high activity. This channel is mainly used for assessment in assuring that no unplanned liquid discharges are being made.

e. Channel R31 1 0 to 106 cpm This channel is mainly used for assess-ment. It monitors activity level in reactor coolant. Confirmed high activity
~~(~') x_/ in reactor coolant is indicative of failed fuel. Confirmed high levels in the coolant can also initiate emergency measures.~~
f. Channel R15 1 0 to 106 cpm Cendenser air ejector monitor. This channel would be used to indicate primary to secondary leakage. This channel is important in indicating steam generator tube leaks.

g. Addit $onal These channels are used by the operator Processes to determine if radioactivity has spread 13nitored into other systems or components. As an for Radio- example, high channel R19 readings in activity one steam generator is ind eative of a lea through the tute bundle.
6
1) Condenser 1 0 to 10 ep, E;ector R15 6

2) Steam 1 4 to 10 ep, Generator Blowdown R19 6

3) Component 1 2 to 10 ep, Cooling Water R17

4) Containment 1 5 to 106 cpm ran Coil Cooling
~~() f %. Water R13~~
~~5) Waste Gas 1 1 to 10 6~~
ep, Effluent 1R14 f Page 6 of 13 Rev. 1 L - -
a l 1 1 EP IV-107 ATT. 1 m (,,e) I CHANNELS INSTRUMENT AVAILABLE RANCE PURPOSE
~~3. Portable Monitors and~~
~~Samplers~~
~~a. Special 1 N/A During an accident, reacter coolant Reactor activity could rise appreciably.~~
Coolant Sampling of the reactor coolant can nct Sampling be performed using the conventlenal System , sampling technique. PSE&G has designed a special reactor coolant sampling system which is s!ielded. Depending on the radiation levels an ALERT, SITE or GENERAL emergency would be issued if not already declared.
b. Special 1 N/A PSE6G has designed a s:ecial containment Containment gas sampling system which would te Gas Sampling capable of delivering a representative sample of containment. Depending on the radiatics levels, an ALERT, SITE or GENERAL emergency would be issued if nct already declared.

c. Plant Vent 1 N/A The plant vent is the final release point Air Sampler of the SNGS. Accident assessment requires that information on the activity discharged through the vent be known.

d. Survey See Tables varies Survey instruments are used inside the Instrument IX-1 to plant to assist the operater in deter-
/~') IX-6 mining the radiation hazards of a \ ,,/ particular area. They are also used out of plant in carrying out the Plan. During an accident survey will be performed at the site boundary. If radiation levels exceed 50 mR/hr at the site boundary a Site Emergency is declared.
~~4. Process Monitors~~
~~, a. Containment~~
1) Pressure 4 -5 to +55 psig The operator uses prassure information to determine if leakage is occurring inside containment. He also uses pressure indication to insure that a negative pressure is being maintained inside containment. An Unusual Event is declared if pressure inside the ccntain-ment is above 4.0 psig.

2) Spray 1 N/A The status of the containment spray System system is important to the operator in
~~hat it tells hin or her that depressuri-zation and cooling is required for the containment. Its automatte actuation signifies an emergency in progress.~~
~3) Phase "A" 5,1 Cpen or Close The status of each valve which penetrates Isolation containment is important to the cperator Valves in order to insure that the content of containment remains confined.
O x/ 4) Purge anu 6 Open or Close Pressure Relief Valves Page ? of 13 Rev. 1
EP IV-107 ATT. 1 () INSTRt MENT _ CHANNELS AVAILABLE RANOE PUPPOSE
b. Peactor Use in assessing the magnitude of any Coolant leakage of reactor coolant inside centain-ment.

1) Leak Rate 6
a) Padiation 1 0 to 10 cp= Channel RllA 6 b) Radiation 1 0 to 10 cp, Channel R12A c) Contain- 1 N/A ment Sump Levei d) Fan Coil 5 N/A Condensate
2) Thermodynamics Reactor coolant pressure indication is used for assessment purposes. It insures a) Tempera- 4 30* to 700*F the integrity of the Reactor Coolant ture System from over pressurization.
b) Pressure 2 0 to 3000 psig Tamperature indication is used fer assess-(Wide ment purposes. An over temperature delta Range) T monitor provides indication if a departure from nucleate boiling has occurred which could result in partial O fuel melting. The over temperature delta T monitor initiates emergency measures through a reactor trip.
3) Borated Boron level, concentration and tempera-Water ture information is required in crder fcr Sources the operator to respond to an accident which requires the use of the reacter a) Level 2 0 to 100% safeguards systems.
~~b) Concen- N/A N/A tration c) Tempera- 50 to 250*F ture~~
4) Chemistry N/A N/A Use in accident assessment to determine Sampling quantity of key chemicals.

c. Subcooling 1 0 - 120'T Indicates inadequate core cooling.
~~Meter (T. Operator is alerted if P-P set <200 psi 0-16.-T) 00 psi or if T sat~~
~~-T <50'F.~~
~~(P-Psat) ,~~
d. Pressurizer Entire distance The pressurizer water level is monitored between taps by the operator during an accident. High

1) water Level 2 475 in of H 2 O water level initiates a reactor trip to 1700-2500 psi prevent fluid loss through the

2) Pressure pressurizer relief valves. The pressurizer pressure initiates emergency measures through a reactor trip on either excessively low pressure or excessively high pressure. Those instruments are also used in accident assessment.
Rev. 1 Page 8 of 13
EP IV-107 ATT 1 0 INSTRUMENT
~~--S AVAILABLE RANCE PURPOSE~~
e. Main Steam

1) water 4 0 to 120 (1) Detects steam generator tube rupture Level monitors water level following a stear in Steam line break useful in assessnent whett.e:
~~Generator a steam line rupture has occurred. 21 Pressure 3 0 to 1200 psig~~
~~f. Reactor Emergency measures are initiated on intermediate and source range nigh~~
~~-11~~
1) Neutron 4 10,3 amps to neutron fluxes. Neutron flux can be used (Source 10 amps by the operator for assessment purposes and to insure that the reactor maintains Inter- itself suberitical after an accident.
~~mediate Range)~~
2) Neutron 4 -1 to +5 Neutron flux rate meters initiate reactor Flux decade / min protection through a reactor trip. It Rate provides protection against rod ejecticn accidents at all power levels.

5. Fire Detectors Multiple N/A Alerts operator of a fire or the spread (in of a fire.
accordance with Table 3.3-10 of Technical Specifi-cations) O FOOTNOTES (1) The containment menitors for Unit 1 can be switched to monitor the plant vent. (2) Three of the four steam generators water level channels are narrow range devices with a
~~+7 to -2 feet range.~~
f O Page 9 of 13 Rev. 1
EP IV-107 ( ATT. 2 ATTACHP.ENT 2 ())) DOSE ASSESSMENT FROM CONTAINPENT RADIATION PONITORING SYSTEP l i The response of R21 as a function of dispersion factor to yield dose of I rem whole body dose l j in 24 hours have been developed and are shown in Figure 1 and 2. These curves are based or.
~~! containment design leak rate.~~
~~Procedure~~
1. Obtain Xu/O from Table I using the appropriate distances and stability class.

2. Determine X/Q by the formula:
~~XE/O~~
~~!O " (Wind Speed in mph) X 0.45~~
3. Obtain R21 response (Unit 1 or Unit 2) and enter Figure 1 or 2 as appropriate to obtain base X/Q value.

4. Determine dose at X/O obtained in Step 2 by the formula:
0 Step 2) Dose (rems) = X/O (Step 3) , O i j lO I Page 10 of 13 Rev. 1 1
EP IV-107 FIG. 1 O FIGURE 1 SJt.'h. .W. D* w sY*e 'd.' a'l. m,____._ . _ . . ,_,
~~'w...._.......~~
t
~~, .. .. ~. .. .. .. .. ... .. .. .. ..... .- .. .. ._. . . . _ . . . . . . . . .~~
a
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~~__ . . : =- 1 == :--s : t- p--- 6 .~~
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~~! (~~
~~3 k:~N1 !.! -IE9:*d . :.:.if J~4 4iJ.l'l'** 4 irj d:..gacj : .d . I i~~
,j j l - - - _ = - - - : : :.; .s . "-li,i e- - I.. . l -- ; jf.,.$ .> ---==.---.:_x:..---=a-- - - .
8
- .I .k 'I t. . . . . 'l Existis, hist range contai= ment monitor ~j i.; i : : .:l 1 has an upper limit of 1,,I 10 4 R/IR. , l l l ll l. l , .m Implacase== with 1 I 10' R/YR capability . = __ ,---- - - will be com:pleted i= t.he nea: futura. .
f '~ Until the monit=r upgrade is complete ' ' ' ' ' ' 750 R/ER wi1*. be used as one of tae d - r ' d zii- .:i=! : - jti = -=::6-i three prvcale:.:. lated act.isa levels i .
+
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4
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t, , . . . . , . . . , , , . . . . . , . . 2:sFERs::N m A I/C ( sec / mI) 1 Off site dose of 1. re:n in 24 hours following a LOCA as detar-
~~nined by R21 response and dispersion factor.~~
~~. Page 11 of 13 Rev. 1 j~~
~~EP IV-107 FIG. 2 O FIGURE 2 SALEF. UM*~' 2 197~~
~~= , . _ . . . _ . . . . . _ . . . . _ . _ _ .~~
8
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s
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0
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a *
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~ : 'l -[-l il I l l l l l !!i!!"N:l l-llllll I h III .
[ i t i it I lit ! I i 4 t I l f 18 l i.._..._._._:i.,- f I h 5 ==h I I 7i I i l I *! il ii l dl ~I' I l l I I l I i b!
~ , ..q 7 ,:.19 I I ! I T di"i~i"-i FF i-l 1 F l I ! . . . - _ . . ._..!.. .._U.,
~~a . . .. . .! . 3. . _ . . . .~~
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. . . . . ~ .%.. . . .l i t 6 6
1e*5 :o*' 10-1 Ic~* 3:37ERS: N MR Z/C ( sed / m3) - __ .. _. . _ offsite dose of' 1 re::t in 24 hours following a LOCA as deter =ined by R21 response and dispersion factor. O l Page 12 of 13 Rev. 1 l - 1
EP IV-107 TABLE 1 1 TABLE 1 Xy/Q 10
~~-6 g,-2)~~
DISTANCE - 8 (METEPS) STABLE NEUTRAL UMSTABLF 500 179.6 148.0 46.8 1000 244.8 61.39 15.00 11.00 s (MEA) 1270 224.8 46.8 1500 207.9 34.41 7.58 2000 168.0 22.49 4.64 2500 136.8 16.08 3.17 3000 113.3 12.20 2.32 3500 95.4 9.64 1.78 4000 81.7 7.86 1.42 4500 70.9 6.56 1.16 5000 62.3 5.58 .968 5500 55.3 4.82 .822 (Nearest Resident) 6000 49.5 4.21 .708 6500 44.6 3.72 .617 A 3.32 .543 ( _) 7000 40.5 i 7500 37.0 2.98 .482 8000 34.0 2.70 .432 8500 31.3 2.46 .389 9000 29.0 2.25 .353 9500 27.0 2.07 .321 10000 25.2 1,91 .294 10500 23.6 1.77 .271 11000 22.1 1.65 .250 11500 20.8 1.54 .231 12000 19.6 1.44 .215 12500 18.6 1.35 .200
. 13000 17.6 1.27 .187 13500 16.7 1.20 .176 14000 15.9 1.13 .165 14500 15.1 1.07 .155 15000 14.4 1.02 .146 ,
15500 13.e .971 .138 16000 13.2 .952 .131 1600 METERS = 1 MILE Page 13 of 13 Rev. 1
EP IV-108 r' EMERGENCY PROCEDURE l ') EP IV-108 PROTECTIVE ACTION RECOM?ENDATIONS ACTION LEVEL Declaration of an emergency at the Alert level or higher. FESPONSIELE INDIVIDUAL The Radiological Emergency Manager (REM) has overall responsibility for this procedure. Until the REM is operational at the EOF, the requirements of this procedure may be met by the Shift Radiation Protection Technician or the Dose Assessment /ALARA Supervisor under the direction of the Radiation Protection Engineer. NOTE Only the individual with the emergency coordinator function may make the decisien to netify state and local authorities of off-site Protective Action Recommendations. ACTION STATEMENTS O NJ Ildi INITIAL
1. The Senicr Shift Supervisor /EDO, upon determination that a radiologital incident is in progress, shall contact the Shift Radiation Protection Technician or the Dese Assessment /ALARA Supervisor to initiate dose assessment.

2. Dose assessments shall be calculated based on data supplied by the plant effluent monitors. This calculation shall be performed by the Shif t Radiation Protection Technician in the TSC and by the REM in the ECT,

3. The dose rates or projected doses shall be compared to the Protective Action Recommendations (Attachment 1) and the Evacuation Time Estimates for areas near the site (Attachment 3).

4. The REM or the Dose Assessment /ALARA Supervisor shall provide the
'N Senior Shift Supervisor /EDO with Protective Action Recommendations prior to activation of the EOT. The REM shall report to the Emergency Response Manager when the ERM arrives.
l Rey, 1 Page 1 of 17 l
EP IV-108 ATTACHSITS
1. Off-Site Protective Action Recorsnendations Fe- The Public

2. Emergency Worker Exposure Criteria

3. Evacuation Time Estimates NOTE ,
Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. ___- --- -_=___=-_------- -- __ . _ ____= _ _ _ _ _ _ - _ - - - - - = _ _ - _ = - - _____________ f Prepared B' -
~~/' 9 .~~
Reviewed By: [. / O 2 6!b / De ar* en Head ' Dater Reviewed By: ,_ tabt to Manager
~~/Of26/[r/~~
Date Reviewed By: s tdh V Station Quality assurance 7 2neer ((-77f[l iDate SORC Meeting No.: b/ - / / / /O/Date!27 b/ Approved By: # /!/ Manager - Saleaf Genef ating Station / Dat'e Approved By: .
~~- A h Lal00o Manager - Emergency PreparedKess I~~
~~21 fS~~
~~' Date O~~
l Page 2 of 17 Rev. 1
EP IV-108 ATT. 1 ATTACWENT I Q' 0FF-SITE PROTECTIVE ACTION REC 0E ENDATIONS FOR THE PlJELIC PROJECTED PROJECTED CHILD?IN &
~~, y WCMEN CT DOSE RATE~~
DCSE DOSE RATE DOSE WHOLE B00Y THYROID THYROID CHILL-3EAEINO WHOLE BODY ACE (rem) ADULTS (rem /hr) (REM) (rem /hr)
~~<0.5 <0.75 <3 None None l <0.125 0.5 - 1 0.75 - 1.25 3-5 Shelter Sheiter 0.125 - 0.25 3~~
~~1-5 1.25 - 6.25 5 - 25 Shelter Evacuate 0.25 - 1.25 3 3~~
~~>5 >6.25 >25 Evacuate Evacuate >l.25~~
1. Use dose rate only if the duration of the release cannot be predicted (dosa rates are based on a 4 hour integrated dose - 2 hour response time + 2 hour minimum evacuation time).

2. No protective action is recuired, however. states may issue an adviserv to seek shelter and await further instructions.

3. Recom: endation to evacuate must also be based on environmental (weather, etc.) and other effecting conditions.
NOTE This table appears in EP I-12. Any revisions to this procedure should also revise the appropriate table in EP I-12. i O l l Page 3 of 17 Rev. 1
i l EP IV-108 ATT. 2 O b/ ATTACHMENT 2 EMERGENCY WORKERS EXPOSURE CRITERIA WADNING CRITERIA ARE FOR RADIATION EXPOSURE TO VOLUNTEEDS ONLY. EMERGENCY EXPOSURE AUTHORIZATION REQUIRED. EXPOSURES ARE TO BE "0NCE IN A LIFETIME". LIFE-SAVINO NON-LIFE-SAVISO Authorized Exposure: 75 rems whole body Authorized Exposure: 25 rems whole body Any and all actions necessary to save or Repair or operation of equipment precertc life, including but not limited necessary to mitigate a situation which to: has or may have the potential to cause projected off-site doses which would Removal of injured personnel require protective action. . First Aid Corrective actions necessary to prevent Personnel decentamination plant safety status from further
~~/) '2 Artulance services deteriorating or to effect significant Medical treatment i=provement in plant safety status.~~
Corrective actions necessary to cause significant reductions in in-plant radic-logical hazards. 4 4 Page 4 of 17 Rev. 1
! EP IV-lC8 i ATT. 3 j Q ATTACHMENT 3 l 4 1 ) 1-4 i 4 i O 4 i l ) i i LVACUATION TIME ESTIMATES for Areas Near the Site of SALEM AND HOPE CREEK _ NUCLEAR GENERATliiG SisiiG;C prepared for PUBLIC SERVICE ELECTRIC & GAS COMPANY prepared by f PARSONS BRINCKERHOFF QUADE & DOUGLAS, INC. February 27, 1981 Page 5 of 17 Rev. 1
~~. _ _ _ _ _ _ . _ - . . . _ _ . . . , , _ _ _ - . . , _ . . ~ . _ , _ _ . _ . . _ _ _ , . . _ , . _ _ . , . _ .- , , _ . ~ . - . _ , _ _ _ _ _ _ - , _ , _ _ _ _ -~~
~~EP IV-108 ATT. 3 i O 1~~
< 's ' s 7 I \ / ! U, // "4 s' ,
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.; f j / "p. :.' . .db F . N ,\ \
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/
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'~
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# $--=s ' . ~ e- . - , ' 4( f:b.x%-\lN / /: . '^
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' I' .h....l,I ~ . . -- )_ ,L \i- *'/l m _,!?,
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p a , i s i u /. j - r:L-
~~s. =g' E~~ / d9, A==- x ;~~
# b ~ W'k M i ,t i YW,_hd -hW s
~~fN.~~
,. b/ ptf $ 5 ./ ;sE ? .: ;. - - %s = %- .. C s& t.
~~r;A", r .~~
% 1 '% s s .r.. . . ===" -> , #i O - / \ . y. ... . .M 9.. ". . .. .gjf .. . 25-Y' </
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~~O rieure 2 rim =e tx>o u=e rme=se"cv > Page 6 of 17 Rev. 1~~
~~.. - .- . . ~ ~ .. - . _ . - - - . . . - - - . . ~ . _ - - - - - . . . _ - . . - . - . . . ,- . - . .~~
4 i EP IV-108 A*T, 3 i ' TABLE 1 RELATIONSHIP BETWEEN EVACUATION SECTIONS AND EVACUATION PLANNINO AREAS . 4 i EVACUATION SECTIONS EVACUATION PLANNING AP_EAS A 1
~~B 1, 3, 15, 17 c 1, 2, 3~~
+ I l D 1, 3, 4, 5, 15, 17, 19 E 1, 2, 3, 5,6,7 4 F 15 J i ^ G 8, 9, 15, 16 H 9, 10, 15, 17 i I 8, 9,.12, 13, 15, 16, 18 t J 9, 10, 11, 12, 14, 15 K 1, 15 s' 1, 2, 3, 8, 9, 10, 15, 16, 17 l L
~~y, 1 through 19 l~~
1 1 1 i i i i i I I a {
\
~~l ? 1, f 1 1 !O i i 1 Page 7 of 17 Rev. 1~~
~~- - . - , - - . . -. . .,. - . , _- . - . ~ . - - - , , , , , , - - - . . . , - . . . , . , .~~
~~EP IV-108 ATT. 3~~
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~~' Planning Areas Evacuation Time Esiimates 90 Section A l Salem Generating Stations Hope Creek Generating Stations O~~
~~Page 8 of 17 Rev. 1~~
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90 Section C Salem Generating Stations Hope Creek Genere. ting Stations O l Page 9 of 17 Rev. 1
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Figure 7 Evacuation Time Estimates Planning Areas 90 Section E Salem Generating Stations Hope Creek Generating Stations O Page 10 of 17 Rev. 1
EP IV-108 . ATT. -
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~~Figure 9' Evacuation Time Estimates Plan'ning Areas 90 Section G Salem Generating Stations~~
~~' Hope Creek Generating Stations Page 11 of 17 Rev. 1~~
~~. EP IV-108 ATT. 3 ~#~~
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Planning Areas Evacuation Time Estimates 90 Section 1 i i Salem Generating Stations Hope Creek Generating Stations Page 12 of 17 Rev. 1
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O Page 13 of 17 Rev. 1
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5 EP IV-108 ATT. 3 TABLE 7 NOTIFICATION AND CONFIPF.ATION TIMES _ i EVACUATION TIME REQUIRED NOTIFICATION CONTIPy.ATION j SECTION A 5 mins. 5 mins. B 1 hr. 45 mins. I hr. C 1 hr. 45 mins. I hr. D 1 hr. 45 mins. I hr. E 1 hr. 45 mins. I hr. 30 mins. F 2 hrs. 2 hrs. G 2 hrs.-4 hrs. 4 hrs.-6 hrs. 4 H 2 hrs.-4 hrs. 4 hrs.-6 hrs. a' I 2 hrs.-4 hrs. 4 hrs.-6 hrs. i 1 i J 2 hrs.-4 hrs. 4 hrs.-6 hrs. K 2 hrs. 2 hrs. 4 J 4 hrs.-6 hrs. L 2 hrs.-4 hrs. l M 2 hrs.-4 hrs. 4 hrs.-6 hrs. O C J i ] y { r 4 l
)
i ia 4 3 4 i i i i 4 1 i i ? I 4 I Rev. 1-Page 15 of 17
O O O TABLE 8 SALI:M/IlOPE CREEK NUCLEAR GENERATING STATIONS
~~EVACUATION TIME ESTIMATES (NIGIIT SCENARIO)~~
~~TOTAL EVACUATION TIME~~
~~' TRAVEL TIME FOR SPECIAL FACILITIES ( '( '~~
EVACUATION NOTIFICATION TIME ;ENERAI. POPUIATION FOR GENERAL POrtilATION WITilOUT AllTO IITtH AUTO WITilOUT AUTO $UllOOL OTill:RS SECTION HOURS : MINUTES WIrit AllTO A 305 :20 - :45 1:45 335 - 2:40 - - 2:45 B 1:45 335 1:35 2:40 3:40 - - C 335 1:50 2:40 3:55 - 2:45 D 1:45 3:05 4: 10 5:10 - - 1:25 E 1:45
~~- - - - 2:05 F 2:00 -~~
~~m 2:40-4:40 - 2:20~~
~~'2:00-4:00 M G :20 e~~
~~25 2:15 2:45-4:45 4:35-6:35 -~~
2:20 g 11 2:00-4:00 3:30 i 0 2:00-4:00 350 2:25 3:10-5:10 4:45-6:45 - 1 45 2:55 3:05-5:05 5:15-7:15 - 2:05 U J 2:00-4:00 20 - 2:40 - - 2:05 K 2:00 35 2:15 2:55-4:55 4:35-6:35 - 2:20 L 2:00-4:00 3:05 4:10 5:25-7:25 6:30-8:30 - 3:30 M 2:00-4:00 3:05 4:10 5:25-7:25 6:30-8:30 - 3:30 Site Emergency 2:00-4:00 (1) Includes additional notification time after reccipt of initial notification by utility. After July 1, 1981, this time will be reduced to 45 minutes except for Section A by the installation of a new warninq system. (2) Includes general population mobilization time of 20 minutes. (3) Includes dispatch time, loading time, and roadway travel time where applicable. yg
~~,I (4) Special Facilities in Sections H, D, F, C, 11 , .T include Delaware Hiver and Delaware Isay. For special f acilit ies other *y ,~~
~~ue than the river and the bay, it is assumed that notification will occur within 15 minutes and that mohllization and 5~~
$ evacuation will begin immediately thereafter. * ? ~
?
O (JD (\_] TAD t,C 10 SALEM / HOPE CREEK NUCLEAR GENERATING STATIONS EVACUATION TIME ESTIMATP.S ( ADVERSE WEAT!!ER CONDITIONS) TOTAI, EVACUATION TIME II TRAVEL TIME FOR SPECI AL FACII,ITIES NOTIFICATION TIME
~~' GENERAL, POPULATION FOR GENERAI,POPUf.ATION SCHOOL OTilflii$~~
EVACUATION WITH AUTO WITilOUT AUTO llOURS - MINUTES WITli AUTO WITHOUT AUTO SECTION 3:30 - 4:15 A 305
~~- 330 2:20 ,~~
3:40 - 6:05 8 1:45 6:05 5:55 30 - 1:45 3:40 3:30 C 5:05 1:40 2:45 3:55 2:40 6:20 D 1:45 8:45 10:05 7:15 5:05 1:45 6:20 7:40 E
- - 2:05 F 2:00 - - 2:20 20 - 3:00-5:00 G 2:00-4:00 3:05-5:05 4:55-6:55 - 2:20 U 11 2:00-4:00 :25 2:15 2:50 4:25 o 2:55 4:30 5:35-7:35 7:10-9:10
"' I 2:00-4:00 5:10-7:10 7:05-9:05 2:55 2:05 2:30 4:25 J 2:00-4:00 6:10 - - 2:05 K 2:00 3:30 - 6:20-8:20 6:10-8:10 330 2:20 3:40 3:30 L 2:00-4:00 10:20-12:20 7:15 5:05 7:40 9:00-11:00 M - 2:00-4:00 6:20 10:20-12:20 7:15 5:05 6:20 7:40 9:00-11:00 Site Emergency 2:00-4:00
)
initial notification by utility. After July 1, 1981, this time (1) Includes additional notification time after receipt offor Section A by the installation of a new warning system. l will be reduced to 45 minutes except (2) Includes general population mobilization time of 20 minutes. 3, s.: (3) Includes dispatch time, loading time, and roadway travel time where applicable. For special facilities other d"
.H (4) Special Facilities in Sections D, D, F, C, H, J include Delaware River and Delaware Day. d than the river and the bay, it is annumed that. notification will occur wit hin 15 minutes an.1 that nw>bil i 7at ion and .x, t evacuation will begin inunaliately thereaf ter. .
{
EP IV-109 EFERGENCY PROCEDURE I~)
% EP IV-109 PLUP.E TRACKING BY HELICOPTED ACTION LEVEL This procedure shall be implemented whenever the plume path is to be tracked with a heliceptei survey party prior to activation of the EOF. ,
NOTE Not to be Dmplemented at night, in poor visibility conditions or in inclement weather. RESPONSIELE INDIVIDUAL This procedure may be initiated by either the Senior Shift Supervisor /EDO or the Senior Super-visor of Radiation Protection. The Shift Radiation Protection Technician (RPT) is responsible for plume tracking p r ior to activation of the ECF. LIMITS ON AUTHORITY The Radiation Emergency Manager shall assume responsibility for plume tracking when the EC: assumes command. ACTION STATEMENTS 1 Il5E INfTfAL
~~1. The Senior Shift Supervisor /EDO or the Senior Supervisor-Radiation Protection on-site shall:~~
a) Request a helicopter from Philadelphia Electric Load Dispatcher. b) Contact the Shif t RPT in the Technical Support Center (TSC) . Request him to implement the clun 3 tracking procedure. O Page 1 of 3 Rev. 1
1 EP IV-109 O sc'io" state r"'s (co~'i~ue=> M INfffAL i 1
~~2. The Shift RPT shall:~~
a) Obtain meteorological data on the the following, and update hourly: e Wind Direction (from) : i AT HRS AT HRS (Add +180* to Control Room reading to determine ! " wind toward") Speed: AT HRS AT HRS a t*t (El. 300 f t) : AT HRS HRS HRS b) Plot isopleths from release point on radial projection map. Update as necessary, i l c) Detemine release rates and provide information to Dose Assessment / AI. ARA Supervisor. d) Plot the leading edge of the plume based on wind speed.
3. The Shift RPT shall relay plume isopleth and suggested tracking vectors to helicopter.

4. Do not request that the monitoring teams enter fields greater than 100 mrem /hr without notification of the Senior Supervisor-Radiation Protection.

5. If possible, the Senior Shift Supervisor /EDO should be aware of i releases from the plant before the helicopter is expected to encounter them. Also keep the helicopter infomed of any changes in the wind direction.
Page 2 of 3 Rev. 1
EP IV-109 ] ;CTIO!! STATEPB4TS (CONTINUED) M INfTfAL
~~6. The Shift RPT shall relay all data to the Dose Ateessment/ALARA Supervisor for plotting and analysis.~~
~~NOTE Forward all completed forms to the Assistant to Manager (SCS) . Attach any referenced completed EP's or attachments. Prepared~~
/
~~I t-j~~
^
~~Reviewed By:~~
~~" / [~~
~~Dttp rt/Dnt H ad 7 Date Reviewed By: 2~~
~~- d As '~~
tant to Manager 'Date Reviewed By: - Jla C m [O 7 k 3tation Quality Kssurance Engineer (Date6 SORC Meeting No.: bI ~ lI I / 0!27 !bl
~~/Date Approved By:~~
~~Manager - Salenf Generating Station O! ITat e Approved By: * * (.4 o pp Manager - Emergency Preparedness I 2./ ! M~~
~~'Date )~~
~~( Page 3 of 3 Rev. 1~~
~~. - . _ - _ _ - _. - _ . . ~ . . . . _ - -. .. . _ - - - - . .- -~~
EP IV-110 () EMEPGENCY PROCEDURE EP IV-110 FIELD MONITORING j r i ACTION LEVEL T When requested by the Senior Shift Supervisor /EDO. , l EESPONSIELE INDIVIDUAL ,4 4 2 A. Radiation Protection Technician , LIMITS OF AUTHORITY
~~1. Exposure in excess of 10CTR20.101 shall be approved in accordance with EP IV-106.~~
~~; 2. Re-entry into areas with suspected dose rates >100 mR/hr shall be approved by the Senior l Shift Supervisor /EDO.~~
t
~~3. Change-out of the air samples or TLD's in the environmental stations requires the approval of the Radiation Protection Engineer and Maplewood Lab.~~
~~O 4. Issuance of KI solution requires the approval of the Senior Shift Supervisor /EDC. I GCTION STATErENTS s 1131 INITIAL~~
~~1. Upcn the request to initiate an Emergency Radiation Survey record the following informations a) Wind Direction (towards)~~
(from) I b) Areas or locations to be surveyed: l l l l Page 1 of 36 Rev. 1
f EP IV-110 1 Act'ot' s'A'vi's (co"'i~uto) O M INITIAL c) Plant conditions that may affect the safety of the survey team er the tJrvey results. d) Enter team composition on Figure 1, " Emergency Team Assignments".
2. Provide the TSC with the names of the team members assembled at the Centrol Point.

3. Log each team member's name, badge number, dosimeter number, and dosimeter reading on the Dosimeter Log (re-zero dosimeters if necessary) .
~~Record the d, ose, time, and date on each Dosimeter Card. Any subsequent j dosimeter resets should be recorded on the Desimeter Card and Desimeter Log. l~~
4. Field Survey Team (s) should initiate a 360* sweep of the local site area. Field surveys should include the adjacent 22-1/2* sectors (centered on the indicated downwind sector) and expand to the next two continuous sectors (5 secters total). If the primary meteoroleyical i
metering system is unavailable and back-up meteorological data from Wilmington Airport or another source is being utilized, Tield Survey Teams should expand their search area. The search should include an area of 180* centered on the indicated wind direction. Several distances should be searched. i
~~5. Quickly brief the team leader on the incident and provide him/her with the following information from Step 1.~~
I a) Wind direction from (meter reading +180* = direction toward) () b) Areas or locations to be surveyed c) Plant conditions that may affect the safety of the survey team or l the survey results l Page 2 of 36 Rev. 1 l
i
~~' EP IV-110 $CTION STATE'ENTS (ccNTINUED)~~
~~IL".E INfTIAL l~~
~~6. If it is suspected that the survey team will be exposed to significant quantities of Radio-Iodine, see Procedure EP I-15 for use of Stable Iodine.~~
~~I NOTE 1 Approval of the Senior Shift Supervisor /EDO must be obtained prior to distribution of Potassium Iodine Solution. 2~~
7. Ensure each team member has ade cuate protective clothing as required for the specific situation.

8. Assign the team a company vehicle. Keys are located in the Administration Building and the TSC. A key for the Emergency Van is also located at the Control Room.
O
~~9. If the assigned vehicle is not equipped with emergency equipment, obtain the necessary materialso from one of tr.e following locations:~~
~~a) Control Point b) TSC c) Emergency Van d) Quinton EDT NOTE The minimum items required include:~~
1. Air Sampler

2. Dose Rate Meter

3. Count Rate Meter
~~() 4. 5. SAM-2 or equivalent Particulate Filters~~
6. Charcoal or Silver Zeolite Cartridges

7. CommgrJeations Equipment (if not in vehicle!
I Rev. 1 ! Page 3 of 36 l l
EP IV-110 ACTION STATEFENTS (ccNTINUED) g INITIAL
~~10. Dispatch the survey team to the survey vehicle. Perform a communica ,~~
~~tions check between the vehicle and the TSC. NOTE If the vehicle is g radio-equipped, instruct the team to obtain a portable radio from the Main Gate,~~
11. Refer to the Instrument Instruction on the operation of the SAM-2 (attached to this procedure). Perform Steps 1 through 5 to allow the instrument to warm up and stabilize.

12. Proceed to the first survey location. Insure the team is centinuously monitoring the radiation levels with a Beta /Ga.-ena Survey instrument.
~~Document the survey results on the Survey Maps and/or the Emergency Survey Log. Inform the TSC of any significant fluctuations in the survey results. f~~
~~13. Upon arrival at the first survey location, initiate an air sa.ple.~~
~~Record the start times and the initial flow rate on the Emergency Survey Log.~~
~~14. Special consideration should be given to current meteorological conditions when directing the field monitoring teams for plume tracking.~~
This is especially necessary if wind speeds at Artificial Island are less than five miles per hour, for frequent wind shifts, if inversion , conditions exist, or if backup meteorological data is used from the ? Wil:nington Airport or some other of fsite f acility. Normally the tean { should be directed to locate the sector of the plume centerline and { survey the adjacent two sectors. (Consideration should be given to the radiation exposure to emergency workers.) For the conditions .
~
listed above, special consideration should be given to expanding the . sectors surveyed to characterize the plume meanderings, spreading, or l location af plume segments. O ; i The maximum flow rate is 2 SCFM for charcoal and 2 SCFM for Silver Zeolite cartridges.
?
~~Page 4 of 36 Rev. 1~~
~~- - - . . ~~~
~~1 I EP IV-110 BCTION STATEPENTS (CONTINUED) O 115E INITIAL~~
15. During the collection of the air samples, monitor the radiation levels and record the results on the Emergency Survey Log. Inform the TS cf the survey results while waiting for the air sample to finish collecting.
4
16. Refer to Section V of the Instrument Instruction for the operation of the SAM-2. Perform Steps 6 to Sg.

17. Upon completion of the air sample collection, count the samples per Steps Sh - 11 of the SAM-2 operational instructions. Document the calculations on the Emergency Survey Log. All samples shall be labeled with pertinent information and retained for future analysts. Pe-ain in plume only to collect sample and perform surveys. Count samples in low a background as possible.
~~NOTE Samples should be checked for excessive dose 1 rates. Any samples with a dose rate greater than 100 mR/hr should be stored in a remote, shielded corner of the vehicle.~~
18. Inform the TSC of the survey and air sample results.

19. Repeat Steps J - L for each survey location.
5
20. If the radio should fail, see the Communications Section of this procedure for phone numbers of the TSC, Control Point and Control Room.

21. Upon completing the assigned survey request additional instructions from the TSC. If surveys are to be terminated
-n g a) Log each team member's final dostmeter reading, the return time and the net exposure on the Dosimeter Log and the Dosimeter Cards, \.l b) Inform the TSC that the team is back on-site.
b Rev. 1 Page 5 of 36
EP IV-110 l ACTION STATEMENTS (c0NTINUED) M INITIAL c) Direct the team to return the equipment to the proper storage locations, d) Have the air samples analyzed for isotopic content.
~~22. Debrief the TSC on the survey results.~~
~~eTTACHMENTS~~
1. Dosimeter Log

2. Emergency Survey Log

3. Instrument Descriptions

4. Survey Locations and Maps COMMUNICATIONS SSS TSC CONTROL ROOM 1 CONTROL ROOM 2 CONTROL POINT Radio Radio No No No 635 200 633 641 611 201 Prepared B" _
~~Peviewed By: Dep *tm t'H 'D te Reviewed By: o ' fstInt to Manager Date Reviewed By:~~
~~Station Quality Assurance Engineer Date SORC Meeting No. : hf ' I f l [O!)7 !bf~~
~~' Dat e' Approved By:~~
~~Manager - fralem Generating Station~~
/b 'Datd Approved By: *
~~MM / Al [V Manager - Emergency Preparedness 'Date Page 6 of 36 Rev. 1~~
i EP IV-110 TIG. 1 FIGL'RE 1 O EP.ERGENCY TE R ASSIGNFENTS t ORIGINAL ASSIGNMENT TIME OUT TIME I?: TEAM CODE TEAM MEMBERS a 4 ED l
~~' i 3~~
~~a i i BLUE l i~~
~~O i~~
~~l a j cc:.D 1 i~~
~~l. .~~
~~O GREEN i~~
~~; ' DENOTES TEAM LEADER ]~~
~~t 4 Rev. 1 Page 7 of 36 4~~
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~~G O N I~~
D A E R T E _ N G N - I D _ A E R L A N I F E D G O N C I D M A A E E R T L A I T I N I E G T O A L D R E T N I K E O I S O D M I T Y T C N U E O G E R M E E I T R E RB EM 1 Tt EN M I L SA
~~) I X R I~~
~~E S R E B M U N E G D A B E M~~
~~A O R E~~
~~D A E N L M A E T~~
~~. On m .W 'll.~~
l jlllJl l
EP IV-110 ATT. D ATTACHr.ENT B Q EMERGENCY SUP.VEY LOG SHEET TEAM MEMBERS TEAMS DESIGNATICN_ d i
~~! INSTRUMENT SERIAL NUMBERS:~~
i 4 TELETECTOR PRM-4 RADECO PIC-6 ! E-520 RO-2 SAM-2 AIR SAMPLE CALCULATION Net Counts Per Minute 7 6 (cubic feet) (2.832 x 104 cm 3/ft3) (2.2 X 10 dpm/pci) (Detector EFF) TYPE OF FILTER (P) (SZ) (C) (P) (SZ) (C) fP) (SZ) (C) (P) (SZ) (C) I LOCATION GAMMA DOSE RATE BETA DOSE RATE SAMPLE DATE j SAMPLE START TIME SAMPLE STOP TIME At AVG. FLOW RATE VOLUME (ft ) COUNT DATE COUNT TIME l NCPM j 4EFF = DPM 6
~~+2.2 X 10 = uCi +ft = 1;Ci/ft +2.832 X 10 = uCi/cm NOTE NCPM = Gross CPM - Background CPM at Analysis Location.~~
~~! q 4 O Page 9 of 36 Rev. 1~~
~~- . . - - - - . - . - , _ , - , , - e - a - ~ _ - , ,~~
~~EP IV-110 f.TT. C ATTACHMEf4T C ({]) INSTP.UNEf1T OPEPAT10tl INSTPUCT10 tis~~
~
~~1. OPEPATl0N OF 90-2 (JUNO TYPE 10fi CHANGED) SUFVEY FETEP A. DEscRfpTf0N It has The Eberline RO-2/RO-2A is a 3" diameter air filled ion-chamber survey meter.~~
four linear rangest RO-2: 0-5, 0-50, 0-500 and 0-5,000 mR/hr, RO-2A: 0-50, 0-500, 0-5,000 and 0-50,000 mR/hr. The RO-2 and RO-2A utilize 3 and 4 NEDA 1604 9 volt batteries respectively. Its energy response is linear from 0.05 MeV to 6 MeV and can be operated in a temperature range of -40'T to +140'F. The detector's outer wall is 200 mg./CM and the inner wall is 7 mg./CM . B, CENEDAL INSTm0 MENT CHECK 00T J The meter
~~1. Turn the function switch to BATT 1 and then to BATT 2 positions.~~
~~should read above the BATT cutoff line in both cases.~~
2. Turn the function switch to ZERO position. Check that the meter reads zero. If not, set it to zero with the ZERO knob. (The zero setting of the instrument may be checked in any radiation fic-ld by merely selecting the ZEhc position.)

3. Set the function switch to the desired range of operation. Wait 10 seconds for full meter response. The switch position selected is the full scale reading of d that range.
~~C. TC DEDCOCM A DOSE RATE SUCVEY~~
1. When measuring beta or low energy gamma or X-ray emissions, open the sliding . .e ta toward the shield on the bottom of the case and face the bottom of the instrument radiation source. To open or close the shield, depress the friction release button on the left side of the case and manually move the slide or let it fall due to gravity. When the shield is open, protect the thin face against damage.

2. Hold RO-2 waist level (approximately 1 meter above ground).
~~l l i 3. Hold meter steady and note open window and closed window readings.~~
~~4. Record reading, location, date and time.~~
eg Page 10 of 36 Rev. 1
1 1 EP IV-110 ATT. C
~~)), OPERATION OF PIC-EA 10N CHMGED SUDVEY METED.~~
A. DESERfDTION walled gas filled ion chamber The Eberline PIC-6A is a 1/2" diameter 30 mg./CM 1-10, 10-100, and 100-1000 mP/hr portable survey metc~. It has 6 logarithmic ranges: Thus the total range of the survey meter is from plus 1-10, 10-100 and 100-1000 R/hr. It utilizes 2 ttE0A type 604 batteries (9 volts) and weighs 1 mR/hr to 1000 R/hr. about 3.3 pounds. Its energy response is linear from 0.8 to approxtmately 6 Mev, and it can be operated from -10' to +140*F. B. GENEDAL INSTDUuENT CHEEK 0UT The meter should read in the BATT CK region.
1. Turn the function switch to BATT.

2. Set the function switch to the desired range. A single rotary switch selects the range to respond in either the mR/hr range or the R/hr range.

3. Wait 10 seconds for full meter response.
~~C. TO DERD00M A DOSE RATE EUDVEY~~
~~1. Hold PIC-6A at waist level (approximately 1 meter above ground) .~~
~~O 2. Hold meter steady and note closed window reading.~~
3. Hold meter steady and note open window reading.

4. Record readings, location, date, and time.
111. 0FEDAT10f4 0F E-520 GM TUEE SURVEY PETED A. DESERIDTION The Eberline E-520 is an external GM tube probe plus internal tube portable survey meter. The external GM tube has 4 linear ranges of 0-0.2, 0-2, 0-20, and 0-200 mR/hr. Its energy response It utilizes two "D7 batteries and weighs approximately 4-1/2 lbs. I is linear from 0.2 to 2 Mev. With alkaline or Nicd batteries, it can be operated from and the
~~-40* to +140*F. The external detector outer wall is approximately 200 mg./CM mg./CM . An external speaker is available for use with this meter.~~
~~2 inner wall is 30 B. GENERAL INSTRUMENT CHECKOUT The meter should read in the BATT CK region.~~
~~1. Turn the function switch to BATT.~~
~~Sc; the function switch to one of the five sensitivity ranges. () 2.~~
~~3. Wait 15 seconds for full meter response.~~
Rev. 1 Page 11 of 36
' EP IV-110 ATT. C g-'s C, TO 'EPROD" A 00?E ' ATE SU'VEY d NOTE s This GM tube survey meter may saturate (and read zero) in a radiation field in excess of 1000 R/nr. NOTE The high range detector (0-2000 mR/hr) is located in the meter case and not in the hand held probe.
1. Hold E-520 at waist level (approximately 1 meter above ground).

2. Hold meter steady and note closed window reading.

3. Hold meter steady and note open window reading.

4. Record readings, location, date, and time.
IV, OPERATION OF THE HIGH VOLUPE AIR SAPPLEP (H-709V) A. CESCRfPTfCN O The H-709V is a 110 VAC, 2-28 CTM variable flow, high volume air sampler. The sampler a 2-inch filter paper for particulate sample collection and a is designed to accept CISCO charcoal, or Silver zeolite cartridge for Iodine 131 sampling. B, TO ODEDATE AfD SA"DLED Place the Iodine cartridge and a filter paper into the filter holder. Attach 1. the filter housing to the sampler.
2. Plug the sampler into a 110 V outlet and turn it on. Insure the flow meter is operating by tapping lightly on the flow meter housing. Switch the sampler power switch to the variable position for a 2 inch sample.

3. Obtain a 40 cubic foot sample; approximately 2 CTM for 20 minutes.
~~NOTE Smaller vsieme samples may be requested by the EDo. Sampling times should be adjusted accordingly.~~
~~4. Observe flow rate during sample. Record air flow, duration of sampling time, and location where sample was taken.~~
(_/ Rev. 1 Page 12 of 36
EP IV-110 ATT. C
~~5. Place cartridge and filter paper into separate envelopes and mark each envelope~~
( with the following information: Date: Emergency Station No.. _ Sample Start Time: min. Sample Stop Time: min. ft. / min. Tech. Sample Flow Rate s Record sample data on the Dmergency Survey Log. V. OFE:ATION OF SA"-2 Dual SINGLE CHANNEL ANALY2ED (WITH 2" x 1/2" NAl CRYSTAL) A. DEscoloTION The Eberline SAM-2 is a lightweight (7 lbs.) two channel gamma spectrom.eter which is stabilized to correct automatically for gain changes (caused by temperature changes, etc.). It can read out each channel independently or the sum or difference of both channels on either a scaler or ratemeter. It will operate from either a 110 volt AC outlet or its cwn 8 pound battery pack. It utilizes a 2" x 1/2" Sodium Iodide crystal which, with its lead shield collar, weighs about 8 pounds. This counting system is designed to operate from 32*r to 140*r. It has both a preset timer and a manual timer. It is fused for both AC and DC operation. CAUTICN The Sodium Iodide probe is fragile and should be handled with care. The Sodiu= Iedide probe should not be taken through rapid temperature charges, it may crack if brought from 30' to 60* with-out some thermal wrapping to slow down temperature equalization. B. ODECATION
1. Utilize a gamma survey meter (low range) to find as low a background area as practicable (0.5 mrem / hour) in which to perform the counting functions. If tack-ground is greater than 0.5 mrem / hour, provide shielding as necessary.

2. Plug cord into 115 VAC, 60 Hz power source or connect to battery power through BATTERY connector (pin 1 negative, pin 2 positive) . Allow the instrument to warm up for at least 10 minutes. A 20 minute warm up period or longer will provide optimum stability results.

3. Connect detector.
O Rev. 1 Page 13 of 36
i l l EP IV-110 l ATT. C 4 Set controls as follows: O al STABILI*ER-ON (rear of instrument) b) H.V. ADJUST - 4.0 c) CH-1 THRESHOLDS - 10. 00 d) Both IN-OUT to OUT el DISPLAY - ON f) TIMED-STOP-MAN - STOP g) CH1 to +, CH2 to CFF i
5. Turn POWER switch ON and push RESET-START switch. The readouts should be all zeros.

6. Operation Check a) Set TIMED-STOP-MAN switch to TIMED.
Press RESET-START switch. () b) Set COUNT TIME IN MINUTES switches to 1 and X.1. Unit should stop counting after 6 seconds, registering 4500-8500 counts (no background). c) Under the above conditions, meter should read 45000 to 85000 counts per minute.
~~7. Detector Preparation a) Shield the RD-19 detector as necessary to insure background less than 0.5 mrem / hour (if possible).~~
~~b) Care must be taken not to contaminate the detector with samples. The face saran wrap, of the d.etector may be covered with a thin plastic sheet (i.e., etc.) and fastened with a rubber band.~~
~~8. Counting Iodine-131 a) Set CH1 WINDOW at 0.7 volts and "IN" f~~
b) Set CH1 THRESHOLD at 3.3 c) Set CH1 switch to "+" g-'g G d) Set CH2 switch to " " and CH2 WINDOW to "IN" R*V- 1 Page 14 of 36 l
EP IV-110 ATT. C e) Set CH2 WINDOW at 0.7 volts f) Set CH2 THRESHOLD at 4.0 g) Set COUNT TIME to 1 minute (1 and X1) . Set COUNT to " TIMED" h) Prtss START button
1) Count background for one minute. If background is greater than 500 cpm, provide additional shielding (if practicable) i j) Set COUNT TIME to "5 and X1" k) Press START button

1) c;2nt sample (Iodine cartridge) for 5 minutes (set count time to 5 and X11

9. Carefully mark and save all samples for later laboratory evaluation.
~~131 activity as follows:~~
~~10. Calculate Airborne I a) Multiply the Net epm by 40 (the efficiency factor for a 0.7 volt windcw 131 peak) to get a reading in dpm.~~
~~spanning the major I O b) Multiply the reading (in dpm) obtained in 10.a. above, by 4.5 X IC~~
~~~I LCi/dpm to obtain a reading in LCi.~~
3 I c) Multiply the sa=pling time (minutes) times the sample flow rate (ft / min) times 2.832 X 10 4 cc/ft3 to find the total sample volume (in ec). I d) Divide the total I 131 reading of step 10.b above (uCi) by the total sample volume (in ec) found in 10.c above to get total activity in uCi/ce. e) Record the following information: 4 Emergency Station No. Date/ Time Sample Counted I'l Activity uCi/cc Date/ Time Sample Taken
11. Alternate Method Refer to Table C-1 to determine concentration and thyroid dose rate.

12. Refer to Figure C-1 or Table C-1 to obtain thyroid dose rate.
l
~~13. Communicate SAM-2 results and derived dose rate to TSC.~~
~~(xh~~
~~\ s Page 15 of 36 Rev. 1~~
EP IV-110 ATT. C O VI, OPEPATION OF PNC-4 POETA:LE NEUTRON COUNTER V i DEscRfRTION A. The Eberline PNC-4 has a BF3 detector with caimium shield and moderator for use in detecting fast or slow neutron radiation. The count rate is read out over four decades (500, SK, 50K and 500K cpm) using two separate meter movements. The instrument requires five standard "D" size batteries. Within the instrument is a moderator consisting of parafin wax encased in a cadmium sheath. Total weier.t cf the instrument is about 12 pounds. B. CENEDAL INSTRUMENT curcycut
1. Turn switch to BATT check position. The left pointer (black) should read in the green area.

2. Release switch and it will spring return to the ON position.
~~C. TO PERCCR* A DOSE RATE SURVEY~~
~~1. To detect fast neutrons, the detector must be inserted into the " moderator" and to detect slow neutrons the detector must be out of the " moderator".~~
~~() 2. If possible, use a beta-gamma survey meter when performing neutron surveys as a precaution.~~
3. Hold the PNC-4 at waist level (approximately 1 meter above ground) .

4. To read the meter, simply read whichever of the two pointers is on scale. The black pointer is read up to SK cpm, above which it disappears frcm view and the red pointer comes on scale.

5. Watch the pointer long enough to obtain the average reading for fast and slow neutrons, as required.

6. Record the readings, location, date and time.
Vil, OPERATION OF PRE-4 PuliE RATE FETER A. DESCRIPTION The Eberline PRM-4 pulse rate meter is used for the detection of beta and gamma radia-tion. The count rate is read out over four decades (200, 2K, 20K and 200K cpm) using two separate meter movements. The instrument requires five standard "D" size batteries. Total weight of the instrument is 5.25 pounds.
~~/~%~~
(~ A Rev. 1 Page 16 of 36
EP IV-llo ATT. C B. GENEDAL f>J"RUwENT CHECK 0UT l')S
1. Turn the switch to the BATT check position. The lef t pointer (black) shculd read in the green area. .

2. Release switch and it will spring return to the CN position.
~~C. TO DEDDORM A DOSE RATE SUDVEY l~~
1. Using the HP-240 probe detection of gamma radiation is done with the sliding window closed. To detect beta, simply open the sliding window.

2. Hold the PRM-4 at waist level (approximately 1 meter above ground).

3. To read the meter, simply read whichever of the two pointers is on scale. The black pointer is read up to 2K cpm. above which it disappears from view and the red pointer comes on scale.

4. Watch the pointer long enough to obtain the average reading.

5. Record the readings, location, date, and time.
Vill, OPEDATION OF THE GENEPAC (6330) PORTAELE ALTEDNAT0D O A. DESCDfDTION The GENERAC 6330 Portable Alternator is a revolving field single phase alternator rated at 115 VAC, 60 cycles, 13 amps, 1500 watts. The alternator is driven by a 4 cycle, single cylinder, 3.5 horse power gasoline engine. The unit itself is light-weight and can be moved by one person and is easily handled by two persons. B. GENERAL CHECKOUT
~~1. Check the alternator and engine as outlined in the technical manuals attached to the unit.~~
~~C. ALTERNATOP ODERATION~~
~~1. Operate the GENERAC 6330 Portable Alternator engine unit as outlined in the technical manuals attached to the unit.~~
l (D v Page 17 of 36 Rey. 1
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7 . Page 18 of 36 Rev. 1
EP IV-llo TABI.E C-1 TABLE C-1 REM DOSE TO THYPOID l'OR 1 HOUP e.XPOS"PI < Infant Non-cccu-SAM-2 cp= uCi/cc* and pational Wcrking Mult Above BacFJ;rocnd (assu=ing 1 ft3 and 2.5% eff) Child Teen Adult 118 108 87 131 1 X 10 5 6.4 E-5 54 44 65 4 3.2 E-5 59 5 X 10 4 12 11 9 13 1 X 10 6.4 E-6 5 4 7 3.2 E-6 6 5 X 10 1.2 1.1 0.9 1.3 1 X 10 6.4 E-7 0.6 0.5 0.4 0.7 5 x 10 3.2 E-7 6.4 E-8 0.12 0.11 0.09 0.13 1 X 10 0.06 0.05 0.04 0.07 50 3.2 E-8 0.01 0.01 0.01 0.01 10 6.4 E-9 i.a. cubic ' 'To correct for actual sample volu=e divide tabulated uCi/cc value by the actual volume feet. A O Page 19 of 36 Rev. 1
EP IV-110 ATT.D ATTACHMENT D ON SITE EMERGENCY MONITORING LOCATIONS H 2. j aME 2 16 .
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= Alt. TSC l h=Emer. Location ARTIFICIAL ISLAND SITE EMERGENCY PLANNING MAP j f I l
Rev. 1 ! Pace 20 of 36 1
l EF IV-110 ATT. D ATTACHF.ENT D f n ON SITE EFERGENCY MONITOP.ING LOCATIONS d DESCRIPTION LOCATION N-S1 420' N, on inner access road , N-52 750' N, security road inside fences N-53 1500' N, Hope Creek Unit 1 Turbine Building (center of east side en ground) NNE-S1 400' NNE, NW corner SNGS Unit 2 Turbine Building (on ground) NNE-S2 850' NNE, SNCS North Fence Vehicle Access Gate NNE-53 2075' NNE, SE corner Hope Creek Change House NE-S1 600' NE, inner access road, NE intersection NE-52 1150' NE, SW corner SNGS #2 Warehouse NE-S3 1825' NE, SW corner Hope Creek parking lot for trades ENE-51 450' ENE, NE corner SNGS Administration Building ENE-S2 1360' ENE, inside site security fence at NE corner of switchyard E-51 400' E, SE corner SNGS Cafeteria E-S2 1300' E, SE corner switchyard, outside security fence ESE-51 500' ESE, sidewalk 150' N of Unit 1 Guardhouse (at Hose Station) ESE-52 1020' ESE, Guardhouse to SNGS employee parking lot /^ access road on outermost parking lot fence ( ,g/ ESE-53 1960' ESE, SE-51 160' SE, closest outside entrance to HP control point (next to #1 Unit Steam Mixing Bottle) SE-52 560' SE, NW corner of SNGS Main Guardhouse SE-53 1060' SE, SW corner of permanent visitors Center SE-54 1100' SE, "Second Sun" barge (when in port) SSE-51 360' SE, NW corner of TSC S-51 360' S, NW corner of B Building 5-S2 825' SE, NE corner of Cire Water Intake Structure SSW-S1 250' SSW, Chemistry Trailer SSW-S2 560' SSW, on , security fence halfway between N end of Cire Water Intake and S end of Service Water Structures SW-S1 490' SW, NE corner of Service Water Structure WSW-S1, 440' WSW, 150' N of llS1 on access road W-S1 510' W, security access road, due W of a point midway between the two Containment Buildings, W of S end of A Building WNW-51 6 9 0 ' kR.d , inside NW corner of security fence at right angle (inside fence) NW-S1 600' NW, inside security fence, 275' from NW corner of fence (near riveri NW-S2 1340' NW, Hope Creek Structure, SW corner Hope Creek Road /~'i N/I NNW-51 600' NNW, inside security fence, 500* from NW corner of fence NNW-52 2400' NNW, SE corner of Hope Creek Material Test Lab Page 21 of 36 Rev. 1
Ep IV-110 ATT. D ATTACHMENT D O orrSt S **S" "" ' " " " "'*" ' ' ""
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0 page 22 of 36
EP IV-110 ATT. D ATTACHMENT D O OFFSITE EMEP.GENCY MONITOPING STATIONS EMERGENCY a MILE A:MU-H SNCS ENV. OI D NEW LOCATION SECTOR 3 N7 Ft. Elfsborg, across from Golf Course 1 5.8 7 /4' 1F1 1 1 9.6 3551 /2' None N10 Ft. Mott, Ft. Mott Rd., S end 1 10.5 10' 1G1 None N20 Rt. 49 0.2 mi. S of Hock Rd. Rich =cnds
~~Dairy 2 4.4 20' 2El None NNE5 Farm 2 5.8 241 /2' 2 NNE7 Ft. Elfsborg & Amwellbury Rd.~~
2 8.7 1 24 /2' 2F2 7 NNE10 Salem Test Lab 2 7.4 26* 2F5 None NNE10a Salem High School 2 10.3 28' None NNE20 Salem County Hospital 1 End of Poplar St. 3 3.8 45 /8* None NE4 3 4.1 48' 3E1 None NE5 Farm 3 5.1 51.5* 3F2 4 NE7 LAC 3 5.8 39' 3 NE7a Mill St. & Han. Br.-Quinton Rd. 8.8 49' 8 NE10 Water Works Rd., Quinton 3 O 1 (0.2 mi. N of 3F3) Corner Clancey & Quaker Neck Rd. 3 10.8 44 /2' None NE20 4 3.7 66' 4D2 None ENE4 Alloway Creek Neck Rd. l 4 4.1 59' 5 ENES Alloway Creek Neck Rd. 1 Harmersville, Dilks Store, Red Light 4 5.9 62 /2' None ENE7 4 8.6 67* None ENE10 Woodmere, Corner Harmersville Pecks Corner Rd., & Jerico Rd. 10.5 72* None ENE20 Pecks Corner, Rt. 49 & Harmersville Rd. 4 5 0.9 90' SS1 62 El Split in Site Access Rd., Hope Creek-Salem Y' 5 3.5 80' SD1 6 E4 Pole GCCO G-68 SP10-40, Air Sampler
5 6.5 841 /2' ~ 5F1 9 E7 Canton, main intersection None E20 Shiloh, main intersection Rt. 49 & Bank 5 12.6 99*
6 6.4 104' 6F1 None ESE7 Stowe Neck Rd. 6 8.1 102* 10 ESE10 Gum Tree Corner 6 11.3 118' 12 ESE20 Greenwich. 0.7 mi. S of center of town on Cohansey Creek 7 8.8 128' 7F2 11 SE10 Bayside 7 11.4 125' None SE20 Ragged Island 161' None SSE10 Woodland Bench, Rt. 6 at Del. Bay 8 9.6
*Also environmental air location Page 23 of 36 Rev. 1
i EP IV-110 ATT. D EMEROEhCY # NEW LOCATION AtMUTH SNCS E!N. DLD SECTOR MILE l O 8 14.5 168' None SSE20 Rt. 9 at Whitehall Neck Tailor's Bridge Spur Rd.-end 1 4.2 188' 9El None SS 9 None 57 Thoroughfare Neck . 9 5.8 179' None S10 Broadway Meadow 9 8.8 176* 176' None S20 Whitehall Crossroads 9 13.2 203' 10D1 105 SSW4 Taylors Bridge Spur Rd." 10 3.9 5.6 1981 /2' 10F1 None SSW7 Rt. 9 intersection 10 SSW10 Walker, Rt. 9 10 8.9 203' None 1001 None SSW20 Smyrna, Rt. 13 & Rt. 6 corner 10 11.6 198* 218' llE2 None SW5 Taylors Bridge, Rt. 9 11 4.9 235* 11F1 Ns"? SW7 Taylors Bridge 11 6.0 None SW10 Point Breeze Fork, Rt. 13 & 896 11 8.9 231' 225' None SW20 Dexter Corners 11 12.3 12El None WSW5 Thomas Landing 12 4.4 258' 6.0 256' None WSW7 Matthews Corners (off Rt. 9) Rt. 299 12 106 WSW10a Pine Tree Corners, Rt. 13 12 7.7 241' 12F1 None WSW10 Townsend Elementary School 12 9.4 241' 11.9 262* None WSW20 Intersection 1.5 mi. West of Townsend 12 Cemetary 103 W5 Rt. 9 Appoquimimink River, Icth. Lab 13 4.2 275' 13E1 13F2 107 W7 Odessa, 2 blks. E of Rt. 13 on Rt. 299 13 6.0 266* 104 W10 Middletown, Icth. Assoc. Hdqtrs. 13 9.9 165' 13F1 None W20 Rt. 299, 1.5 mi. W of Middletown 13 11.3 263' 296* 14D1 102 WW4 Bayview, Coast Guard Station Gate 14 3.4 None WNW5 Rt. 9 (90* turn), 0.7 mi. W of Bayview 14 4.1 296* 294' 14F2 None W!N7 Boyds Corner, Rt. 13 14 6.7 291' None WNW10 Cedar Lane 14 8.5 None W!N20 Sur:mit Bridge (Town not bridge) 14 11.4 297* 318' None NW4 Augustine Beach (0.2 mi. S), Rt. 9 15 3.8 None NW7 Biddle Corner Intersection, Port Penn Rd. 15 5.5 314' 15F3 None NW10 S end St. Georges Bridge, Rt. 13 15 8.4 314' None NW20 Kirkwood, Del. 15 11.5 311' 101 N!N S Port Penn Sewage Plant
16 4.2 330* 16El NNW7 Rt. 9 at Wooden Bridge 16 5.9 337' None O 100 NNW10 Del. City, office of-Emerg. Planning 8.1 343' (f 16 Rt. 301 Fork 333' None NNW20 Rt. 13 16 12.3
*Also environmental air location Page 24 of 36 Rev. 1 , = . = ..- ,
~~EP IV-110 STATION N7~~
1. Proceed to Hancocks Bridge intersection.

2. Turn left and proceed 1.6 miles to Elsinboro turnoff. -

3. Turn left on Elsinboro cutoff.

4. Follow road 1.7 miles to fork.

5. Take right fork .2 miles to fork in road.

6. Take left fork and proceed 1.5 miles to Elsinboro intersection.
~~NOTE: Pole will be located left side of intersection. Pole No. S25440 383-1 em sasiam*f ** W s.4 DT.* N %~~
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p. Pace 25 of 36 Rev. 1
I EP IV-110 l STATION NNE7 D V 1. Proceed to Hancocks Bridge intersection.
~~2. Turn left and proceed 1.6 miles to Elsinboro turnoff. j~~
)
j
3. Turn left on Elsinboro cutoff.

4. Follow road 1.7 miles to fork.

5. Take right fork .2 miles to second fork. This is location of Station #2.
~~NOTE: Pole will be located directly across intersection. Pole No. BT-324-65 b Sbd143%4CT W~~
~~t. S.~~
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3 s o ? l( X ^g y. uk Page 26 of 36 Rev. 1
EP IV-110 STATION NE7a O 1. Turn left at Hancocks Bridge intersection towards Salem,
~~2. At 1.6 miles from intersection you pass the Elsinboro cutoff, ,~~
~~disregard and proceed towards Salem.~~
~~3. Station #3 is at .2 miles from Elsinboro at intersection.~~
~~NOTE: Pole I.D. is on the Salem side of intersection. ea.. a y wws~~~
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Page 27 of 36 Rev. 1
EP IV-110 S'"ATION NE7
l. Proceed down access road from main gate to Hancocks Bridge intersection (%6 miles).

2. Turn left at Har. cocks Bridge intersection and proceed .5 miles e and turn left to fire station. 1 2
~~M STnTww J / Te s A L.s - r:, D. ' kk b' " Atb4~~
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N Oy. w. [ '\\ s d O Page 28 of 36 Rev. 1
EP IV-110 l STATION ENES
1. Proceed frcm main gate, down access road, for 5.4 miles.

2. At curve, pull off to left side on old road and locate .
~~Pole No. ACE S-28944 (36).~~
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i T. Mci 6 O l Page 29 of 36 Rev. 1
l EP IV-110 STATION E4 O 1. rrom maia sete, eroceea 4 =11e= oa ecce== roea-
2. Pole is located on left hand side of the road just past turn. I 1

3. Pole has white air monitor box attached. Pole is No. GCCO G-68 SP10-40.
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N O ~.g-ja su n,2% s' i\ S s e.wi' . I j O l l 1 Page 30 of 36 Rev. 1 l l
FP IV-110 STATION NNE10 access road to Hancocks Bridge intersection.
1. Proceed out

2. Turn left and proceed 4.7 miles to light on Route 49. '

3. Continue through light .5 miles to the end of the road.
~~) Turn left and proceed two traffic lights. turn right and proceed s 4.~~
~~5. At third traffic light (Anchor Hocking),~~
~~.2 miles to substation. d.~~
~~Substation is located on the right hand side of the roa We do not have a key for substation. NOTE: f pys. w.. "Oo~~
~~%%MS .,e..s I'~~
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J g%, genuf STECCT 1 1 .s e i 7 W i , $W' GL L - A \c e 9euTC M (NW Qg, i l w e sixen . I .
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~~~8V- 1 Pace 31 of 36~~
_ . mummum
l EP IV-110 l l l l
~~-STATION NE10 0 1. Proceea aowa ecce== roaa to neacocx 8ria se iacersectiom.~~
~~2. Continue through the intersection .3 miles and take the left -~~
~~cutoff.~~
3. Proceed straight through stop sign 2.6 miles.

4. At second stop sign, turn left.

5. Proceed 2.5 miles to Route 49.

6. Turn left on 49 and proceed .1 miles to traffic light.

7. Turn right at light and proceed .2 miles to Water Works Road.

8. Turn right at Water Works Road.

9. Proceed .3 miles to pumping station on right.

v. g NOTE: Pole is located in M% I, front of pumping station. Pole No. S29335.
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Pane 32 of 36 - ~: 7 . L
EP IV-110 STATION E7 O
l. Proceed down access road to IIancocks Bridge intersection.

2. Go through the intersection and keep bearing to your right towards Harmersville (^-1 mile).

3. At the blinking light (Harmersville interseccion), turn right towards Canton.

4. Station #9 is 2.4 miles on the Harmersville-Canton Poad.
~~NOTE: Pole is located across the street from house in picture. Pole No. ACE 996 L224.~~
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EP IV-110 STATION ESE10 V 1. Proceed down access road to Hancocks Bridge intersection.
2. Go through intersection and keep bearing to your right towards Harmersville (N1 mile).

3. At blinking light (Harmersville intersection), turn right towards Canton.

4. At 5.3 miles down the Harmersville-Canton Road you will come to the Gum Tree intersection (Station #10).
~~NOTE: Pole is located by the tree at intersection. Pole No. ACE 12410. T. b le~~
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Pace 34 of 36 Rev. 1
1 l EP IV-Il0 STATION SE10 l l 1. Proceed down access l - road to Hancocks Bridge intersection.
~~2. Go through inter-section and keep bearing to your right towards Harmersville~~
~~(%1 mile).~~
~~3. At blinking light (Harmersville intersection), turn 4,, g G g T. Lim 4,~~
~~right towards w, Canton.~~
~~4. At 5.3 miles down N~~
~~the Harmersville- s.4 Canton Road, you t, g will come to the Gum Tree inter- %@. w N~~
~~,f:p section. .~~
4
~~5. Take the far right cutoff for 2.8~~
~~[*N 0 /sa. miles to Mill Road.~~
'--n q*
~~O e. Turn rieht end mi11 Road is .4 miles to N~~
~~< i.. ~the fork. " . ^g 7 d\~~
~~7. Take left fork .3 a.ng miles to a second u fork. '\ %~~
~~% h c. ,,a,~~
~~8. Take left fork, , ***" i- Tr. 4 )~~
~~again proceed 0.5 miles to another m , .. h. 0 intersection. m;a% A~~
~~9. Turn right at~~
, J ~,, .,/ 'R'<%. c. w-intersection 4 g and proceed D i %N \ b.h e'
1.2 miles to l another inter- Ma section. ( Aa,- N W m'JI IW bue O
~~10. Turn right w %j \ 4 again and proceed .5 JT snme . s.:a~~
~~O k j; ,~~
~~NOTE: Station is i l O~~
~~% located 5 poles from l~~
the water. Pole No. 15547. Rev. 1 Page 35 of 36
EP IV-110 D -STATION ESE20
\)
1. Proceed down access road to Hancocks Bridge intersection.

2. Go through the intersection and keep bearing to your right towards Harmersville (%1 mile).

3. At blinking light (Harmersville 7, intersection), Au turn right towards 'D a i Canton. W%

4. At 5.3 miles on the Harmersville- '
~~Canton Road, you '*4 will come to the T* %%~~
Gum Tree inter- % 4' section (Station

v 10 ) .
~~8 j O 5. Take the middle~~
~~.Q 0~~
[sw l road of the inter- '"' l section 4.9 miles __ to Greenwich. ( m agg g 1 m.4 %
~~6. At Market Lane in Greenwich, turn f.1. H ,~~
right and proceed k4 11e 0 \ 8-*
~~.7 miles to the intersection (Station #12).~~
~~D' k ,Wb u.a.4,~~
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7. Pole is located

m. m. y'g. -
"*'2**
~~l at the intersection. Pole No. B-19518. 0 /4 l mm rk,,i Ag~~
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~~D,th A Page 36 of 36 Rev. 1~~
~~EP IV-lli () EMERGENCY PROCEDURE EP IV-111 EFFLUENT DOSE CALCULATIONS~~
~~. 1 ACTION LEVEL l~~
This procedure shall be implemented upon the request of the Senior Shift Supervisor /EDO cr the J Radiation Trotection staff. f The calculations shall normally be performed by the Radiation Protection personnel in the TSC. The primary individuals responsible for the initial calculations will be the Shift Radiation Protection Technician (Shift RPT) and the REP /ALARA Supervisor. LIMITS OF AUTHORITY Projected off-site dose estimates should be forwarded to the Senior Shift Supervisor /EDO and the Radiation Protection Engineer. Transmittal of the projected doses shall require the prior approval of the Senior Shift Supervisor /EDO. If re-entry into the affected area is required for effluent determination, consideration shall be given to the potential for encountering high dose rates. Approval of the Radiation Protection Engineer and the EDO shall be obtained prior to entering the penetration areas. ATTACHMENTS No. 1 - Xu/Q Value Determination No. 2 - Noble Gas / Iodine Dose Conversion Factor (K) vs. Decay Time No. 3 - R43 Calibration Factor vs. Decay Time No. 4 - Default' Values for Low /High Plant Vent Monitors No. 5 - Containment Monitor R21 Response vs. Dispersion factor No. 6 - Survey Meter Responsa vs. Main Steam Activity No. 7 - Unit Analysis of Off-Site Dose Calculations ; I ACTION STATEMENTS
~~1. Contact the Control Room and obtain a briefing on the incident and identify the probable pathways for release of radioactive material.~~
1 i Page 1 of 21 Rev. 1
EP IV-Ill O l V ACTION STATEMENTS (CONTINUED) ) i
~~2. Determine which sections of this procedure are appropriate for the particular release. .~~
~~I TYPE OF RELEASE PAGE A. Releases from PLANT VENT (Elevated Release) 3~~
~~1. Unit el .~~
~~l 6~~
~~2. Unit #2 9~~
~~B. Unmonitored releases from: (Ground Release)~~
1. POWER OPERATED RELIETS

2. AUTCrtATIC RELIEFS

3. STEAM DRIVEN AUX FEEDWATER PLMPS i 12 j C. Releases due to CONTAINMENT LEAKAGE (Ground Release)
I l O f Page 2 of 21 Rev. 1
EP IV-lll l O V A.1 Pf3NT RF? RASE FROM UNIT NO. 1 A.1.1 CONTACT THE CONTROL ROOM AND ENSURE THAT 10.-11A, 1P-12A AND IP-12B ARE IN THE " PLANT VENT" MODE. IF THEY WERE NOT, ALLOW SUFFICIENT TIME FOR THE CHANNEL READINGS TO STABILIZE. l A.1.2 RECORD THE FOLLOWING PLANT PARAMETERS FOR SUBSEQUENT CALCULATIONS. , VALUE AFTER METER HAS BEEN IN THE VALUE WHEN METER METER PLANT MODE FOR IS FIRST PUT IN VALUE AT PARAMETER NUMBER TIME, TX _ PLANT MODE SELECTED TIME Low Range 1R-12A cpm a. Gaseous Release Rate
b. High Range R-43 mr/hr Gaseous Release Rate

c. Iodine Release 1R-12B cpm (Cx) cpm (Co)
~~Rate time (Tx) time (To)~~
~~d. Plant Vent II cfm~~
)
~~J Flow Rate~~
e. aTemp I I(4I at C' Wind Speed I II#I mph f.

g. Wind Direction (4) (5)
(from) NOTES: (1) If plant vent flow rate is unobtainable or cannot be estimated, assume 125,000 cfm. (2) If the (300'*C)-(33'*C) is unobtainable to determine the at use the (150'*C)-(33'*C) reading. If this is unavailable refer to Note 4. (3) If the wind speed is unobtainable, assume 5 mph. Use Elevation 300' data for an elevated release. Use Elevation 33' data for a ground release. (4) Backup meteorological data from Wilmington Airport (302-323-2280 or NAWAS Line) including wind speed, wind direction and an estimated stability class. If the estimated stability class is nat available, assume conditions to be stable. (5) If time pennits average data over 15 minute period. O V R*V. I Page 3 of 21
a . EP IV-lli (]) A.1 PLANT RELEASE FROM UNIT NO.1 (CONTINUED) N0 ELE GAS CONTRIBUTION TO WHOLE BODY DOSE RATE . ! I A.1.3 LOW RANGE QE DEFAULT VALUES (ATTACHMENT 4) Noble Gas (IR-12A)(Plant Vent Flow Rate) (Xu/Q) (Dose Ccnversion Factorl (5E-4) , mrem (Wind Speed) hr (a )(b )(c ) (d )(SE-4) , mrem hr (e ) QR A.I.4 HIGH RANGE (R-43) 1 Noble Gas I (R-4 3) (Plant Vent Flow Rate) (Xu/Q) (Dose Conversion Factor) (1.05E+3) , mrem ; (Wind Speed) (Concentration Conversion Factor) hr O (f )(b )(c )(d )(1.05E+3) , mrem
~~) (g ) hr te NOTE~~
a. 1R-12A in epm, or equivalent cpm value from Attachment 4.

b. Plant vent flow rate in ft / min.
2
c. Xu/Q value from Attachment 1. (1/m )

d. Dose conversion factor from Attachment 2. (*#'"# #)
~~pCi/m~~
e. Wind speed in miles per hour,

f. R-43 reading in mR/hr.

g. Concentrationconversionfactorin*[*g## Attachment 3.
4 Date Time CalcuIated By Date Time Reviewed By O Page 4 of 21 Rev. 1
EP IV-lll I () A.1 PLANT RFIFASE FROM UNIT NO. 1 (CONTINUED) IODINE CONTRIEUTION TO THYROID DOSE COMMITMENT . A.1.5 DETERMINE THE RATE OF INCREASE OF 10 DINE ACTIVITY. a) Low Range Monitor 1R-12B Aepm , Cx-Co , ( )-( ) , ( I cpm ,, g ) min er amin Tx-To ( )-( ) ( 1 min I NOTE I Refer to Step A.l.2(c). QR b) Using Def ault values Use Attachment 4 to determine the appropriate equivalent epm / min. () cpm / min l A.1.6 EQUATION FOR 50 YEAR DOSE COMMITMENT Iodine
,eE %. In )(Plant Vent Flow Rate) (Xu/Q) (Dose Conversion Factor) (3. 5E-7) * "#'*
~~(Wind Speed) (a )(b )(c ) (d )(3.5E-71 = mrem le ) NOTE~~
a. cpm / min from Step A.l.5 (a or b).

b. Plant vent flow rate in ft / min.

c. Xu/Q from Attachment 1. (1/m )
~~- d. Dose conversion factor from Attachment 2. (mrem /hr) vCi/m~~
~~e. Wind speed in miles per hour.~~
Calculated By Date Time Reviewed By Date Time Page 5 of 21 Rev. 1
EP IV-111 1 A.2 PLANT RM RASE FRO
~~UNIT NO. 2 O~~
l A.2.1 CONTACT CALCULATIONS. THE CONTROL ROOM AND OBTAIN THE FOLLOWING PLANT i l VALUE AFTER METER HAS BEEN IN THE VALUE WHEN METER METER PLANT MODE FOR PARAMI*ER NUMBER TIME, TX IS FIRST PUT IN VALUE AT PLANT MODE SE:.ECTED TIw.!
a. Low Range 2R-41C Gaseous cpm Release Rate

b. High Range R-43 Gaseous mr/hr Release Rate

c. Iodine Release 2R-41B cpm (Cx)
~~Rate cpm (Co) time (Tx) time (To)~~
~~d. Plant VentII Flow Rate ,~~
~~cfm ) e. ATemp I II4I Lt C'~~
~~f. Wind SpeedI3I III eph~~
~~. g. Wind Direction (4) (5)~~
~~(from) .~~
,s
h. Shutdown Time hr

1. Transport Distance for Calculation mi NOTES:
(1) If plant vent flow rate is unobtainable or cannot be estimated, assume 125,000 ef:n. (.21 If the (3 00 reading. C)-(33 If this ' *C) is unobtainable is unavailable to determine refer to Note 4. the at use the (15 0 ' 'C l - ( 3 3 ' ' C) (3) If the wind speed is unobtainable, assume 5 mph. Use Elevation 300' data for an elevated release. Use Elevation 33' data for a ground release. (4) Backup meteorological data from Wilmington Airport or NAWAS Line) including wind class speed, wind direction is not available, assume and an estimated conditions to be stability stable. class. If the estimated stability (5) 2f time permits average data over 15 minute period. PR VACY ACT INFORMATION O Page 6 of 21 Rev. 1 l
EP IV-111 A.2 PLANT RELEASE FROM UNIT NO. 2 (CONTINUED) ( FHOLE BODY DOSE RATE DUE TO N0 ELE GAS . 3 A.2.2 LOW RANGE QE DEFAULT VALUES (ATTACHMINT 4) Noble Gas (2R-41C) (Plant Vent Flow Rate) (Xu/Q) (Doso Conversion Factor) (3.15E-4) , mrer hr (Wind Speed) (a 1(b )(c ) (d )(3.15E-4) , mrem hr (e ) SE A.2.3 HIGH RANGE (R-43) Noble Gcs (R-43) (Plant Vent Flow Rate) (Xu/Q) (Dose Conversica Factor) (1.05E+3) , mrem (Wind Speed) (Concentration Conversion Factor) hr O (f (e
)(b ) (c ) (g )(d )(1.05E+3) , mrem ) hr NOTE
a. 2R-41C in cpm, or equivalent cpm value from Attachment 4.

b. Plant vent flow rate in ft / min.

c. Xu/Q value from Attachment 1. (1/m }

d. Dose conversion factor from Attachment 2. (****# #1 uCi/m

e. Wind speed in miles per hour.
E
f. R-43 reading in mR/hr.

g. Concentrationconversionfactorin"(("c## Attachment 3.
Date Time Calculated By Date Time Reviewed By i 2 l i I \ Page 7 of 21 Rev. 1
EP IV-lli A.2 PLAf4T RELEASE FROM UNIT NO. 2 (CONTINUED) ([]) THYROID DOSF C0KMITMENT DUE TO IODINE , A.2.4 DETERMINE THE RATE OF INCREASE OF IODINE ACTIVITY. a) Low Range Monitor 2R-41B tcpm , Cx-Co , ( )-( ) , ( ) cpm , g ) minE aman Tx-To ( )-( ) ( 1 min NOTE Refer to Step A.l.2(c). QR tl Using Default Values Use Attachment 4 to determine the appropriate equivalent epm / min. O g epm / min A.2.5 EQUATION FOR 50 YEAR DOSE COMMITMENT Iodine
,%1n cgm)(Plant Vent Flow Rate) (Xu/Q) (Dose Conversion Factor) (3.3SE-7) " *#**
~~(Wind Speed) (a )(b 1(c )(d 1(3.35E-7) = rem (e 1 NOTE~~
a. cpm / min *from Step A.2.4 (a or b).

b. Plant vent flow rate in ft / min.

c. Xu/Q from Attachment 1. (1/m )
~
~~d. Dose conversion factor from Attachment 2. (*#'" D#~~
~~uCi/m' )~~
~~e. Wind speed in miles per hour.~~
~~l Calculated By Date Time~~
)
Reviewed By Date Time Page 8 of 21 Rev. 1 l
EP IV-lli B. BELEASE RATE DETERMINATION FROM UNMONITORED STEAM PELEASE POINTS ({]) i B.1 IF CONTROL ROOM PERSONNEL HAVE DETERMINED A PRIMARY TO SECONDARY LEAK EXISTS IN CNE OR MORE STEAM GENERATORS BY ONE OR MORE OF THE FOLLOWING INDICATIONS: i a a) Air Ejector High Radiation Alarm 4 b) Uncontrolled increasing level in Steam Generator cl Increasing steam pressure in one Steam Generator d) High Activity alarm in the steen generator blowdown system with or without an isolation l
4 then the Senior Shift Supervisor shall initiate mcnitoring of the affected steam lines upstream of the isolation valves to estimate the microcurie content per cc of steam in the affected steam lines. This action is required if the potential exists for a
() relief valve lifting, a power operated relief being opened or the operation of the steam driven Aux. Feed pump attached to the affected Steam Generator (11 & 13) (21 & 231 l B.2 PRIOR TO RADIATION PROTECTION PERSONNEL ENTERING THE PENETRATION AREAS TO MEASURE THE I CONTACT DOSE RATE ON THE AFFECTED STEAM LINES, THE SENIOR SHIFT SUPERVISOR /EDO AND 1 THE SENIOR REPRESENTATIVE FROM RADIATION PROTECTION WILL EVALUATE AND DETERMINE THE POTENTIAL FOR HIGH RADI'ATION AREAS BEING ENCOUNTERED IN THE PENETRATION AREAS FOR THE FOLLOWING REASONS: i a) Reactor malfunction resulting in fuel damage I - 4 b) LOCA resulting in fission products being released to contairment resulting in i radiation streaming through containment penetration. B.3 IF ANY OF THE ABOVE CONDITIONS ARE PRESENT, SPECIFIC ACTION POINTS MUST BE ESTABLISHED IN ACCORDANCE WITH EP l-17 TO DETERMINE THE FOLLOWING REQUIREMENTS. i a) Total dose accumulation for operation Page 9 of 21 Rev. 1
l EP IV-lli l I l ( ]) B. RFLEASE RATE DETERMINATION FROM UN"0NITORED STEAP PELEASE POINTS (CONTINUED)
~~\ l b) Maximum dose rate field to enter .~~
c) The types of dosimeters and instruments to use d) The type of protective clothing and equipment to be used B.4 ENTER AFFECTED PENETRATION AREA OR LOCATION AND MEASURE THE CONTACT DOSE RATE ON THE AFFECTED STEAM LINE OR AUX. FEED PUMP EXHAUST LINE. a) The contact dose rate measurement can be made with any dose rate instrument having a range of 0.1 to at least 10,000 mR/hr. bl If it is expected that the background in the affected penetration area will be greater than 10 mR/hr a dose rate instrument with a shielded probe should be used. O Record the contact dose rate on pipe. c) mR/hr 3.5 USE THE CONTACT DOSE RATE CORRECTED FOR BACKGROUND RADIATION TO DETERMINE THE CONCENTRATION IN THE PIPE OF CONCERN FROM ATTACHMENT 6. I uCi/cc 3.6 USE THE FOLLOWING FLOW RATES TO DETERMINE STEAM RELEASE RATES: a) Power operated relief valve 450,000 lb/hr b) Relief Valve 800,000 lb/hr each Aux. Feed pump exhaust 50,000 lb/hr c) O Page 10 of 21 Rev. 1
~~. _l~~
EP IV-lli O B. RrlFASE RATE DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS (CONTINUED) B.7 MULTIPLY THE UCI/CC FROM B.5 AND THE PROPER FLOW RATE IN LB/HR FROM B.6 TO ' DETERMINE RELEASE RATE IN uCl/SEC. (uci/cc) (lb/hr) (3.3) = VCi/sec (a ) (b ) (3. 3) = uCi/sec
a. uCi/cc from Step B.5.

b. Ib/hr from Step B.6.
~~B.8 WHOLE BODY DOSE RATE DUE TO NOBLE GAS RELEASES mrem /hr = (t 01/ sectspeed (Wind (Xu/0)- (DCF) (2.22) El. 33')~~
~~) )(c )(2.22) mrem /hr = (a (d )~~
~~O -~~
~~a. WCi/sec from B.7.~~
2
b. Xu/Q in 1/m from Attachment 1.

c. Dose conversion factor from Attachment 2. ("#[)
~~pCi/m~~
~~d. Wind speed in miles per hour (El. 33').~~
B.9 DOCUMENT TOTAL NUNTIME FOR THE STEAM DRIVEN AUX. FEED PUMP. B.10 DOCUMENT THE TOTAL PERIOD OF TIME THE RELIEF AND POWER OPERATED RELIEF VALVES WERE OPEN ON THE AFFECTED STEAM GENERATOR. B.11 LIMIT THE NUMBER OF TIMES THE RELIEF AND power OPERATED RELIEF VALVES ARE OPEf! ON THE AFFECTED STEAM GENERATOR. B.12 IF LONG TERM OPERATIONS ARE REQUIRED FROM THE AFFECTED STEAM GENERATOR, PER!ODICALLY MONITOR THE STEAM LINES TO DETERMINE THE ACTIVITY IN THE AFFECTED SYSTEMS. Date Time calculated By i Date Time Reviewed By i Page 11 of 21 Rev. 1
EP IV-lli () C, PFLEASES FROM CONTAINPENT LEAKAGE NOTE , i This dose determination assumes a design basis containment leak rate (La). Actual containment leak rates may be more or less. This dose determination is a postulation and should be used as such. Field monitoring results are preferable. C.1 CONTACT THE CONTROL ROOM AND OBTAIN THE READING ON THE HIGH RANGE CONTAINMENT , RADIATION MONITOR 1E-21 (UNIT 1) OR 2R-21 (UNIT 2). R/hr C.2 USING ATTACHMENT NO. 5, CORRELATE THE METER AEADING TO THE VERTICAL AXIS AND DETERMINE THE BASE X/Q FROM THE HORIZONTAL AXIS. base X/Q
~~' C.3 DETERMINE THE ACTUAL Xu/0 USING ATTACHMENT 1.~~
actual xu/Q C.4 DETERMINE THE 24 HOUR DOSE. ( Actual xu/Q) (2. 22) = 24 hour dose in rem (Wind Speed - El. JJ')(Base X/Q) (a 1(2.22) (b ) (c j = rem NOTE
a. Actual Xu/Q from Attachment 1.

b. Windspeed in miles per hour (El. 33').

c. Base X/Q from Attachment 5 (correlated to containment monitor).
Date Time Calculated By Date Time Reviewed By Rev. 1 Page 12 of 21
EP IV-lll j NOTE ( Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments.
)
~~Prepared B' -~~
~~\ /'~~
~~Reviewed By: . A- -~~
~~/ OQ '~~
~~y' eMr ad [ Dat'e~~
~~A d Reviewed By:~~
Assisteht to Manager / Date P.eviewed By: JJ2 D2 . [b f I 3tation Quality Assufance Engineer Date
~~hl - [Il /8 7 /~~
~~SORC Meeting No.:~~
~~' Date Approved By: /!/~~
~~Managet - Salem Generating Station 'Dats Approved By:~~
~~d / I L-Manager - Emergency Preparedness Date~~
/
O. Page 13 of 21 Rev. I
EP IV-111 ATT. 1 ATTACHMENT 1 O Xu/0 VAUJE DETEPMINATION Select the Xu/Q values that correspond to the stability class as determined by the a temperature, distance from the site and the release point (ground or elevated).
~~1. USE THE a TEMPERATURE VALUE FROM THE METEOROLOGICAL TOWER TO DETERMINE STABILITY CLASS.~~
~~Primary Instrwnent l 300 ft. - 33 ft. temperature ('C) UNSTABLE NEUTRAL STABLE~~
~~-1.3 -0.5 i~~
~~Backup Instrument 150 ft. - 33 ft. temperature ('C) UNSTABLE NEUTRAL STABLE~~
~~-0.6 -0.2~~
~~2. DISTANCE (3ROUND LEVEL RELEASE (E-6/m ) ELEVATED LEVEL RELEASE (E-6/m )~~
METERS MILES titSTABLE NEUTRAL STABLE UNSTABLE NEUTRAL STABLE 1000 0.62 15 61.39 244.8 18.28 45.1 - 1270 MEA 0.79 9.95 41.5 227 12.4 42.2 - 2000 . l.2 4.64 22.49 168.0 6.13 27.99 .017 3000 1.9 2.32 12.20 113.3 3.12 17.26 .753 4000 2.5 1.42 7.86 81.7 1.92 11.72 3.54 5000 3.1 .968 5.58 62.3 1.31 8.55 7.22 6000 3.7 .708 4.21 49.5 .363 6.56 10.48 7000 4.4 .543 3.32 40.5 .740 5.23 12.81 8000 4.9 .432 2.70 34.0 .589 4.28 14.26 8045 LPZ 5. 0 .42 2.5 33.3 .57 4.06 14.3 9000 5.6 .353 2.25 29.0 .481 3.50 15.02 10000 6.2 .294 1.91 25.2 .402 3.06 15.29 11000 6.8 .250 1.65 22.1 .341 2.65 15.23 12000 7.5 . .215 1.44 19.6 .294 2.32 14.95 13000 8.1 .187 1.27 17.6 .256 2.05 14.55 14000 8.7 .165 1.13 15.9 .225 1.83 14.06 15000 9.3 .146 1.02 14.4 .200 1.65 13.54 16000 9.9 .131 .952 13.2 .179 1.49 13.01 MEA - Minimum Exclusion Area LPZ - Low Population Zone Distance -Xu/Q = E-6/m (ground) Xu/Q = E-6/m (elevated) O Page 14 of 21 Rev. 1
EP IV-lll ATT. 2 O ATTACHMENT 2 NOBLE GAS / IODINE DOSE CONVERSION FACTOR (K) VS. DECAY TIME A. Time from shutdown to time of release in hours = hr B. Time for transport = (Desired D'. stance) /(Wind Speed) ( mr)/( mph) = hr C. Total decay time = (Step A) + (Step B) ( )+( ) = hr D. Correlate the total decay time to the curves to determine the dose conversion factors for Noble Gas or Iodine as required. j NOBLE GAS DOSE CONVERSION FACTOR (K) VS. DECAY TIME O 0.o.
,_ L :! . i l 0.9 .i l g _
~~e*z 0.4 x K = (-40T + 520)/(1000)- imu5 z I. . ,~~
~~- 1\ : i.~~
~~3 n.J U {. . -i - h ;,; -~~
; i .N ; 0.2 .!. : .h L K=0.1 0.1 ~ ". ! ~ : "Dr i . a .. ..j. .; i. .
0 0 2 4 6 8 10 12 14 16 18 DECAY TIME (HOURS) O Page 15 of 21 Rev. 1
EP IV-lll ATT. 2 l O IODINE DOSE CONVERSION FACTOR VS. DECAY TIME (INHALATION DOSE TO CHILDS THYROID)
-- l 3000 - ;7 ; 7y ---- -- -- i . ~; 4 ,......
~~2900~~
'~~~" ! ; NORMALIZED TO 1 uCI/k3 1-131 2800 ; . ~
~~2700 j.~~
~~} l .l ! ;~~
~~l~'. -~~
~
~~2600 l~~
~~, ., . .i g p_..q ; . . ; . _ .. . .. ..~~
~~g e*r g 2500 i~~
~~; ;. x!N; ; ;~~
~~I 5 U 2400 5 N. , i X I ! 2200 . .~~
~~-: _ _ _ i -. . . _ .~~
2100 Q l- - - . . _ . . . . 2000 m ,
~~~ "~~
1300 O 10 20 30 40 50 60 DECAY TIME (HOURS) O l Page 16 of 21 Rev. 1
EP IV-lll ATT.- 3 O ATTACHMENT 3 R43 CALIBRATION FACTOR VS. DECAY TIME e u -- --
. , . .. ; r-_ - ..a.._.. . . _ . ...__a.._._.._.. .
~~40 ..a a~~
~~.. c... --~-~~
35
~~-. ._ ..s.; = 30 .. i 0g %~~
~~ipr ++Q . __ m.; := - -~~
~~- ' - - - - -=----- % 25 l :-~~~
~~lr Q 20~~
~~. .;;..l;i, . l " . . h =. , .p:1. +. . _ ..~~
i.
~~-+ '- - - - -~~
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~~n V~~
~~ . " =. ~~
~~10 .~~
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~~5 -~~
~~.=x.....= . - . ...=.~~
~~c. ; . : w : . . t .a . .r.._.. .~~
10 20 30 40 50 DECAY TIME (HOURS) fl0IE BASED UPON EPA-520/1-75-001; 3200 MW7g M M W . M .. . INGROWTH FROM PARENT ISOTOPES NOT INCLUDED. ; O 1 vv:n._.RSLrdL53 Rev. 1.
EP IV-111 ATT. 4 1 l ATTACHMENT 4 DEFAULT VALUES FOR LOV/HIGH PLANT VENT MONITORS . Read the below accident description and determine which case is applicable. From the table select the appropriate release rates (cpm). CASE I LOCA A LOCA assuming severe core damage - fuel melting (Regulatory Guide 1.4 assumptions) 100% of noble gases and 25% of the iodines contained in the core are assumed releas ' to the contain-ment. The containment initially leaks at the maximum design leak rate. CASE 11 LOCA Primary coolant leaks at a rate fast enough to increase the temperature of the core to the point where there is damage to the fuel rods. For this case, it is assumed that all the gap activity (the gases contained between the fuel and fuel rod) is released to the containment. The contain-ment is assumed to initially leak at the maximum design leak rate. In this accident, it is up to the Senior Shift Supervisor or Emergency Duty Officer (EDO) to assume that there has bee.. no tuel melting. If there is any cuestion, a Case I LOCA should be assumed. CASE III DECAY TANK RUPTURE n is unavailable for
~~\s l This procedure is used only if actual radiological monitoring equipment release evaluation (monitors out of service, read off scale, etc.).~~
CASE IV FUEL HANDLING ACCIDENT Any activity occurring as a result of a fuel handling accident is normally drawn into the Fuel Handling Building Ventilation System and vented to the plant vent for release. The process monitors are used to monitor these releases; however, should these monitors be out of service or off scale, this technique is used to evaluate off-site dose. CASE V STEAM GENERATOR TUEE RUPTUPE The activity released during a minor tube rupture can be determined using vent monitors and normal procedures. This procedure addresses the steam generator tube rupture as analyzed in the FSAR. This accident is set apart from others because of the inability to consult radiation monitors to determine the activity release rate. Therefore, this is the primary procedure to determine the activity release rate resulting from a steam generator tube rupture. EQUIVALENT GASEOUS EQUIVALENT ICDINE ACTIVITY INCREASE RATE ( CPM / MIN) l
~~/ ACCIDENT CLASS RELEASE RATE CPM I~~
l1I 2.42 E S 9.35 E 6 III 7.82 E 1.45 E - - II III l1I 1.25 E' ---- 4 1.22 E
~ IV II 9.9 E g4 3,3 gs N/ v(2) 1,, " (1) Use actual or estimated plant vent flow (cfm) as provided in the procedure.
~~(2) Case V is assumed not released through the plant vent so use a flow of 125,000 cfm for this calculation.~~
~~/Ng EP IV-111 ATT. 5 Q.~~
~~ATTACHMENT 5 CONTAINMENT MONITOR R-21 RESPONSE VS. DISPERSION FACTOR 107 :: t ,~~
. , i. ._o.._.....m.
_d as *
.*
T=" .m E* 4 ***
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10-3 10-2 10-5 10-4 DISPERSIONFACTOR(X/O-SEC/Mb c\ 0FF, SITE DOSE OF 1 REM IN 24 HOURS FOLLOWING A LOCA AS DETERMINED R-21 RESPONSE AND X/0.
EF IV-111 ATT. 6 O \ ATTACHMENT 6 SURVEY METER RESPONSE VS. PAIN STEAM LINE CONCENTRATION 0 10 1 102 10-3 10-2 10-1 10 105 i f
~~!.. . y . i i. 2 1 2-. '. i /--~~
~~1' - - -~~
~~. /=~~
~~. m . ; , . . -y~~
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4
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- I 10-1 s. - -
CONCENTRATION IN PAIN STEAM LINES q'v uC1/cc a 1005 PSIA *
*TO CONVERT TO uCrAs PULTIPLY BY 1.20E4 Page 20 of 21 Rev. 1
EP IV-111 ATT. 7 ATTACHNENT 7 O UNIT ANALYSIS OF 0FF-SITE DOSE CALCULATIONS l A.1.3 (epm * "Ci### )(ft . 2.032E4cc . I min _) ) mrem / ) 2.1E6 epm min ft 60 see a uCi/m = SE-4 O " (mph
~~ph )~~
i $ 3 A.1.4 (mr/hr)( 1 2.832E4cc . 1 min _){ )(mram/hr) min ft 60 see m VCi/m 1.05E3 (mph
U *

aph * "# *** ) ("# / h#WC1/cc)
I (g . uCi/cc )( . 2.832E4cc . I min )( )(arem/hr) A.1.6 60 see m uci/m min 3.0E9 epm / min min ft = 3.5E-7 (mph
~~45 sph "**)~~
O 2.832E4cc . 1 min ) )(mrem /hr) I A.2.2 (epm . uC1/cc )[ft 3.33E7 epm min 60 see a vCi/m l ft = 3.15E-5 U*** "
~~f (mph~~
~~ph ')~~
J .{ A.2.3 (mr/hr)( 2.832E4cc . 1 min )( )(mrem / ) , min ft 60 see m vCi/m = 1.05E3 (mph . o.4 sph 5 m/sec, # (mr/hr
~~;:C1/ce )~~
~~1 .~~
~~" "Ci/** t A.2.5 (*2"~~
~~3.13E9 epm / min min~~
)(ft3 . 2.832E4cc ft .60I min see m )( )(mrom/hr) uCi/m , 3,35g,7 min . (,,,, o..,aphm/s.c)
~~B.7 1. E4 e/ = 3.3 B.8 (b)(- )(mrem /hr)~~
, p - ci~ = 2.22 O (,,,. o.4s m,.ee) mph
! Rey, 1 Page 21 of 21
EP IV-113 EFERGENCY PROCEDUPE 4 O EP IV-113 i COMPUTERIZED DOSE CALCULATI0t!S ACTION LEVEL This procedure may be used in lieu of the manual doce calculation procedures. RESPONSIBLE INDIVIDUAL An individual f amiliar with the Nuclear Data 6620 system (normally the Shif t RPT) . ACTION STATEMENTS 1131 INIT1AL
~~1. Contact the Control Room and obtain the necessary information for the respective unit.~~
~~l Unit 1 Unit 2~~
~~) Wind Speed Wind Direction (from) .~~
~~Delta T'~~
' Elevated or Ground Release Time From Start of Incident (hours) 1R-12A 2R-41C Noble Gas Monitor High Range Gas Monitor R-43 R-43 ,
~~Initial epm from 1R-12B 2R-41B 1R-12B 2R-41B Final cpm from Time Between Readings on IR-12B 2R-41B l 1~~
~~2. Ensure a valid user is signed on the computer.~~
Type ins WHO (return) i O i Page 1 of 5 Rev. 1
_ _ _ _ - - . - - __ _ .. . = . . - = - _ - _ . - - .- - EP IV-113 i ACTION STATE!*ENTS (c0NTINUED)
~~O INITfAL M~~
~~e i~~
~~3. If the system indicates a user is signed on, proceed to Step 4. If the system responds with "NO USER SIGNED ON" type in:~~
~~HEL 10 (return) ,~~
~~4. Type in:~~
~~R BASIC (return)~~
~~5. Type in:~~
~~J OLD (return)~~
~~6. Type in~~
~~; DOSCAL.ALL (return)~~
~~7. Type in:~~
~~R3 (return) I~~
~~8. The program will respor d withs i ALL (TODAY'S DATE) MIDAS BASIC V01-01 THE FOLLOWING SUB-PROGRAMS ARE AVAILABLE TO YOU:~~
~~PRO. GRAM f PURPOSE eeeeeeeeeeeeeeeeeee...eeeeeeeeeeen~~
1. EFFLUENT DOSE CALCULATIONS

2. DOSE COMMITMENTS BASED ON W/B COUNTS

3. I-131 EQUIVALENCE CALC-USING GELI ANALYSIS

9. TO EXIT PROGRAM ENTER THE PROGRAM i YOU WISH TO RUN 0
ENTER 1 FOR EFFLUENT DOSE CALCUATIONS O Page 2 of 5 Rev. 1
EP IV=ll3 ACTION STATEMENTS (CONTINUED) O IN!TfAL IjfiE
~~9. Proceed to answer the questions with a carriage return after each entry.~~
The answers below are examples, use actual values. ' NOTE Operator entries are underlined. ENTER YOUR NAME (EXAMPLE: J. R. DOE): I i I JOHN R. DOE ENTER THE CURRENT TIME OF DAY (EXAMPLE: 2230): 7 9 2230 1 ENTER THE SALEM UNIT NUMBER (1 or 2): j T ?81 1 [V - ENTER THE WIND SPEED IN MPH (IF UNKNOWN ENTER 5) : l
~~?92 l~~
~~j ENTER THE WIND DIRECTION (IN DEGREES FROM):~~
? i 2M ENTER THE DELTA TEMP. (IF UNKNOWN ENTER 11 : ?91 IS THE RELEASE FROM PLANT VENT (ELEVATED) OR FROM THE GROUND 7 ENTER E FOR ELEVATED, OR G FOR GROUND: ?jE ENTER THE PLANT VENT FLOW RATE IN CPM (IF INOP USE 125000): ? I 65000 ENTER THE TIME IN HOURS SINCE SHUTDOWN:
79M Page 3 of 5 Rev. 1
EP IV-ll3 O action starter"Ts (c0Nr)~uro) IldE INITIAL N,EfE, If you wish to use the values for the five accident classes, enter 0 (zero) for the required meter readings. ,
~~ENTER THE CPM ON 1R-12A, IF OFF-SCALE OR INCP ENTER 0 (ZERO):~~
~~? 9 12000~~
~~ENTER THE INITIAL CPM FROM 1R-12B, IF INOP OR OFF-SCALE I .TER 0 (ZERO):~~
~~7 9 100 ENTER THE CURRENT CPM ON 1R-12B~~
? 9 10 ENTER THE TIME IN (MINS.) BETWEEN READINGS ON 1R-12B: ? 9 10 NOTE If 0 (zero) is entered for both low and high range gas monitors, the program will request default values based on the 5 accident categories. The 5 values will be printed out and you must enter the equivalent gaseous epm for the appropriate type accident.
NOTE If 0 (zero) is entered for the Iodine monitor, the program will request default values based on the 5 accident categories. The 5 values will be printed out and you must enter the equivalent epm / min for the appropriate type of accident. If 888 is entered for equivalent epm / min the program will calculate the Iodine activity on worst case of Iodine to Noble Gas satios. i
~~10. The program will then printout tn= rssults and return to step 8. You may run the program again or exit with the appropriate entry.~~
~~o Page 4 of 5 Rev. 1~~
~~' EP IV-ll3 O aCriON StartMtNTS ccourieuco) < Ilf,E INITIAL~~
11. Review the input data and the projected dose rates. Ensure that data is transmitted to the EDO (Control Room or TSC) as soon as possible.

12. As additional data is received, repeat this procedute to maintain the availability of current information.
COMMUNICATIONS NETWORK TSC CONTROL POINT CONTROL ROOM 1 CONTROL ROOM 2 SSS 200 611 633 641 635 201 623 642 DISCUSSION Rapid projected doses are essential for U.e EDO to make prompt protective action recommendations to off-site agencies. If the computer should fail, you should use the manual dose calculation procedures 15.12.318 or 15.12.319. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced c:zapleted EP's or attachments. Prepared By: //- /
~~, 7 a Reviewed By: i /[ hnt ead De art /O!E0!h/~~
~~Date V / Reviewed By: . . ( tant to Manager~~
/O!20!b/ ' Date Reviewed By: U Station Quality Assurance Engineer / D7M ' Date SORC Meeting No.: 8/- / / / Of 27 ! Tr' / ' Date Approved By: J w 3 Manager fSalani Generating Station ' / Data Approved By: . / M Manager - Emergency Preparedness Date l
i Page 5 of 5 Rev. 1
( EP IV-lls EMERGENCY PROCEDURE ({]) EP IV-115 i PERSONNEL AND VEHICLE SURVEY
/
ACTION LEVEL This procedure should be implemented whenever the normal contamination control program is inadequate due to any of the following: .
1. off-site release .

2. Excessive high background on-site

3. Whenever there is a reasonable possibility that contamination is going beyond the site boundary, i
~~RESPONSIRIE INDIVIDUAL This procedure may be initiated by any of the following:~~
~~1. Senior Shift Supervisor /EDO~~
~~() 2. Senior Supervisor of Radiation Protection~~
~~3. Shift Radiation Protection Technician .~~
~~Radiation Protection personnel under the direction of a Radiation Protection Technician will implement this procedure. LIMITS ON AUTHORITY~~
1. Non-station personnel cannot be forceably retained, nor can they be forced to submit to a personal survey.

2. Ensure that the Senior Shift Supervisor /EDO has previously approved surveying the public prior to initiating such actions.
~~ACTION STATEMENTS 11ME INITIAL~~
~~1. Obtain the necessary equipment to perform and document the required surveys.~~
O v l a) Countrate and dose rate meters l l r b) Radios Page 1 of 7 Rev. 1
EP IV-115 ecTION STATEMENTS (CONTINUED) . O INfTTAL 113E 4 c) Survey logs 1 d) Smears e) Protective clothing, if appropriate f) Spare batteries g) Head phones
~~2. Proceed to survey location and set up a means to:~~
~~J a) Identify contaminated items b) Document c) Segregate clean and contaminated materials J i~~
~~3. If necessary, obtain assistance from the police or Security Departments.~~
~~b I ( j 4. Perform the necessary surveys. I 5 a) Vehicle Surveys~~
1) Utilize the police or security for traffic control.

2) Document the license plate number of each vehicle surveyed. j

3) Depending on the time available, the following items are recommended for surveying (a) Tires i
(b) Hood i l l (c) Front grill / radiator Page 2 of 7 Rev. 1
EP IV-ll5 O ACTION STATEMENTS (CONTINUED) IlgE INfTIAL (d) Carburetot intake filter (e) Rubber bumpers
~~4) Vehicles may be released in accordance with Table I. If positive results are obtained, decon the vehicle or ask the occupants to use alternate modes of transportation.~~
~~NOTE Upon identifying the first contamination off-site, ensure the Senior Shift Supervisor /EDO is notified, e- b) Personnel Surveys~~
1) If possible, use earphones and hold the meter face away from the individual to avoid unnecessary anxiety.

2) Record the name, date and time of each individual surveyed along with the survey results.

3) The following locations of the body are recommended check points:
~~(a) Top of head and hair (b) Shoulders (c) Hands (d) Knees (e) Feet~~
}
~~4) Individuals may be released in accordance with Table I.~~
Page 3 of 7 Rev. 1
E1 IV-115 i n ts ,) $CTION STATEPEtiTS (cONTIhUED) IlgE INfTfAL
~~5) Contaminated personnel should be asked to allow decontaminaa tion to be performad (see the personnel decontaminatica procedure for in6tructions).~~
~~NOTE Ensure the Senior Shift Supervisor /EDO is contacted when the first contamination is found off_ site.~~
~~i 5. Return any collected contaninated material to the site for proper disposal.~~
~~6. Survey yourself and any personnel assisting you prior to releasing all personnel.~~
ATTACHf*ENTS Personnel and Vehicle Survey Log i COWUtllCATIONS NETWORK TSC CONTROL ROOM 1 CONTROL ROOM 2 SSS CONTROL POINT MAIN GATE 200 633 641 635 611 500 201 Radio 600 Radio Radio NOTE Forward all completed formd to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. DISCUSS 10i1 In the event of an emergency, normal access control procedures may be inadequate. A special survey point (s) may be required to identify, isolate and contain contamination from the plant. () ..___....._____. ..______..___..........__________..________ ___. ..__...___.__.__ __...._..___. Page 4 of 7 Rev. 1
l EP IV-ll5 j l O - Prepared By: ' {
~~/ \/ v .~~
Reviewed By: [ /O! d b ! Y/ Dep6rtM tI ad Date Reviewed By: /Of 2(a!I/ s &nt. to Manager ' Date Reviewed By: - h Ox _ 7
~~'Date h~~
~~Eation Quality Assurance Enginuwe SCRC Meeting No. -_ b [ "._/ / [~~
~~/O!d7!I/ , p g,g .~~
Approved By: /c 7, ///_7/ Manager - Sflem A nerating Station / Dater Approved By * - (j d A LA'B l b [ I!1/ 8P Manager - Daergency Preparedness ' Date O . l l O Page 5 of 7 Rey. 1
_ _ = . - . - , - - - . . .- EP IV-Il$ TABLE I Q TABLE I PERSONNEL AND VEHICLE RELEASE LIMITS EXTREME EMERGENCY II NORMAL RELEASE LIMITS WITH EDO PERMISSION ( ' 2 2 2 DPM/100 CM DPM/100 CM DPM/100 CM 10 alpha 20 alpha 500 beta-gama 1,000 beta-gamma 10,000 beta-gamma r NOTES: (1) Limits can be used to release personnel and personnel vehicles with the Emergency Duty Officer's parmission. (2) Extreme emergency limit can be used when the EDO determines the situation dictates this I to be the best course of action, e.g. clean-up would involve a potentially higher risk or a high population density of construction workers. O l O V l l l Page 6 of 7 Rev. 1
I EP IV-115 ATT. 1 ATTACHPENT 1 O VEHICLE AND PERSONNEL SURVEY FORM NAME DATE CONTAMINATION FIXED DCSE OR ( ) RATE TECH. 2 LICENSE TIME DPM/100 CM mr/hr ACTION SIGNATURE 4 )
~~. I 1~~
l! ) i s O r 4 . O Page 7 of 7 Rev. 1 l
EP IV-116
~'s EP.ERGENCY PROCEDURE U EP IV-116 FIRE BRIGADE ESCORT ACTION LEVEL A Radiation Protection Technician shall escort all Fire Brigades whenever there is a fire in the Controlled Access Area. ,
RESPONSIBLE INDIVIDUAL The Radiation Protection Technician assigned to escort the Fire Brigade. LIMIT ON AUTHORITY Any entry into an evacuated area must have prior Senior shift Supervisor /EDO approval. 6CTION STATEMENTS IlgE INITfAL () 1. Upon receipt of a valid fire alarm in the Auxiliary Building or other radiological significant area, a Control Point Rad Protection Technician shall don a SCBA and obtain a dose rate instrument and a lapel air sampler.
2. Escort the Fire Brigade to the location of the alarm (continuously monitor the radiation levels).

3. Ensure all members utilize the SCBA as soon as significant smoke is encountered.
~~I 4. Upon verification that a fire is in progress, page for additional l assistance and air sampling equipment.~~
5. Escort the Fire Brigade into any radiation areas to establish dose rates and stay times. Keep the exposure as low as practicable. Fire Brigade members may be allowed to receive up to 75 rems to save a life, but otherwise are limited to 2.5 rems except as authorized in EP IV-106.

6. When possible obtain an air sample for subsequent analysis.
Page 1 of 3 Rev. 1 j l
EP IV-116 ACTION STATEMENTS (CONTINUED) TIME INITIAL
7. Set up contamination control barricades as needed to allo *r Fire Brigade free access to/from the fire zone and their equipment.

8. Calculate and record all personnel exposures.

9. Obtain comprehensive surveys to determine the extent of contamination.

10. If necessary, obtain whole body counts of personnel exposed to significant airborne contamination.
COMMUNICATIONS NET'JORK TSC CONTROL POINT CONTROL ROOM 1 CONTROL ROOM 2 SSS RP OFFICE 200 295 633 641 635 642 201 611 Page Page Page 623 Page Page 644 O Page DISCUSSION Fires in contaminated areas create a significant potential for airborne contaminents in addition to the normal fire hazards. The proper use of air packs (DO NOT USE STANDARD FACE MASK WITH CARTRIDGE) will prevent this internal exposure to hazardous chemicals and airborne contaminents. If off-site Fire Departments respond to the fire, they will recuire extra assistance and monitoring due to their lack of familiarity with Radiation controls. The Main Gate (Security) is responsible for contacting Radiation Protection for the off-site fire squads. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced ccmpleted EP's or attachments.
~~.___.__._________..___.._______...__...._____.--- .== .__.___.__..__ ..___.... ..=== -~~
~~l l l Page 2 of 3 Rev. 1~~
~~. EP IV-ll6 O~~
~~Prepared By _ l~~
~~) =~~
l Reviewed By: ( / O! Z b [ Depart hent _ ead ' Date Reviewed By: / O!2 b !k / ant to Manager Date , Reviewed By: . uh ! N Schtion Quality Assurance Engineer Date SORC Meeting No.: @l- /// /0[Z 7h/
'Date' Approved By: // '/Datn Manager 'Saleaf Genefating Station Approved By: . - l 21 V Manager - Elmergency Preparedness Date O
l O l Page 3 of 3 Rev. 1
l EP IV-117 l l EMERGENCY PROCEDURE (]) EP IV-117 RE-ENTRY TEAM RADIATION PROTECTION ACTION LEVEL Whenever personnel are required to enter any area previously evacuated due to adverse radio-logical conditions. . RESPONSIBLE INDIVIDUAL
1. This procedure may be initiated by a) Senior Shif t Supervisor /EDO b) Senior Supervisor of Radiation Protection On-Site c) OSC Coordinator

2. The Team Leacer shall implement this procedure.
LIMITS ON AUTHORITY Any re-entry into evacuated areas shall have Senior Shift Supervisor /EDO approval. All radiation exposures to personnel in excess of 2.5 rams whole body per quarter require an Emergency Exposure Authorization as per EP IV-106. All radiation exposures in excess of 3 rems whole body per quarter shall be incurred by volunteers only. The recommended upper limits for emergency exposures to volunteers are 75 rems whole body to save a life and 25 rems whole body to accomplish critical work. These exposures shall be once in a lifetime. Criteria for planning mission where exposures may exceed 3 rems whole body are as follows: Life Saving: 75 rems Non-Life Saving: 25 rems Any and all actions necessary to save or Repair or operation of equipment preserve life including, but not limited necessary to mitigate which has or may to: have the potentici to cause off-site doses would would require protective Removal of injured actions. First Aid Personnel decontamination Corrective actions necessary to prevent Ambulance services further deterioration or to effect Medical services significant improvement in plant safety status. O Corrective actions necessary to cause significant improvement in plant safety status. Page 1 of 5 Rev. 1
EP IV-ll7 ( ACTION STATEMENTS M INITIAL
~~1. The initiating individual shall notify the Senior Shift Supervisor /EDO and Radiation Protection of the re-entry requirements. Specify the following:~~
a) Where b) Reason and objective c) Relative importance of the re-entry j l d) Who's going e) When f) Any information relative to the conditions that may be encountered (i.e.; steam leaks, water, no lights, high radiation alarms, etc.) g) Estimated radiation levels to be encountered, including estimated stay time and integrated dose
~~2. The Senior Shift Supervisor /EDO or the OSC Coordinator shall assemble a team and designate a Team Leader. Clearly define the role of each member on the team.~~
~~a) Leader b) Individual keeping track of accumulated exposures c) - First aid representative d) Repairman or equipment operator~~
~~3. The Team Leader shall assure that the following items have been obtained, performed or considered, as appropriate:~~
a) Backup Instrumentation O b) Hi-Range Dosimetry Page 2 of 5 Rev. 1
EP IV-117
/) ACTION STATEMENTS (c0NTINUED) l 1151 INITIAL c) Check the ARM readouts in the Control Room d) Utilize personnel familiar with the areas to be entered e) Utilize personnel with low exposures f) Use respirators or SCBA g) Use stable Iodine h) Lapel air sampler
1) Stretcher or first aid supplies j) Portable lights k) Two-way radios

1) Keys or bolt cutters

4. The Radiation Protection representative shall assure that step-off pads and other contamination control equipment are in place.

5. Specific operations shall be conducted in accordance with specific procedures as follows:
a) EP I-6, " Radioactive Spill" b) EP I-7, " Station Fire" c) EP I-9, " Search and Rescue Operations" d) EP I-14, " Initiation of Recovery Operations" i l e) EP I-17, " Radiation Protection - Emergency Actions" J
)
~~6. The Senior Shift Supervisor /EDO shall determine need for thyroid blocking in accordance with EP I-15, " Stable Iodine Thyroid Blocking".~~
Page 3 of 5 Rev. 1
EP IV-ll7 O 8CTION STATEMENTS (CONTINUED) TIME INITfAL
~~7. The Team Leader shall maintain communications with the Senior Shift Supervisor and/or the OSC Coordinator. Two-way radios shall be used on all missions into hazardous areas or locations.~~
~~B. The Radiation Protection represer.tative shall document any survey results.~~
9. The Team Leader shall notify the TSC and the appropriate supervisor of any important observations.

10. The Radiation Protection representative shall document the accumulated exposures.

11. A formal debriefing shall be conducted by the Dose Assessment /ALARA
() Supervisor following each re-entry into previously unsurveyed areas. COMMUNICATIONS NETWORK TSC CONTROL ROOMS CONTROL POINT RADIATION PROTECTION OF/ ICE Page Page Page 130 200 633 611 642 635 644 641 NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. O l l' Ppge 4 of 5 Rev. 1 l
. EP IV-117 Prepared By: h 8' Reviewed By: I b par ~
d_ / D te ' Reviewed By: Assistant to Manager # Date Reviewed By: h . ! ) C"atab UnaI1ty' Assurance Enganeer 'Date soRc neeting so. 8I- III / o/z 7 /P/
~~/ Date' Approved By: /// k Manager - dalem Generating Station ' 5 ate '~~
~~Approved By: 4~~
~~_D Ol f, MI N Manager - E:nergency Preparedness 'Date O~~
~~O Page 5 of 5 Rev. 1~~
~~- ~ ..~~
EP IV-ll8 i EMERGENCY PROCEDURE ([]) EP IV-118 HIGH ACTIVITY SAMPLE ANALYSIS ACTION LEVEL Any requirement to analyze a sample which has an exposure rate of 20 mR/hr at a distance of 8 inches. (Refer to EP IV-301 or EP IV-302, as appropriate.) .
~
FESPONSIELE INDIVIDUAL A Technical Supervisor of Radiation Protection or Chemistry shall be responsible for implementing this procedure. LIMITS ON AUTHORITY Prior to proceeding with high activity sample analysis, dose estimates shall be evaluated. Approval of the Senior Shift Supervisor /EDO is required prior to analysis of any samples that may result in exposures in excess of 10CFR20.101 limits. ACTION STATEMENTS Ildg INITIAL
1. Evaluate the analysis request for relative priority. If a result is f not essential, consider its postponement until backup instrumentation arrives.

2. Notify the Chemistry or Radiation Protection Counting Rooms that a high activity sample is to be analyzed.
NOTE i Normally, the Chemistry Counting Room would be designated the " hot" lab. In the event of an accident, the Radiation Protection Counting Room is more likely to retain a low background. Inform requestors where to deliver samples. A separate procedure shall be used for sample collection and handling until it is delivered to the appropriate counting facility. 1 O Page 1 of 6 Rev. 1
EP IV-118 []} ACTION STATEMENTS (CONTINUED) ligE INITIAL
~~3. Determine sample quantities awaiting analysis and consider establishing relative priorities for each before the backlog gets excessive.~~
~~Samples and data for evaluating Protective Action Guides should get the highest priority. ,~~
4. Ensure designated counting lab is prepared for sample arrival and don protective clothing, which, at a minimum, shall consist of lab coat and either one pair of rubber or two pairs of Latex (Surgeon's) gloves.

5. Ensure extremity TLD'S are properly worn as required by REP instructions.

6. On receipt, survey the sample (preferably with a Teletector) and store in lead pigs, if available, apart from occupied areas, for exposure reduction.
O 7. Record survey data on Attachment 1 and calculate dose estimates for extremity using contact gamma dose rate and use general area radiation levels for whole body dose estimates. When calculating dose estimates, approximate times for sample analysis are fif teen (15) minutes for the first sample and six (6) minutes for successive samples. Calculate dose estimates on Attachment 1.
8. Handle all samples with tongs or tweezers.

9. Continue monitoring background radiation levels for marked increases.

10. Continue to monitor your exposure. Use pocket dosimeters and calcula-tions and continue updating exposure status. If doses exceed or are likely to exceed previous determined limits contact the Dose Assessment /
ALARA Supervisor (located at the TSC, Ext. 200, 201). O Page 2 of 6 Rev. 1
EP IV-ll8 p/ v ACTION STATEMEHIS (CONTINUED) 11gE INITfAL
~~11. Sample Reduction (to obtain samples of 20 mR/hr at 8 inches fer GeLi Analysis) :~~
i a) Divide 20 mr/hr by the gamma dose rate at 8 inches to get reduction factors, e.g., 20 mr/hr 1 500 mr/hr " II and multiply the sample weight by the reduction factor to got maximum desirable portion of sample. For example, if the above sample weight is 50 grams, hX50 grams =2 grams you will have to use no more than 2 grams of the sample for ultimate counting. This ensures dead time losses of less than O 10% for samples counted at 8" from the detector. b) Iodine Filters Work in vented, filtered hood. Place clean paper on scale for each weighing operation. Determine desired fraction and weight of portion of original sample and separate from balance of filter contents. Remove a similar amount of sample media in a plastic bag. To this bag, add the portion of the sample, twist and seal, and shake. Return contents to (or place bag and contents into) an unused container and tape. Discard remaining sample media and canister into radioactive waste. What remains is a diluted sample in identical geometry to the original. Seal in bag or saran wrap. Proceed with standard laboratory counting methods and ensure you account for lost counts from sample reduction and dead time. O Page 3 of 6 Rev. 1
EP tv-ll8 (] ACTION STATEMENTS (CONTINUED) 11gE INITIAL
~~c. Particulate Filter Work in a vented, filtered hood. Place clean paper on scale for each ,~~
weighing operation. Determine what portion of the sample is to be used as per section "a" and cut out a slice (like a pie slice). Seal in plastic bag or saran wrap and count. Proceed with standard laboratory methods and ensure that you account for lost counts from sample reduction and dead time. i
~~12. Lead filters of various thicknesses may be used in lieu of sample reduction to reduce the instrument dead time to an acceptable level~~
~~(>10%).~~
~~13. Report results to requestor and the Dosc Assessment /ALARA Supervisor.~~
~~O 14. Keep track of your exposure. l l~~
~~15. Monitor lab for contamination and airborne radioactivity. Decon as necessary.~~
l ATTACHMENTS Dose Assessment / Sample Size Peduction Worksheet COMMUNICATIONS NETWORK Dose Assessment /ALARA Supervisor (TSC) Chemistry Lab Radiation Pr3toction Lab 200 616 612 201 Page NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. Page 4 of 6 Rev. 1
EP IV-llB O / Prepared By: _ M Reviewed By: [ De a en esd I Date' Reviewed By: '
~~/ /~~
~~As tant to Manager ' Date , Reviewed By: >0 - a 7tafson Quality Assurance Engineer~~
~~/O/v7 Wate ~~~
~~Tl SCRC Meeting No.: bf~ f[l / O!d 7 !b/ .*A~~
~~' Date' Approved By: /~~
~~Managet - Salem Generating Station~~
~~//Date Approved By: +~~
~~Oh I Y Manager - Emergency Preparedness Date O~~
4 O 4 Page 5 of 6 Rev. 1
EP IV-118 i o ATTACHMENT 1 i d DOSE EVALUATION AND SAMPLE SIZE PEDUCTION WORKSHEET
1. DATE TIME l

2. SAMPLE INFO: (a) LOCATION 4
~~(b) LOCATION (c) LOCATION (d) LOCATION (e) LOCATION~~
~~3. PREVIOUS EXPCSURE DATA QUARTER TO DATE NAME/SSt WHOLE BODY EXTREMITY a.~~
~~b. c. d.~~
4. Use a dose limit of 1000 mram whole body or 10,000 mrem extremity. If you anticipate exceeding these, contact the Dose Assessmtnt/ALARA Supervisor at the TSC. If you anticipate exceeding 1500 mram.whole body or 15,000 mrem extremity, obtain permission of the Dose Assessment /ALARA Supervisor and the Senior Shift Supervisor /EDO.

5. Estimate time requirad to get results (e.g.15 minutes for first sample, 6 minutes for each
; successive one) and doses SAMPLE GENERAL AREA MR/HR X TIME = W/B DOSE CONTACT MR/HR X TIME = EXTREMITY DOSE A (1/4) (1/4)
B (1/10) (1/10) C (1/10) (1/10) D (1/101 (1/10)
~~6. Calculate Sample Reduction Factor~~
~~" = R.F. R.F. X WEIGHT = REQUIRED PORTION OF SAMPLE jh 8 ,,~~
~~A. B. C. l l D. 4~~
O
~~\s Page 6 of 6 Rev. 1~~
EP IV-119 EMERGENCY PROCEDURE EP IV-119 () PERSONNEL DECONTAMINATION ACTION LEVEL Whenever personnel are found to be contaminated during a declared emergency. RESPONSIBLEINDIVIDUAL . Any designated Radiation Protection Technical Supervisor or Radiation Protection Technician. LIMITS ON AUTHORITY Decontamination efforts by Radiation Protection personnel are lLaited to external surface of the body. NOTE In cases involving transport of a contaminated person off-site, the Shift RPT should arrange for a member of the R=diation Protection Department to escort the victim off-site. The escort shall carry the appropriate survey equipment. O k> BCTION STATEMENTS 1 11gE INITIAL
1. Determine if victim's life is threatened and if so, contact the Senior Shift Supervisor /EDO to arrange for transportation to Salem County Memorial Hospital.

2. First aid efforts take precedence over decontamination efforts unless the contaminant itself is life threatening. High beta dose to the skin j is.very serious radioactive materials can be absorbed through the skin.

3. Survey victim. Check for severe injury: compound fractures, chest or abdominal wounds, severe bleeding, suspected head injury or back injury or unconscisusness require special precautions and have highest priorities. If contaminated, severely injured and in high radiation field, remove from field if possible, cover wounds to avoid contamination, cut clothes off (often reduces significant amounts of radiation) and keep warm to prevent shock. If seierely bleeding, apply
() pressure to wound with as sterile a dressing as possible. Proceed with non-abrasive decon methods and wash with mild soap and lukewarm water on a damp cloth. Do not excessively disturb wound areas. Page 1 of 7 Rev. 1 l
i i EP IV-119 ACTION STATEMENTS (CONTINUED) [) nn JamAL
4. If vict's is not injured, have him remove clothes and take a shower with lukewarm water only and soap.

5. Follow-up on all injuries to ensure adequate treatment has been provided.

6. Review Attachment 1 for alternative decon methods.

7. After successful decontamination, site personnel shall be bioassayed by any standard method.

8. Obtain names, addresses and telephone numbers of all members of the general public who have been decontaminated for follow-up.
O 9. The Dose Assessment ALARA Supervisor shall calculate the dose commit-ment and report accordingly to the Senior Supervisor / Radiation Protection, the Senior Shif t Supervisor /EDO.
10. In any overexposures, the NRC shall be promptly notified.

11. Contaminated decontamination materials shall either be decenned, stored or disposed of properly.

12. Document all cases of personnel contamination greater than 10,000 DPM/100 cm2 smearable or 0.1 mr/hr fixed.
NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. i O Page 2 of 7 Rev. 1
EP IV 119 j ATTACHMENTS O 1. Personnel Decontamination COMMUNICATIONS NETWORK First Aid Control Point E 605 611 Salem County Memorial Hospital 200 6u =
~~"' PR VACY ACT .~~
DISCUSSION IN:0RMA10h Inunediate conditions. threatening attention nrust be given to contaminated and/or injured victims with severe or life High dose rates and possibility of internal absorption through the skin or into open wounds will be present when gross contamination is present. M Prepared B p , Reviewed By: O - partien Me /o[2 G[ P/ Date Reviewed By: Ass tan to Manager /0[Z6[PI Date Reviewed By: . A M _ N k Ma C wiQdality Assurance Engineer Date SORC Meeting No.: b[- I[I /0/77!b/ Date Approved By: Managezr- SM em Generating Station /[/ M
~~/ /Untd Approved By: -~~
~~24A Manager - Einergency Preparedness~~
~~/ Al V Date O~~
Page 3 of 7 fra R
w O O O PERSONNEL DECCNTAMINATION METHOD
SURFACE ACTION TECHNIQUE ADVANTAGES DISADVANTAOES Soap and water Skin and hands Emulsifies and Wash 2-3 minutes and Readily available Continued washing dissolves monitor. Do not and effective for will defat the skin.
contaminate. wash more than 3-4 most radioactive Indiscriminate times. contamination. washing of other than affected parts may spread contami-nation. Soap and water Hair Same as above. Wash several times. If contamination is not lowered to acceptable levels, shave the head and apply skin decontamination methods. m
$u Lava soap, soft Skin and hands Emulsifies, Use light pressure Same as above. Continued washing brush and water dissolves, and with heavy lather. will abrade the a erodes. Wash for 2 minutes, skin.
o 3 times. Rinse and m monitor. Use care
~~-4 not to scratch or erode the skin.~~
Apply lanolin or hand cream to prevent chapping. Tide or other Same as above. Same as above. Make into a paste. Slightly more Will defat and detergent (plain) Use with additional effective than abrade skin and water with a mild washing with soap. must be used with scrubbing action. care. Use care not to erode the skin. Mixture of 50% Tide Skin and hands Emulsifies, Make into a paste. Slightly more Will defat and and 50% cornmeal dissolves, and Use with additional effective than abrade skin and erodes, water with a mild warhing with water. must be used with scrubbing action. care. Use care not to erode the skin.
*BEGIN WITil Tile FIRST LISTED METilOD AND TI EN PROCEED STEP BY STEP TO THE MORE SEVERE METHODS, AS NECESSARY. Q N
n :.
. 0
~~= . . . . . . . . . . . . . . . . . . . . . . _ . _ . _ .~~
O O O PERSONNEL DECONTAMINATION METHOD
~~SURFACE ACTION TECHNIQUE ADVANTAGES DISADVANTAGES __~~
5% water solution of Skin and hands Emulsifies, Use with water. Rub Slightly more Will defat and a mixture of 30% dissolves, and for a minute and effective than abrade skin and Tide, 65% Calgon, St erodes. rinse, washing with soap. must be used with Carbose care. (carboxymethyl cellulose) A preparation of 86 Same as above. Same as above. Use with additional Same as above. Same as above. Carbose, 34 Tide, it water. Rub for 1 Versene, and 884 minute and wipe off. water homogenized Follow with lanolin into a cream. or hand cream. Titanium dioxide Skin, hands, and Same as above. Work the paste into Removes contami- If left on too long paste. Prepare extremities. Do not the affected area nation lodged under will remove skin. paste by mixing use near face or for 2 minutes, scaly surface of precipitated other body openings. Rinse and wash with skin. Good for 3 soap and warm water, heavy surface s titanium dioxide (a n ' ".o r , contamination of l u very thick slurry, l ui never permitted to skin. l o dry) with a small
~~amount of lanolin.~~
~~-a If not successful, go on to next step.~~
Mix equal volumes of Same as above. Dissolves contami- Pour over wet hands, Superior for skir. Will remove a layer a saturated solution nant absorbed in the rubbing the surface contamination. May of skin if in of potassium epidermis. and using hand brush be used in contact with the permanganate and 0.2 for not more than 2 conjunction with skin for more than N sulfuric acid. minutes. Rinse with titanium oxide. 2 minutes. (Saturated solution water. of KHnO, is 6.4 grams per 100 ml of Hy O.) Continue with next step. Skin, hands, and Removes the per- Apply in same manner Will remove a layer Apply a freshly prepared St solution extremities. Do not manganate stain. as above. Apply for of skin if in of sodium acid use near face or not more than 2 contact with the sulfite. (Solution other body openings. minutes. The above skin for more than made by dissolving procedure may be 2 minutes. 5 ga of NaHSO repeated. Apply y crystals in ido al lanolin or hand y distilled water.) cream when completed. y *BEGIN WITH THE FIRST LISTED METHOD AND THEN PROCEED STEP BY STEP TO THE MORE SEVERE METHODS, AS NECESSARY. 4 4 0
O o o PERSONNEL DECONTAMINATION SURFACE ACTION TECHNIQUE ADVANTAGES DISADVANTAGES METHOD
Flushing Eyes, ears, nose, Physical removal by Poll back the eyelid If used immediately When using for nose and mouth. flushing. as far as possible, will remove contami- and mouth, contami-flush with large nation. May also be nated individual amounts of water, used for ears, nose, should be warned If isotonic and throat. not to swallow the 1rrigants are avail- rinses.
j able, obtain them without delay. Apply to eye continually and then flush with large amounts of water. (Isotonic irrigant [0.9tNaCl solution]: 9 grams Nacl in beaker, fill to 1000 cc with water.) Can w be purchased from drug suppliers, etc. u e Further decontamina-o tion should be doa.c m under medical super-w vision. Flushing Wounds Physical removal by Wash wound with Quick and efficient May spread contami-flushing. 3arge amounts of if wound not severe. nation to other water and spread areas of body if edges to stimulate not done carefully. bleeding, if not profuse. If profuse stop bleeding first, clean edges of wound bandage, and if any contamination remains, it may be removed by normal cleaning methods, as above.
*BEGIN WITH THE FIRST LISTED METHOD AND THEN PROCEED STEP BY STEP TO THE MORE SEVERE METHODS, AS NECESSARY.
~~U M N $:~~
~~? e s~~
~~~N O)~~
~~PERSONNEL DECONTAMINATION METHOD~~
SURFACE ACTION TECHNIQUE ADVANTAGES DISADVANTAGES Sweating Skin of hands and Physical removal by Place hand or foot cleansing action is If glove or booty feet. sweating. In plastic glove or from inside out. is not removed booty. Tape shut. Hand does not dry shortly af ter pro-Place near source out. fuse sweating of heat for 10-15 starts and part minutes or until washed with soap hand or foot is and water sweating profusely. immediately, Remove glove and contamination may then wash using seep into the pores.
~~standard techniques. Or gloves can be worn for several hours using only body heat.~~
*BEGIN WITH THE FIRST LISTED METHOD AND THEN PROCEED STEP BY STEP TO THE MORE SEVERE METHODS, AS NECESSARY.
~~N e w 4 O es 4 2 w :.~~
?
EP IV-120 i EMERGENCY PROCEDUP.E EP IV-120 O EQUIPF.ENT DECONTAMINATION ACTION LEVEL When equipment, vehicles or structures exceed the limits as found in Table 1 of this procedure. BESPONSIBLE INDIVIDUAL This procedure may be initiated by any of the following:
1. Senior Shift Supervisor /EDO

2. Senior Supervisor of Radiation Protection

3. Shift Radiation Protection Technician Radiation Protection persor'el under the direction of a Radiation Protection Technician will implement this procedure.
~~LIMITS ON AUTHORITY () 1. Non-station personnel cannot be forceably retained, nor can they be forced to submit to a personal survey.~~
~~2. Ensure that the Senior Shift Supervisor /EDO has previously approved surveying the public prior to initiating such actions.~~
~~ACTION STATEMENTS IldE INITIAL~~
~~1. Set-up an area to facilitate the following:~~
~~a) . Clean Area b) Contaminated Area~~
1) Low level contamination

2) High level contamination c) Step Off Pads d) Receptacles for contaminated b
~~\/ 1) Decon fluids (55 gal. drums)~~
2) Solid Rad Waste

3) Protective Clothing Page 1 of 7 Rev. 1
~~EP IV-120 l l ACTION STATEMENTS (CONTINUED) M INITIAL e) Ensure proper posting is in place~~
1) Rad /High Rad Area

2) Rad Material Area

3) contaminated Area ,

2. Perform initial surveys on incoming contaminated materials. Adjust the protective clothing requirements as necessary to ensure worker safety. If necessary, segregate the materials into areas reflecting the level of contamination.

3. Ensure the personnel transferring the contaminated materials perform adequate personnel surveys prior to leaving area.

4. See Attachment 1, " Area and Material Decontamination", for recommended methods of decon.

5. Large numbers of vehicles may require utilization of fire hoses. If so, locate decon area where drainage will collect in a low area and barricade area.

6. Perform frequent operability checks on instrumentation.

7. Perform frequent contamination control surveys of the work area and Step Off Pads.

8. Perform frequent surveys on waste receptacles to avoid unnecessary exposure to accumulated waste.
ATTACHMENTS Area and Material Dacontamination . COMMUNICATIONS NETWORK CONTROL POINT TSC CONTRCLS ROOMS SSS MAIN GATE 611 642 200 633 635 500 623 644 201 641 600 NOTE Forward all completed foms to the Assistant to Manager (SGS). v Attach any referenced completed EP's or attachments. l l Page 2 of 7 Rev. 1
EP IV-120 p) DISCUSSION l Tools and emergency equipment may become contaminated in an emergency. Control of these items is essential to prevent off-site release of the contamination. Large scale decori of items like I vehicles must be done with the materials at hand (fire hoses, water hoses, etc.) depending on resources and time available. ; i TABLE I I EQUIPMENT DECONTAMINATION NORMAL RELEASE LIMITS WITH EDO PERMISSION (l) EXTREME EMERGENCY DPM/100 CM DPM/100 CM DPM/100 CM 10 alpha 20 alpha 500 beta-gamma 1,000 beta-gamma 10,000 beta-gamma NOTES: (1) Limits can be used to release essential equipment with the Emergency Duty Officer's permission. (2) Extreme emergency limit can be used when the EDO determines the situation dictates this to be the best course of action. Os Prepared B' Reviewed By: _N ! Irt e H e -' iDate Reviewed By: tant to Manager
~~! ' Date Reviewed By:~~
~~Station Quality Assurance Engineer [ M ' Date' SORC Meeting No. bI~ ll l O !2 7 /~~
~~' Dath Approved By: / b Manager # Salem Generating Station Date Approved By:~~
~~4/M4 / N M Manager - Emergency Preparedness ' Date v~~
Page 3 of 7 Rev. 1
m U (n) V,m ATTACPJ'ENT 1 AREA AND tiATERIAL DEEONTAMINATION NET HOD
SURFACE ACTION TECilNIQUE ADVANTAGES DISADVANTAGES Vacuum Cleaning Dry surfaces Removes contaminated Use conventional vacuum Good on dry, porous All dust must be dust by suction. technique with efficient surfaces. Avolds water filtered out of exhaust.
filter, reactions. Nachine is contaminated. Water All nonporous surfaces Dissolves and erodes. For i.arge Surfaces All water equipment may Drainage must be (metal, painted. Hose with high-pressure be utilized. Allows controlled. Not suit-plastic, etc.) water at an optimum operation to be carried able for porous distance of 15 to 20 out from a distance. materials. Oiled feet. Spray vertical Contamination may be surfaces cannot be decon-
. surfaces at an angle of reduced by 50%. . Water taminated. Not incidence of 30* to 40*; equipment may be used applicable on dry con-work from top to bottom for solutions of other taminated surfaces (use to avoid recontamina- decontaminating agerts. vacuum); not applicable Lion. Work upwind to on porous surfaces such avoid spray. Det e rmine wood, concrete, canvas, cleaning rate experi- etc. Spray will be mentally, if possible; contaminated.
3 otearwise, use a rate jj of 4 square feet per minute. O m All surfaces Dissolves and erodes. For Small Surfaces Extremely effective if of little value in the
decontamination of large Blot up liquid and hand- done immediately after wipe with water and spill and on non-porous areas, longstanding appropriate commercial surfaces. contaminants and porous detergent, surfaces.
Steam Nonporous surfaces Dissolves and erodes. Work from top to bottom Contamination may be Steam subject to same (especially painted or and from upwind. Clean reduced approximately limitations as water. olled surfaces). surface at a rate of 4 90% on painted surfaces. Spray hazard makes the square feet per minute. wearing of water-proof The cleaning efficiency outfits necessary, of steam will be greatly increased by using detergents.
*Begin with the first listed method and then proceed step by step to the more severe methods, as reecessary. >M ,, e. .
H >* 4 kJ o kd
(~ u r) u. ( METHOD
SURFACE ACTION TECHNIQUE ADVANTAGES DISADVANTACES Detergents Nonporous surfaces Emulsifies contaminant Rub surface I minute Dissolves industrial May require personal (metal, painted, glass, and increases wetting with a rag moistened film and other materials contact with surface, plastic, etc.). power of water and with detergent solution which hold contamina- May not be efficient on cleaning efficiency of then wipe with dry rag; tion. Contamination longstanding contamina-steam. use clean surface of the may be reduced by 903. tion, rag for each applica-tion. Use a power rotary brush with pressure feed for more efficient cleaning.
~~Apply solution from a pressure proportioner.~~
~~. Do not allow solution to drip onto other surfaces. Hist application is all that is necessary.~~
Complexing Agents Nonporous surfaces Forms soluble complexes Complexing agent Holds contamination in Requires application for p (especially unweathered with contaminated solution should contain solution. Contamination 5 to 30 minutes. Little e surfaces; 1.e., no rust material. 3% (by weight) of agent. may be reduced by 75% in penetrating power of W or calcareous growth). Spray surface with 4 minutes on unweathered small value on weathered ut solution. Keep surface surfaces. Easily surfaces. moist 30 minutes by stored; carbonates and en
~~"" spraying with solution citrates are nontoxic.~~
4 periodically. After 30 noncorrosive, minutes, flush material off with water. Com-plexing agents may be used on vertical and overhead surfaces by adding chemical foam (sodium carbonate or aluminum sulfate). Nonporous surfaces Dissolves organic Immerse entire unit in Quick dissolving action. Requires good ventila-Organic Solvents (greasy or waxed materials (oil, paint, solvent or apply by Recovery of solvent tion and fire surfaces, paint or etc.). wiping procedure (see possible by distilla- precautions. Toxic to plastic finishes, etc.) Detergents). tion. personnel. Material bulky.
*Begin with the first listed method and then proceed step by step to the more severe methods, as necessary.
I
> ps i , 47 i . r.
w e. p DS kJ c2 4
O O O METHOD
St1RFACE ACTION TECH,NIQUE ADVANTACES DISADVANTAGES Inorganic Acids Metal surfaces Dissolves porous Use dip-bath procedure Corrosive action on Personal hazard. Wear (especially with porous deposits. for movable items. Acid metal and porous goggles, rubber boots, deposits; 1.e., rust or should be kept at a con- deposits. Corrosive gloves, and aprons.
calcareous growth); centration of I to 2 action may be moderated Good ventilation circulatory pipe normal (9 to 18% hydro- by addition of corrosion required because of systems. chloric, .3 to 6% inhibitors to solution, toxicity and explosive sulfuric acid). Leave gases. Acid mixtures on weathered surfaces should not be beated. for I hour. Flush sur- Possibility of excessive face with water, scrub corrosion if used with-with a water-detergent out inhibitors. solution, and rinse. Sulfuric acid not
~~Leave in pipe cir- -~~
~~effective on calcareous culatory system 2 to 4 deposits. hours; flush with plain water, a water-detergent solution, then again with plain water.~~
*o jj Acid Mixtures: Nonporous surfaces Dissolves porous Same as for inorganic acids. A typical mix-Contamination may Weathered surfaces may u Hydrochloric, (especially with porous deposits. reduced by 901 in I hour require prolonged treat-os Sulfuric, deposits); circulatory ture consist of 0.1 gal. (unweathered surfaces), ment. Same safety pre-Acetic, pipe systems. hydrochloric acid. 0.2 Hore easily handled than cautions as required for o
~~es Citric Acids, Ib sodium acetate and 1 inorganic acid solution. inorganic acids.~~
~~.a Acetates, gal, water.~~
Citrates Caustics: Painted surfaces Softens paint (harsh Allow paint-remover Minimum contact with Personal hazard (will Lye (Sodium Hydroxide) (horizontal), method). solution to remain on contaminated surfaces. cause burns). Reaction Calcium Hydroxide surface until paint is Easily stored. slow; thus, it is not Potassium Hydroxide softened to the point efficient on vertical or where it may be washed overhead surfaces. off with water. Remove Should not be used on remaining paint with aluminum or magnesium. long-handled scrapers. Typical paint remover solution: 10 gal, water, 4 lb lye, 6 lb boiler compound. 0.75 lb cornstarch. Trisodium Phosphate Painted surfaces Softens paint (mild Apply hot 10% solution Contamination may be Destructive effect on (vertical, overhead), method). by rubbing and wiping reduced to tolerance in paint. Should not be procedure (see one or two applications. used on aluminum or 3, g Detergent). magnesium. y *o
~~. H be k 8Begin with the first !!sted method and then proceed step by step to the more severe methods, as necessary. [~~
~~c2 p4~~
~~. _ .. __ ._ _,- _ . . , _ _ _ _ . . .__.m . _ ..m . ._._ .. . _ _ , . . _ _ _ . - _ . -.-._ _ -.._.m - . _ . . .__ _ . . _ .~~
~~( C O METHOD~~
SURFACE ACTION TECIINIQUE ADVANTAGES DISADVANTAGES Abreston Nonporous surfaces. Removes surface. Use conventional Contamination may be Impracticable for porous procedures, such as reduced to as low a surfaces because of sanding, filing and level as desired. penetration by moisture.
chipping; keep sur-face damp to avoid dust hazard. Sindblasting Nonporous surfaces. Removes surface. Keep sand wet to lessen Practical for large sur- Contamination spread spread of contamination. face areas. over area must be Co!!ect used abrasive removed. Contaminated or flush auay with dust is personnel
~~. water. . hazard.~~
4 Vacuum Blasting Porous and non-porous Removes a surface; traps Hold tool flush to sur- Contaminated waste ready Contamination of equip-surfaces. and controls contant- face to prevent escape for disposal. Safest ment. nated waste. of contamination. abrasion method.
~~=a f's 40 U~~
~~4 O M M lp M~~
.~
p. ds me >4 La kJ 4 ca 4
EP IV-121 EMERGENCY PROCEDUP.E O EP IV-121 CONTAINMENT ATMOSPHERE REMOTE SAMPLING ACTION LEVEL Declaration of an emergency at Alert level or above, or at the discretion of the Senior Shift Supervisor /EDo or Senior Radiation Protection Representative. WARNING Treat all samples as radioactive material. Sampling area a0d/ or samples may emit high exposure rates. LIMIT ON AUTHORITY Any entry into an evacuated area must have prior Senior Shif t Supervisor /EDO approval. ACTION STATEMENTS LigE INITIAL
~~1. The initiating individual shall contact the Dose Assessment /ALARA~~
~~[} Supervisor to obtain an Emergency Job Evaluation and a REP in accordance with EP IV-106.~~
2. The Radiation Protection Technician shall assure the sampling team protective clothing and equipment are in accordance with REP require-ments.

3. The Team Leader shall assemble apparatus / materials as follows:
a) . Particulate filter discs b) Caarcoal filter cartridges (or Silver Zeolite) c) Gas collection chamber d) Tritium collection chamber e) Poly bags l () f) Sample rigs (see Figure 1) g) Remote Sampling Data Form (Attachment 1) Page 1 of 7 Rev. 1
EP IV-121
~~,-~)~~
~~eCTION STATEFENTS (c0NTINUED) TIME INITTAL~~
4. The Team Leader contacts Unit 1 Control Room, informs them that Radia-tion Protection has authorization to obtain a remote air sample from containment and the valves to the alternate sample point must be lined up by the Control Room. ,
~~NOTE The sample location is remoted to the 78' elevation stair-well not at the containment air monitor in order to reduce personnel exposure during emergencies.~~
5. Connect the sample rig (Figure 2 for Unit 1 or Figure 3 for Unit 2) at the location and open the inlet and discharge valves. Monitor the system for rad levels while running the pump.

6. Close the sample rig valves, remove the sample, shield as necessary,
~~(} and return it to the Counting Room to analyze as needed.~~
~~7. Complete Attachment 1, Sections 2, 3, 4 and 6 and sign at the bottom, and insure results are transmitted to the TSC.~~
~~NOTE Sample flow rate and time require only that an adequate volume for good counting statistics is obtained. ATTACHMENTS~~
1. Remote Sampling Data Form

2. Figure 1 - Typical Sample Rigs

3. Figure 2 - Sampling valve Line-Up

4. Figure 3 - Emergency Sampling Rig
( [ Page 2 of 7 Rev. 1
EP IV-121 NOTE ( Forward all completed foms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. j
~~. . . - ~ . - - - - - __....... ...... _ . . . . . = .....-- __............_____________..~~
Prepared By h . r 1 Reviewed By: /O A0! Depa tim t d Date Reviewed By: / O!Z 4!M/ a y nager Data f Reviewed By: -
E tationVuality Assurance Engineer Date SORC Meeting No.: 8l-/// /027[E/ ' Date Approved By: /[/
~~Manager - Kalem Generating Station Date Approved By:~~
~~U ' Ak I 2I [2""""~~
Manager - Emergency Preparedness Date s l O Page 3 of 7 Rev. 1
EP IV-121 ATT. 1 ATTACHMENT 1 REMOTE SAMPLING DATA FORM ({])
/
~~Sample Date Sample Time~~
~~- l~~
1. Pre-Sampling Monitor Pump Readings Flow Rate cfm Vacuum inches

2. Particulate / Charcoal Filter Sampling Data Sample Flow Rate Ipm Sampling Time minutes Time on Time Off Sample volume liters

3. Gaseous Sampling Data Sample Flow Rate Ipm Sampling Time minutes Time on Time off
~~() Sample Volume liters~~
4. Tritium Sampling Data Sample Flow Rate Ipm Sampling Time minutes Time on Time off Sample volume liters

5. Af ter Sampling Monitor Pump Readings Flow Rate cfm Vacuum inches i 6. Monitor valve line up has been returned to normal.
~~YES NO~~
~~/ /~~
Signature of Person Taking Sample Date Time . I I (]) Page 4 of 7 Rev. 1
EP IV-121 FIG. 1 FIGURE 1 lO l l TYPICAL SAMPLE RIGS 4 C 9 ' v * % t-++J:;w.r,) f } ', '
~~~? }\ ,~~
~~c- _k_.~~
~~. , } i .~~
L?
~~= . Fow Matar E L*M Fica Meter I _~~
~~L*M L8M 3 .g~~
# Tritic:n Sa.m;;!ing i g .h 5 ~
t F1rticulata/ Chat

:al Y : 100cc Gas Cci1+cti:n Filter Heldar ,
~~C a ter 1 (Psrticu: ate and tedine Sa.m:!!ng) (Gaws.:s Sa.m: ling) I~~
~~/ - \~~
~~i, - -'~~
'g n A L m: p; K F x .
~~yn., , u - =n d , o ~~~
~~~5 l ~~~
l O Page 5 of 7 Rev. 1
1 1 EP IV-121 FIG. 2 i 2
~~FIGUPE 2 SAMPLE RIG CONNECTION FOR UNIT 1~~
) l I , i ! 1 1- PLASTIC LINE ! FROM CollTAINFI.NT s i V }1 - 1 i PtJMP ROTOMETER A B C I i 4
~~%f i~~
~~I A - Particulate Collection Filter t i B - Gaseous Collection Container (e.g., J-Bomb) C - Iodine Collection Filter (e.g., silver zeolite) f 4 l 1 iO n i k i k i t l, i~~
~
i t i 4 . 1 1 .i i I !O j } Pege 6 of 7 Rev. 1
EP IV-121 FIG. 3 l l Q FIGURE 3 sat'PLE RIG CONNECTION FOR UNIT 2 From To Containment Containment 3110HA 2VC910 /N2VC910 3111HA u u u u m n m, r n n n rN 2VC910 kJ rv Plastic Line Plastf[Line Back to Containment From Containment Sample Station Sample Station y .
~~- ~ ~~~
A B C ROTOMETER ~_ PUMP A - Particulate Collection Filter B - Caseous Collection Container (e.g., J-Bomb) C - Iodine Collection Filter (e.g., silver zeolite) O Page 7 of 7 Rev. 1
l EP IV-122 EMERGENCY PROCEDUPE ( $) EP IV-122 EFERGENCY STAFFING GUIDE AC_ TION LEVEL This procedure is to be followed whenever the Radiation Protection Emergency Organization is implemented, normally by order of the Senior Shift Supervisor /EDO. . BESPONSIBLE INDIVIDUAL The Radiation Protection Engineer or the Senior Radiation Protection Supervisor shall assure the Radiation Protection Emergency Organization is implemented and adequately staffed. LIMITS ON AUTHORITY The Radiation Protection Engineer / Senior Radiation Protection Supervisor has the authority to request additional personnel as required to meet Radiation Protection emergency staffing require-ments. Staffing sources are company personnel and/or contractor supplied personnel.
~~GCTION STATEMENTS 1~~
~~M INITIAL~~
~~1. Determine the potential length of the emergency and follow the suggested staffing guide.~~
<1 hour - No additional staffing <6 hours - Call all available normal stafi to Station <24 hours - Provide coverage using available staff on an overtime basis >24 hours <7 days - Place normal staff on 12 hour shifts, alert contracting agencies that additional personnel may be required >7 days - Staff through company and contractor personnel as required by conditions.
~~2. EP IV-101, Technical Support Center Activation, shall be used for all~~
() notifications within the Radiation Protection ocganization. Page 1 of 7 Rev. 0
EP IV-122 l Q ACTION STATEMENTS (CONTINUED) 11gi INITIAL
3. Assistance for equipment and personnel requests can be processed by the Office Administrator or through the Emergency Response Manager's Office.

4. Complete staffing for outage conditions (Attachment 2) is recommended for emergency conditicas lasting greater than 7 days.

5. The required staffing will be placed on shifts on an as needed basis.
~~Shift schedules will be set up so as to provide for the best utiliza-tion of available personnel.~~
~~6. The normal processing time for contractor personnel when they arrive on site is one week. Previously trained contractor personnel should be requested when possible.~~
~~O NOTE As a result of the rapid increase in personnel, assure that adequate supervision and coordinating personnel are available.~~
~~7. A partial list of Radiation Protection contractors is provided in Attachment 1.~~
~~ATTACHMENTS~~
1. List of Radiation Protection Contracting Companies

2. Radiation Protection Department Emergency Staffing

3. Radiation Protection Department - Alternate Emergency Positions

4. Radiation Protection Department - TSC Staffing l
Page 2 of 7 Rev. O
EP IV-122 ) { l C0ft'UNICATIONS NETWORK l f CONTROL POINT E TRAINING MAIN GATE RP OFFICE I 611 200 131 500 623 J 195 201 600 642 DISCUSSION In an emergency situation, there are many tasks that are required to be done. Through the , effective use of available and incoming personnel, these tasks can be performed in the most efficient manner possible. l l Many personnel, not trained in Radiation P m tection, can be used *o fill various required positions with minimal training. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments.
/
Prepared By*
/
~~Reviewed By: ' pa t ad~~
~~/O!d0!M/~~
~~Date Reviewed By: A stant to Manager~~
~~/0[2le / I/~~
Date Reviewed By: . . S'tation Quality Assurance Engineer Date SORC Meeting No.: bI~I// / O!2
~~'Date' 7!II Approved By: /~~
Manager - Salen Generating Station 'Date Approved By: *
~~M[ M #~~
Manager - Emergency Preparedness ' Date O Page 3 of 7 Rev. O
EP IV-122 ATT. 1 ATTACRENT 1 O RADIATION PROTECTION CONTRACTING COMPANIES ! 3T.V1.CY ACT l l INFORMATION f O A more complete list of contracting companies supplying services and material can be found in EP IV-212. O Page 4 of 7 Rev. 0
EP IV-122 l ATT. 2 l O ATTACHMENT 2 RADIATION PROTECTION DEPARTMENT EMERGENCY STAFFING l DECON/ RPT'S ASST'S HELPERS CLERKS SUPV'RS LAUNDRY OPERATIONS 6 12 12 2 Control Point Containment 3 9 3 Auxiliary Building 12 3 Operating Unit 3 - 6 3 3 2 45 Rad Waste 3 REP Room 3 3 3 2 Desimetry Dosimetry 3 3 Counting Room 3 3 2 Equipment 3 3 3 Instruments 3 6 Respirators 8 2 Administration 57 36 8 10 45 TOTAL' 24 135 Rad Protection Personnel 4 45 Decon Personnel (This staffing assumes 3 complete thifts.) I i O Page 5 of 7 Rev. O
k EP IV-122 ATT. 3 Q ATTACHMENT 3 RADIATION PROTECTION DEPARTMENT KEY PERSONNEL ALTERNATE EMERGENCY POSITIONS RPE J. O'Connor B. Ferguson L. Krajewski REP ROOM SOLID RAD WASTE EQUIPMENT DOSIMETRY OPERATIONS DOSE ASSESSMENT B. Hunkele D. Noce B. Cislo L. Krajewski B. Ferguson B. Cislo B. Hunkele D. Noce B. Ferguson A. Ogurek A. Ogurek B. Cislo B. Hunkele A. Ogurek W. Hunkele A. Ogurek A. Ogurek TRAINING Rad Services Inc. Hydro Nuclear Services Porter Consultants University of Lowell University of Michigan O , Page 6 of 7 Rev. O
j EP IV-122 ATT. 4 Q ATTACHFENT 4 PADIATION PROTECTION DEPAP.TPENT TECHfilCAL SUPPORT CENTER STAFFING RPE/ SENIOR RADIATION PROTECTION SI'PERVISOR PMONE TALKERS - SHORT TERM TSC St'RVEYS DOSE ASSESSMENT ENVIRONMENTAL MONITOR!NC CONTROL ROOM E.O.F. CONTROL POINT RADIO TSC TF , Radiation Radiation Shift Radiation TSC TSC Protection Technician RPH/ Clerk RPH/ RPH/ Clerk RPH/ Protection Protection Clerk Assistant Supervisor Clerk TELECOPIER RPH/ Clerk l RADIATION PROTECTION DEPARTMENT Technical Support Center Interia Staffing O PHONE TALKER SHORT-TERM ENVIRONMENTAL MONITORINC. i Shift Radiation Protection Technician Control Room to TSC t i I f o ; Page 7 of 7 Rev. 0
t EP IV-201 ([]) EFERGENCY PDOCEDURE EP IV-201 RADIATION PROTECTION SENIOR SUPEDVISOP RESPONSE ACTION LEVEL This procedure shall be used whenever the Radiation Protection Emergency Organization is activated. . RESPONSIDLE INDIVIDUAL i l This procedure shall normally be implemented by the Senior Supervisor of Radiation Protection on site. LIMITS 04. AUTHORITY Not applicable ACTIONSTATENENTS 1 M INITIAL O
1. Upon arrival onsite, proceed to Technical Support Center (TSC) . Deter-mine radiation levels in TSC. Obtain current briefing on the incident from the Shift RPT or the EDO.

2. Assume the overall responsibility for the Radiation Protection Organization. Assign the Shif t RPT the responsibility for, managing the short term environmental monitoring. Assign other personnel as they arrive.

3. Review the radiation levels onsite and offsite. Ensure that the projected doses and recommended protective actions are consistent.
i
~~4. Upon ct.p.etion of the initial data review, inform the EDO of your evaluation of the situation.~~
l
~~5. Check with each supervisor for briefing on specific areas of responsibility and inform the supervisors on plant's status.~~
l Page 1 of 3 Rev. 1
i 1 l EP IV-201 O U ACTION STATEMENTS (CONTINUED) M INITIAL AREA OF RESPONSIBILITY EXT. CR LnCATION
a. Dose Assessment-ALARA PAG Determination TSC Ext. 201, 200

b. Rad Waste TSC Ext. 201, 200

c. Chemistry Ext. 524

d. Environmental Monitoring TSC Ext. 201, 200

e. Dosimetry, Records Counting Room Ext. 623

f. Administrative Assistant Ext. 642

g. Materials, Instruments Ext. 642

h. Procedures, Training, Incident Investigation Ext. 642

1. In-Plant Health Physics Ext. 623

6. Discuss short term situational changes to be effected by Administrative Assistant. Areas to consider include manpower / materials requirements to supplement plant personnel and equipment, scheduling current staff and contractor personnel for extended duty hours, exposure levels of personnel, and ensure senior management personnel are onsite 24 hours /
day. Maintain overall authority and review of program and continue to advise upper management on Radiation Protection concerns. ATTACHf1ENTS None . C0f7UNICATIONS NETWORK Pr'Jtiously mentioned DISCUSSION The Senior Supervisor of Radiation Protection provides guidance and determines priorities in an
^ emergency situation. In the initial stages, he provides management and subordinates with the leadership and experience necessary to evaluate radiological consequences and therefore a vital aspect in over-all control of the emergency.
~~Page 2 of 3 Rev. 1~~
~
~~EP IV.201 NOTE Forward all completed forms to the Assistant to Manager (SGS) .~~
~~Attach any referenced completed EP's or attactaments.~~
/
~~Prepared By _ Reviewed By: /O A0!M/ par e d Date~~
,eviewed By, istant to Manager io/u Date /w Reviewed By: 1AAAA ! Date Station-Quality Issurance Engrneer SORC Meeting No.t O[~ /// /d!Z Date I!bI Approved By: // /
~~Managdr 'Salen Generating Station ' 4at( Approved By -~~
~~M M Manager - Daergency Preparedness Date O ,~~
Page 3 of 3 Rev. 1
EP IV-202 EFERCENCY PPOCEDURE i O Ee iv-202 CHEMISTRY SENIOR SUPEP.V!SOR PISP0flSE ACTION LEVEL This procedure shall be implemented whenever the Radiation Protection Emergency Organization is activated. , RESPONSIBLE INDIVIDilAL This procedure shall normally be implemented by the Senior Supervisor of Chemistry. LIMITS ON Al]THORITY
1. The approval of the Senior Shift Supervisor /EDO is required prior to re-entry into evacuated areas.

2. Prior to obtaining any samples that will result in personnel exposures in excess of 10CFR20.101, obtain the approval of the Senior Shift Supervisor /EDO.

3. Prior to sending any samples offsite, the approval of the Senior Supervisor of Radiation Protection shall be obtained.
~~ACTION STATEPEllTS M INITfAL~~
~~1. Upon arrival onsite, proceed to the TSC and determines a) Anticipated radiation levels in the Primary Sample Lab and Counting Room.~~
~~b) Briefing on the incident.~~
~~2. If it is expected that the radiation levels in the Auxiliary Building are going to increase significantly, consider evacuation of personnel and essential equipment.~~
Page 1 of 4 Rev. 1
EP IV-202 I ACTION STATEMENTS (CONTINUED) ({]) 11gE INITIAL CONSILER INITIATING MPC MR/HR EVACUATE PERSONNEL EVACUATION OF EQUIPMENT 10 1 Within 24 hours Within 8 hours i i 50 , 5 Within 8 hours Within 2 hours 100 10 Within 8 hours Within 1 hour 1000 Immediately
3. Specific items to consider for evacuation includes a) High Priority O 1) Gas Chromatograph i

2) Boron Titration Kit

3) Ge (11) Detector

4) Canberra 8100 or Scorpio System

5) La-36 b) Moderate Priority j ,

1) pH meter, buffer and probes

2) Log Books

3) Chloride Analysis Kit i
~~O l Page 2 of 4 Rev. 1~~
~
~~EP IV-202 O SCTION STATEMENTS (CONTINUED) l lig[ INITIAL c) optional Items~~
1) Miscellaneous Glassware ,

2) Atomic Absorption Unit

3) At least one (1) scale 1 4) Reference Books (a) Table of Radionuclides (b) MCA References i

4. calibration standards and sources Transfer the equipment to an alternative location. Possible j alternatives include:
I, a) Unit 2 Warehouse b) Hope Creek Warehouse c) Spare trailers d) Administration Building e) , Main Gate f) "A" Building NOTE All materials and personnel shall be surveyed for contamination prior to release to an uncontrolled area. ! Re-establish the operability of the evacuated equipment as soon as possible. Page 3 of 4 Rev. 1
l
~~EP IV-202 f~~
~~l l~~
~~$CTIONSTATEMENTS(c0NTINUED) t IJgE INITIAL~~
5. Contact the Administrative Assistant for the proper distribution of personnel. Consider establishing a 24-hour staffing schedule.

6. Requests for samples shall be approved by the Senior Supervisor of Radiation Protection prior to collection.
l l NOTE l l Forward all cczmpleted forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. COMMUNICATIONS NETWORK TSC CONTROL ROOM 1 CONTROL ROOM 2 SSS CHEMISTRY LAB 200 633 641 635 616 g 201 U DISCUSSION . The Chemistry Supervisor shall have the responsibility of coordinating the efforts of obtaining samples of reactor coolant and of monitoring the containment atmosphere for hydrogen-oxygen concentrations. He shall also advise the EDO in regard to any pertinent plant problems in the chemisty area. j Prepared B .
/'
Reviewed By: /O!d6 / ar en He d Dats Reviewed By: /Of26f9'
~~' Date istant ~to Manager I~~
Reviewed By: - ! W Date ( Station Quality Assurance N gineer SORC Meeting No.: bl~ l/ I /0/l7!JP # Da t'e Approved By: Manager - Salem Generating Station
/// k Date Approved By: * * /Mdd Jf 84-Manager - Emergency Preparedness Date Page 4 of 4 Rev. 1
EP IV-203 O EMERGENCY PROCEDUPE EP IV-203 ADMINISTRATIVE ASSISTANT D.ESPONSE ecTION LEVFIS This procedure shall be implemented whenever the Radiation Protection Emergency Organization has been activated. , ftESPONSIBLE I;1bfVIDUAL These guidelines will normally be implemented by the Administrative Assistant for Radiatior4 Protection. LIMITS ON AUTHORITY
1. The Administrative Assistant may notify any individual or group in Radiation Protection to assume a " standby" or " alert" status.

2. Approval from the Senior Supervisor of Radiation Protection shall be obtained prior to requesting any individual or group to supply materials or personnel. EDo approval will also be required.
~~V ACTION STATEMENTS I,L1 INITIAL~~
~~1. Upon arrival onsite obtain a briefing on the incident from the TSC.~~
~~Synchronize your watches. If the TSC does n_o,t,have o any special procedure for you to follow, proceed to Step 2.~~
~~2. Proceed to a suitable work location (normally the Control Point).~~
Alternative locations includes a) Administrative Building b) Onsite or offsite trailers c) Main Gate NOTE O If a location other than the Control Point is used, ensure that the TSC is aware of your location. Page 1 of 6, Rev. 1
EP IV-203 SCTION STATEMENTS (CONTINUED) (}}) 1151 INITIAL
3. Notify other Radiation Protection Supervisors of your arrival. Note if they have any material or personnel deficiencies. Any surplus personnel should be requested to report to you for redistribution.
PADIATION PROTECTION EFERGENCY OPGANIZATION PRE-ARRANGED COMMUNICATION POSITf3N LOCATION LINK Sr. Supervisor R_d. Pro. TSC 200 201 offsite and Out-Of-Plant Monitoring TSC 200 201 Dose Assessment /ALARA TSC 200 201 Rad Waste Coordinator C.P. 633 Dosimetry Supervisor C.P. 551 623 Materials & Inst. Supr. C.P. 623 642 Procedures Training Supervisor C.P. 623 642 NOTE If any supervisors cannot be reached at their pre-assigned locations, contact the TSC for additional information.
4. As surplus personnel become available, assign and distribute them to areas requiring additional manpower. Any serious deficiencies in personnel or materials that cannot presently be corrected should be brought to the attention of the Senior Supervisor of Radiation Protection on site.
~~O . { t I Page 2 of 6 Rev. 1~~
~~._ . -_. - . _ . _ . . - - --=~~
~~EP IV-203 ACTION STATEMENTS (CONTINUED) IldE INITIAL~~
5. If possible, schedule break reliefs for the personnel in the field.

6. As soon as possible, make arrangements for 24 hour coverage for each ,
emergency position. Consider sending home (or alternative rest locations nearby) non-essential personnel for subsequent shift relief. Prior to relieving any personnel, ensure adequate communications are available for recall. Ensure that replacement personnel are briefed and understand what they are expected to do (normally delegated to procedures and training supervisors). I
7. Consider using surplus personnel (including personnel from other station groups) to perform certain tasks that do not require extensive training, e.g., communications, equipment inventory, data recording, clerical work, etc.
- a) Notify the appropriate individual, group, company or agency, if O5 additional personnel are required. Request them to place their personnel or equipment on standby - Alert. If authorization has been obtained from the Senior Supervisor of Radiation Protection, you may request them to begin supplying their materials or personnel, b) Retain a record of the individuals / companies contacted, the quantity and type of service requested, date and time of contact, estimated costs, and the anticipated time of arrival onsite.
c) . Ensure that an onsite contact has been provided to each group or company. Provide them with instructions on where to report (e.g., main gate, Hancock's Bridge, etc.). d NOTE l Use Attachment 1 to record the information required for steps a, b, c. l O Page 3 of 6 Rev. 1
EP IV-203 ACTION STATEMEilTS (CONTINUED) 11gi INITIAL
8. Prior to the arrival of additional offsite personnel, make arrangements i with the Training and Dosimetry Departments. Provide them with the f approximate arrival time and the number of personnel expected.

9. If materials have been ordered, pr6 vide the Instrument and Materials Supervisor with information on the type of material and expected time of arrival.

10. If sources for any item or service cannot be found, or if the lead time is excessive, notify the requestor of the item or service and attempt to identify an alternative vendor.
~~NOTE See EP IV-212 for a list of supplied, services and sources for each item. O~~
~~11. Consider making lodging arrangements for any personnel that normally reside excessively far away from the site.~~
~~ATTACHMENTS~~
1. Supplementary Assistance Request Form C0muNICATIONS NETWORK CONTROL POINT TSC WAREHOUSE MAIN GATE 623 201 . 120 500 642 200 551 DISCUSSION I
l In an emergency situation, the initial response will depend upon onsite materials and personnel. If competition arises for a limited resource, priorities will have to be established. It will be the responsibility of the Administiative Assistant to establish the priorities and ensure that the appropriate resources get allocated to proper locations. (Vl Page 4 of 6 Rev. 1
~~EP IV-203 O oiscussion <cos1,soto)~~
( Subsequent to the initial response, offsite assistance may be utilized. Various services or additional materials may be required to augment the initial emergency response. The Administrative Assistant will be as, signed the responsibility to ensure adequate, but not excessive, supplies or services are obtained. Depending upon the specific incident (i.e., type, length and magnitude), some of the responsibilities of this procedure may be delegated to the Instrument and Materials Supervisor., NOTE Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments.
~~. ==. ..........._ .... ....._............ . ........_............= ...............~~
Prepared - r-Reviewed By: /C!d6! b/ Dep r t ead Date O Reviewed By: /0/26 !E / Assistant to Manager ' Date Reviewed By: )h N \ t3Yion Quality Assurance Engineer Date ~ SORC Meeting No.: h/~/!/ /0/7 7 !b / Date Approved By: / / W /d Manager sSaled Gener& ting Station 15 ate ' Approved By: * - M 2 / [V Manager - Emergency Preparedness Date l Page 5 of 6 Rev. 1
~~. . _ . _ . . -= .. - - _ . . . ~ . . . _ . - _ - _ .-. ._. _ . _ . _ _ _ _ _ ..~~
~~EP IV-203 ATT. 1 O acen SUPPLER.Ef1TARY ASSISTAtiCE REQUEST FOPP .; 1. Type of Service or Materials Requested l i~~
2. Quantity or Period of Time Required

3. Approximate Costs I
~~i O~~
4. Required By (Date) i I 5. To be Used by (Individual or Group) 5 l

6. Suggested Supplier l
{ O Senior Supervisor Approved Radiation Protection Admin. Asst. Date/ Time Page 6 of 6 Rev. 1
EP IV-204 EMERGENCY PROCEDURE EP IV-204 Q SHORT TEPR EfNIRONMENTAL RESPONSE ACTION LEVEL This procedure shall be implemented when the Radiation Protection Emergency Organization is activated. , PESPONSIBLEINDIVIDUAL The Shift RPT assigned to the TSC per the Radiation Protection Emergency Organization will be responsible for Short Term Environmental Response. When supplementary off-site personnel arrive, long term environmental monitoring will be handled by the Radiological Emergency Manager. LIMITS ON AUTHORITY
1. Exposure in excess of 10CFR20.101 shall be approved by the Shift Supervisor /EDO.

2. Change out of the air samples or TLD's in the environmental stations requires the approval of the Senior Supervisor-Radiation Protection.

3. Issuance of KI solution requires the approval of the Shift Supervisor /EDO (refer to EP I-15).
~~eCTIONSTATEMENTS M INITIAL~~
1. Proceed to the Technical Support Center (TSC) when it is activated and announce your arrival.

2. Get. briefed on the incident.
l
3. Obtain wind direction from the computer printout or alternatively call the Control Room.

4. Call the Accident Assessment Liaison and request sufficient personnel be assigned to the Short Term Environmental Monitoring Team. If the Administrative Assistant isn't available, contact the Control Point, Ext. 611, and request extra people.
Page 1 of 4 Rev. 1
EP IV-204 Q ACTION STATEPBlTS (CONTINUED) IIME INITIAL
5. Instruct assigned personnel to reference the Field Monitoring Instructions (EP IV-110).

6. Acquire portable radios (including remote antennas) from the Main Gate and perform operability checks.

7. Request vehicle keys for off-site monitoring teams from the Senior Shift Supervisor /EDO and provide Environmental Monitoring Team Leader with the keys.

8. Brief team members and ensure the following categories are covered prior to departures a) Team Leader designated.
b) Teams have adequate equipment. c) Teams will be able to communicate (radio range). d) Teams know where, how long, and for what they are sampling. e) How to use thyroid blocking agent (KI).
9. Initiate off-sit dose calculations using data obtained from primary vent stack monitors. See Procedures EP IV-lll and EP IV-ll3.

10. Record data from on and off-site surveys on Attachment 1 for future evaluation and inform the Senior Supervisor of Radiation Protection on site of significant changes in survey results.
\
~~11. Ensure that the Team Leaders are kept up to date on plant conditions.~~
As the offsite monitoring teams relocate, ensure that the communica- { 1 i tions link is not broken. Page 2 of 4 Rev. 1
l l
EP IV-204 ATTACHNENTS Data Transmittal / Receipt Form COMMUNICATIONS NETFORK OFFSITE MONITORING TEAMS HELICOPTER TSC CONTROL ROOM Base Station Radio Radio Radio Pay Phone Pay Phone Phone Phone ,
DISCUSSION The prime objective of the off-site radiation monitoring teams is to rapidly survey off-site areas in order to determine the extent and magnitude of any uncontrolled release of radioactive material following an incident. The initial off-s'te surveys are very important regarding the extent and types of protective actions required. Accurate transmission, reception and interpretation of data is of param unt impor% nce regarding initiation of protective actions. NOTE Forward all ccanpleted forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments. J Prepared By: Reviewed By: /D 80 / parta Head ' Date Reviewed By: / M / 4tadt to Manager ' Date Reviewed By: r- . 1 Station Quality Assurance Engineer LDate SORC Meeting No.: bl ~ I/I /0!Z7!?I
' Dat6 Approved By: / // k Manager sSalent Generating Station ' Qatd Approved By: . -
444/1 2/ M Manager - Emergency Preparedness 'Date b v Page 3 of 4 Rev. 1
' EP IV-204 ' ATT. 1 ATTACHfiErlT 1 DATA TRAftSMITTAUDECEIPT FORT 1
l. Team

2. Team Leader B C D

3. Location: A _
~~B C D Date/ Time: A~~
~~4. Air Sample Data A B C D Volume i Particulate uCi/cm 3~~
~~Iodine DC1/cm i Charcoal / Silver Zeolite~~
~~5. Direct Radiation Survey I~~
Beta Dose Rates A B C D Waist 1 Ground Level i Gamma Dose Rates A B C D Probe Up Probe Down
~~6. Miscellaneous Comments .~~
A B C l O < l D l Page 4 of 4 , Rev. 1
EP IV-205 O EP.ERGENCY PROCEDURE EP IV-205 MTERIALS AND INSTRUMENTS SUPEP. VISOR RESPONSE ACTION LEVEL This procedure shall be implemented whenever the Radiation Protection Emergency Organization is activated. . RESPONSIBLE INDIC Dljal. This procedure shall be implemented by the Materials Supervisor of Radiation Protection. LIMITS ON AUTHORITY None ACTION STATEMENTS M INITIAL
1. On .wrival onsite, proceed to the Technical Support Conter (TSC) and obtain briefing on the incident. If already onsite, proceed to the Control Point where a briefing on the incident will be available.

2. Determine the necessity for initiating inventory control and when the decision to proceed with it has been made, reference the Inventory control Initiation procedure.

3. Take responsibility for instrument issue. Insure adequate controls are in place to assure instruments in use are functioning properly (i.e.,
~~battery checks, response checks).~~
~~4. Insure SCBA bottles are being replaced and refilled as quickly as possible.~~
COMMUNICATIONSNETWORK TSC CONTROL POINT CONTROL ROOM WAREHOUSE SSS 201 611 633 120 635 200 Page 641 647 576 ' Page ( l
)
Page 1 of 2 Rev. 1
EP IV-205 O niscussion (- Delays in controlling emergency situations resulting from supply insufficiencies can be prevented by ensuring adequate amounts are available on short order. EP IV-212 starts the process by which adequate supplies are obtained. NOTE Forward all completed forms to the Assistant to Manager (SGS). , Attach any referenced completed EP's or attachments.
/
~~Prepared By: _ , Reviewed By: , _~~
~~!O pd'r n ead / Date '~~
Reviewed By: sYstant to Manager e ! i Date Reviewed By: ) Station Quality Assurance Engineer Date SORC Meeting No. h / ~ /f / IOf 7 7 / Wf Date Approved By: NJ //[ W Managet - Salem Generating Station sate Approved By: . - 4W Manager - Emergency Preparedness f l81 /!dI Date V
/
Q - Pac)e 2 of 2 Rey. 1
EP IV-206 EHERGEllCY PROCEDURE Q DOSIMETRY-COUNTING ROOM SUPERVISOR RESPONSE EP IV-206 ACTION LEVEL These procedures shall be followed whenever the Radiation Protection Emergency Organization is activated. RESPONSIBLE INDIVIDUAL This procedure shall be implemented by the Dosimetry Supervisor. LIMITS ON AUTHORITY Any movement of equipment in other than life threatening situations shall have prior approval of the Senior Shift Supervisor /EDO. 8CTION STATEMENTS M INITIAL
1. Obtain a briefing on the incident from the TSC.

2. Monitor the current radiation levels in the Dosimetry Office and the Counting Room (normally located at the Control Point) .
~~NOTE If the radiation levels exceed 2 mr/hr in the Counting Room or 5 mr/hr in the Dosimetry Office, consider tne procedure for the " Evacuation of Equipment and~~
~~. Materials" (EP IV-105).~~
3. If the radiation levels exceed 1 mr/hr at the TLD rack, ensure adequate control TLD badges are in use. If the radiation levels exceed 10 mr/hr, consider transferring the dosimeters to another location (e.g. Main Gate). Notify TSC of change.

4. If the Control Point area is expected to remain habitable, ensure all the necessary Dosimetry and Counting Room equipment is operable, calibrated, and ready for use.
i Page 1 of 3 Rev. 1 ~
EP IV-206 O ACTI0fl STATEPEflTS (CONTINUED) 11gE INITIAL
5. If the nature of the incident is such that additional personnel will be arriving en site, prepare TLD's, Pocket Dosimeters, etc.

6. If additional personnel are required or surplus staff is under your direction, contact the Administrative Assistant at the control Point, and advise accordingly.

7. Consider making Shift Schedules for 24-hour staffing.

8. If you require the assistance of outside vendors (e.g. Nuclear Data, Harshaw, etc.), contact the Administrative Assistant at the Control Point.

9. Continue to monitor radiation levels in your work locations and the
~~() dosimetry racks.~~
10. Be on the alert for contaminated dosimeters.

11. Dose evaluations due to lost or of f-scalo dosimetry must be conducted with extra care. Any suspicious or high doses shall be resolved prior to allowing individuals to return to work in a radiation area.
ATTACHf'EllTS , None (OPfiUNICAT10fisNETWORK TSC CONTROL ROOM 1 CONTROL ROOM 2 SSS OFFICE CONTROL ROOM 623 201 633 641 635 642 NOTE Forward all completed forms to the Assistant to Manager (SGS) . O's Attach any referenced completed EP's or attachments. Page 2 of 3 Rev. 1
EP IV-206 DISCUSSION In the event of an emergency, it will be essential to maintain current exposure history records an1 the operability of the Counting Room. Extra personnel, dosimeters, and consumables will haie to be obtained to support the group. Prepared B . Reviewed By: /O!dd / Depal en stead ' Date Reviewed By: / c[26 [Y / Assistant to Manager Date
~~/ ,~~
~~Reviewed By: i . mL [Ob2 i \ StttioT Quality Assurance Engineer i Date SORC Meeting No.: 8 / - // / /0[27h Date~~
/
~~Approved By: // ] Manager - Salkm Generating Station~~
~~~ 'Date Approved By: . . M !!1I Date IM Manager - Emergency Preparedness l~~
O Page 3 of 3 Rev. 1
EP IV-207 EFERGENCY PROCEDURE O EP IV-207 RAD WASTE SUPERVISOR RESPONSE ACTION LEYEL This procedure shall be implemented whenever the Radiation Protection Emergency Organization is activated. , RESPONSIBLE INDIVIDUAL This procedure will normally be completed by the Supervisor for Rad Waste or a Chem-Nuclear representative as directed by the Senior Supervisor-Radiation Protection. LIMITE ON AUTHORITY Re-entry must have Senior Shift Supervisor /EDO approval. ACTION STATEMENTS 11ME INITIAL O 1. Obtain a briefing on the incident from the TSC.
2. Evaluate the current status of the Rad Waste Systems a) Current capacity o) Status of demineralizers c) , Availability of spare materials onsite d) Anticipated operations which will affect Rad Waste e) Current isotopic composition of waste material f) Habitability of Rad Waste work areas O
Page 1 of 3 Rev. 1
EP IV-207 1 l 1 8CT101 STATEPINTS (CONTINUED) ({]) ligE INITfAL
~~3. Establish 24-hour staffing for decon, laundry, and waste collection.~~
~~If additional personnel are required, contact the Administative Assistant at the Control Point.~~
4. Evaluate the establishment of long-term stcrage areas for Rad Waste onsite.

5. Arrange shipping schedules with the burial site.

6. Prepare paperwork for Rad Weste shipments.

7. Keep Senior Supervisor-Padiation Protection briefed on all work.
~~, 8. Ensure that all Rad Waste storage areas are properly posted and/or locked.~~
9. ontact the Administrative Assistant and request notification of transport organization and burial sites.

10. Check the supply of waste containers (e.g., LSA boxes, drums, etc.)
~~and inform the Administative ?.ssistant of their status. Request that the Materials and Instruments Supervisor be advised if supplies are low. ATTACHMENTS .~~
)
l None COMMUi1ICATIONS NETWORK CHEM-NUCLEAR ADMIN. ASST. TSC CONTROL ROOM 1 CONTROL ROOM 2 SSS (onsite) 542 201 633 641 635 (Barnwell - 623 200 0* PRIVACY ACT INFORMATION R.,. - 2 R.v. 1
EP IV-207 9 NOTE V Forward all completed forms to the Assistant to Manager (SGS). A; tach any referenced completed EP's or attachments. DISCUSSION volumes of rad waste greater than those from norsal operations will be encountered in an emergency. Establishment of additional storage locations and facilitating removal of the material offsite will ensure that the removal of materials from work locations will not be hindered and the exposure to personnel from superfluous materials is minimized. Prepared B - Reviewed By:
~~/0 Date/2b!N Department ad Reviewed By: / o[24!P/~~
~~Assistant to Manager Date Reviewed By: - M \~~
~~" Staflon Quality Assurance Engineer Date h/ ~ //I / 27 /~~
~~SORC Meeting No.: ' Date Approved By:~~
~~//M ' Fate Manager . Salesh Generating Station l I' I V Approved By:~~
~~Date Manager - Dnergency Preparedness~~
? I l l Page 3 of 3 Rev. 1
EP IV-208 EMERGEllCY PROCEDURE ())) EP IV-208 DOSE ASSESSMENT - ALARA SUPERVISOR RESPONSE ACTION LEVEL This procedure shall be implemented whenever the Emergency Radiation Protection Organization is activated. . RESPONSIBLE INDIVIDUAL The Technical Supervisor for REP Planning will normally be responsible for implementing this procedure. LIMITS ON AUTHORITY Protective Action Guides shall be approved by the Senior Shift Supervisor /EDO prior to onsite actions. ACTION STATEMENTS IlgE INITIAL O
1. Upon arrival onsite, proceed to the TSC and obtain a briefing on the incident. Synchronize your watches.

2. Determine the areas where the greatest radioactive concentrations can be expected. Inform the supervisor for environmental surveys (the Shif t RPT in TSC) where to dispatch monitoring teams onsite.

3. If any tasks are requested, evaluate them against the ALARA Review Instructions (EP IV-106).

4. Keep the Senior Supervisor of Radiation Protection on site informed of any significant data.

5. If additional staffing or materials are required, contact the Administrative Assistant.
ATTACHf4ENTS None l l Page 1 of 2 Rev. 1
EP IV-208 e COMMUNICATIONS NETWORK ( CONTROL RCOM 2 SENIOR SHIFT SUPERVISOR CONTROL POINT E CONTROL ROOM 1 615 611 201 633 641 623 200 642 DISCUSSION l As emergency tasks are submitted to the Radiation Protection Group for review, use the ALARA 1 Review Guide. This review will be conducted by the ALARA - Dose Assessment Group. Final approval for jobs involving excessive exposure or re-entry into evacuated areas will require the endorsement of the Senior _ Supervisor of Radiation _ Protection and the Senior Shift Supervisog/. EDO. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. d Prepared
/,
Reviewed By: 10f26 fir 1 Dep' arts t H ad Datie Reviewed By: / Ofd0 !IfI Assistant to Manager Date Reviewed By: l 71 ation Quality Assurance Engineer Date SORC Meeting,No.: b f ~ ll! /Of27!bI Date n <
/
~~Approved Byt Date Manager - Salen Generating Station AA4A [ I & Approved By:~~
~~Date Manager - Emergency Preparedness Page 2 of 2 Rev. 1~~
EP IV-209 EMERGENCY PROCEDURE lgg EP IV-209 IN-PLANT SUPERVISOR RESPONSE ACTION LEVEL This procedure shall be implemented whenever the Radiation Protection Emergency Organization is activated. . BESPONSIELE INDIVIDUAL The Technical Supervisor of Operations for Radiation Protection will normally be responsible for completing this procedure. LIMITS ON AUTHORITY The approval of the Senior Shif t Supervisor /EDO shall be obtained prior to a21owing any of the following actions:
1. Re-entry into evacuated areas.

2. Planned exposures in excess of 10CFR20.201.
~~( V) 3. Dispatching of personnel offsite. ACTION STATEMENTS 11gE INITIAL~~
1. Obtain a bri-S . cn 5e .ncident from the TSC.

2. Assign an individual to record all pertinent information in the Emergency Log Book.

3. Check the radiation levels at location :normally the Control Point) .
Ensure the area is properly posted. NOTE If the radiation levels are greater than two (2) mr/hr (~'y see " Equipment and Instrument Evacuation Instructions" \ (EP IV-105). Page 1 of 4 Rev. 1
1 EP IV-209 BCTION STATEMENTS (CONTINUED) 11gE INITIAL
4. Account for all Radiation Protection personnel. Notify the TSC of personnel at the control Point and the current radiation levels.

5. Ensure that the emergency equipment and portable survey instruments are ready for use.

6. Assemble your staff into teams. Normally they should be assembled into pairs, with a senior and junior member on each team. Record the names of all personnel in the Log Book. For each member include their current quarter-to-date exposure estimates and current dosimeter readings.
NOTE All personnel should have their TLD's, Self Reading Dosimeters and Dosimeter Cards with them if they [) v expect to rezero dosimeters in the field. Ensure the Control Point is aware of their locations.
7. Consider having some of the teams don protective clothing in anticipation of a re-entry.

8. As personnel are re-assigned to other supervisors or dispatched to survey locations, record their assignments in the Log Book.

9. Contact the Administrative Assistant and review manpower requirements.
~~Surplus personnel should be re-assigned to the Administrative Assistant.~~
10. Consider establishing a schedule for 24-hour staffing.

11. If equipment deficiencies are identified, notify the Instrument and Equipment Supervisor. Inform him of your needs and relative priority for each item.
~~Ci '\. .J~~
~~12. Maintain communications with the TSC.~~
Page 2 of 4 Rev. 1 l l l
EP IV-209 ACTION STATEMENTS (CONTINUED)
)
~~115E INITfAL~~
13. Contact the Dose Assessment /ALARA Supervisor in anticipation of upcoming jobs.

14. Ensure frequent surveys of the Control Point area are conducted (contamination, dose rate, and airborne).

15. Ensure all pertinent data is recorded in the Emergency Log Book.
eTTACHMENTS None COMMUNICATIONS NETWORK COUNTING ROOM CONTROL POINT CHEM - RP CONTROL ROOM 1 CONTROL ROOM 2 SSS TSC 611 616 - 612 633 641 635 201 O 623 200 642 551 DISCUSS 10fl In the event of an emergency, the Technical Supervisor of Operations for Radiation Protection will retain his normal responsibilities for in-plant Health Physics. He will normally report to the Control Point and assume responsibility for all unassigned technicians and for the access control functions. Dosimetry devices should be distributed to all the technicians along with their dosimeter cards to track any resets. Survey equipment should be checked and ready for use. Personnel should be assigned to teams of two"each. All pertinent data should be documented in the log book and transmitted to the TSC. In summary, the Operations Supervisor for Radiation Protection should nave the personnel under his direction ready to respond, maintain access control over any evacuated areas and constantly monitor the Control Point Area for habitability. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. ] \)' I" 1 Page 3 of 4 Rev. 1
EP IV-209 Prepared b Reviewed By: 1ep nt ad / te / Reviewed By: ! , Assistant to Manager Dates Reviewed By: I i1 % W tation Ghality Assurance Engineer [b!N Tate SORC Meeting No.: bI ~ llI /0[77 ' Date'
/
~~Approved By: /# Managet - Salem Generating Station~~
~~/!/3 'Da te '~~
Approved By: * * >_ l_k I I [b Manager - Emergency Preparedness Date O . I J O I Page 4 of 4 Rev. 1
EP IV-210 EMERGENCY PROCEDURE
~~/~'\ EP IV-210 '~~~
PROCEDURES-TRAINING SUPERVISOR RESPONSE ACTION LEVEL This procedure shall be implemented whenever the Radiation Protection Emergency Organization is activated. RESPONSIBLE INDIVIDUAL This procedure shall be implemented by the Supervisor of Training for Radiation Protection. LIMITS ON AUTHORITY Not applicable ACTION STATEMENTS IlgE INITIAL
~~1. Obtain a briefing on the incident from the TSC. Synchronize your~~
~~(_) watches.~~
~~2. Check with the Administrative Assistant and aid him with his duties.~~
~~You may be temporarily re-assigned to support any other department requiring assistance.~~
~~3. Debrief the individuals who were onsite at the time of the incident.~~
~~Ensure that any significant details are brought to the attention of the Administrative Assistant. Record all information on Attachment 1 (Debriefing Notes).~~
4. When the Administrative Assistant defines the expected influx of additional personnel, develop training outlines to reflect the specific incident.

5. Depending upon the severity of the incident, daily training or briefing sessions may be held for each shift turnover. The briefing sessions should be concise and t.) the point. Personnel should not be detained
~~[j from relief longer than absolutely necessary. , %J i~~
~~Page 1 of 3 Rev. 1~~
~~s EP IV-210 l ACTION STATEMENTS (c0NTINUED)~~
)
ligE INITIAL l 6. When offsite agencies or intra-company representatives request ' interviews with individuals, contact their respective supervisors and arrange a mutually convenient meeting time and place.
7. If current or new procedures require drafting or revision, ensure that they are routed for adequate review. Ensure the appropriate approvals are obtained prior to SORC review.

8. After new or revised procedures are approved by SORC, ensure the necessary training is conducted and documented.

9. After new or revised procedures are approved, ensure the necessary copies are distributed to the controlled copy location.
() 10. If additional staffing or materials are required, contact the Administrative Assistant. ATTACHMENTS Debriefing Notes COMMUNICATIO!ls NETWORK TSC CONTROL POINT ADMIN. TRAILER 201 611 542 200 623 642 551 . NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. O Page 2 of 3 Rev. 1
EP IV-210 l Q DISCUSSION In the event of an emergency the Procedures-Training Supervisor will assume the responsibility for ensuring that all Radiation Protection personnel receive current briefing. Prior to offsite personnel being assimilated into the Radiation Protection Organization, they should receive a plant orientation. The training should include information on:
1. Current Radiation Levels .

2. Plant Procedures

3. Emergency Responses, and

4. organizational Outlines As offsite agencies and intra-company representatives begin to investigate the incident, all interviews and inquiries should be routed through the Procedures-Training Supervisor.
/
~~o Prepared '~~
/
~~Reviewed By: De rtmaf H d D te Reviewed By: _ !~~
~~/ AssisMnt to Manager Date Reviewed By:~~
~~Station Quality Assurance Engineer -~~
~~/h!'d1( 'Date k~~
~~SORC Meeting No.: bl~lI /O Date 7 [ Approved By: /<! Manager ( Sals!n GeneTating Station~~
/// 3/W ~ ' Datte l V Approved By: * * .W _
Date Manager - Emergency Preparedness O Page 3 of 3 Rev. 1
EP IV-211 EMERGENCY PROCEDURE EP IV-211 ([]) RADIATION PROTECTION COMMUNICATIONS GUIDES ACTION LEVEL This procedure may be referenced whenever the Radiation Protection Emergency Organization is activated. . RESPONSIBLE INDIVIDUAL This procedure may be initiated by anyone requiring communications with the Radiation Protection Emergency Organization. LIMITS ON AUTHORITY Release of information to off-site agencies will be at the direction and approval of the Senior Shift Supervisor /EDO. ACTION STATEMENTS 11gE INITIAL If communications between any two locations is required, compare the avail. able devices for each location. Utilize a device that is common between . both locations. Indirect communication is possible if the primary method is inoperable or overused. ATTACHPENTS Ccmmunications Devices DISCUSSION During an emergency, prompt and accurate communications will be essential. Primary and back-up devices should be available ,for all essential locations. Do not tie up communications links with unnecessarily long conversations. NOTE i l Forward all completed forms to the Assistant to Manager (SGS) . Attach any referenced completed EP's or attachments.
~~. - - - . - - - -- --.--.......------.= .......-----------------.------------------- =-- ====-..---~~
l Page 1 of 3 Rev. 1
EP IV-211 Prepared B > -
<f-Reviewed By: /O!2 6!M Dep tme ad ' Date Reviewed By: /0!M Date Il sistadt to Manager Reviewed By: # ! ' 7,7[hk Date '
~~ation Quality Assurance Engineer SORC Meeting No.: h I ~ I/l /0!27!3"/ .~~
~~' Date Approved By: # / /.3 Manager - Salem Generating Station ' Dat'e Approved By: * .~~
~~b I!Af~~
~~' Date M~~
Manager - Emergency Preparedness O O Page 2 of 3 Rev. 1
i EP IV-211 ATT. 1 O AttacanENT 1 COMMUNICATION DEVICES l LOCATION PSE&G EXT. SECURITY RADIO PAGE DEDICATED PHONE TO PRIVATE OUTSIDE PHONE control Room 1 633 No Yes TSC Control Room 2 641 No Yes TSC Senior Shift Supervisor's Office 635 Yes Yes TSC Local, State Police, NAWAS 935-2415 201 NRC-Operations,
14. 200 Yes Yes Health Physics 935-6191 611 642 Control Point 623 Possible Yes NRC-Health Physics No Call TSC via pay phone or local Emergency Van No Yes No No residence I
i Hancock's Bridge No Possible No No 935-7300 Call TSC via pay phone or local Helicopter No Possible No No residence 500 Main Cate 600 Yes Yes No NOTE: Home phone numbers will be attached to the Emergency Procedures in the TSC. (Addendum No. 1) . O Page 3 of 3 Rev. 1
EP IV-212
<- g EP.ERGENCY PROCEDUPE l~/ EP IV-212 PADIATION PROTECTION EPEPGENCY INVENTORY CONTROL ACTION LEVEL When either the Senior Supervisor-Radiation Protection or the Technical Supervisor of Radiatior.
Protection responsible for, inventory control deems such action is necessary. , BESPONSIBLE INDIVIDUAL This procedure will normally be implemented by the Senior Supervisor-Radiation Protection on-site or the Technical Supervisor of Radiation Protection responsible for inventory control. LIMITS ON AUTHORITY j If the inventory indicates additional supplies are required, approval from the Senior Supervisor of Radiation Protection on-site is required prior to ordering any supplies. t ACTION STATEMENTS IldE INITIAL b v
1. Contact the Inventory Control Group, preferably its Supervisor, and request them to initiate the inventory control initiation procedure.

2. Provide the Inventory Control Group with directions regarding specific items requiring inventory. If certain items are critically insufficient, a priority order may be appropriate.

3. a) A list of categories and corresponding vendors is provided in
~~; Attachment 1.~~
b) A list of vendors' phone numbers is provided in Attachment 2. c) Attachment 3 lists specific items available from the PSE&G stock-room. O Page 1 of 6 Rev. 1
~~,g . _ __. -.~~
~~EP IV-212 O ACTION STATEMENTS (CONTINUED) 115E INITIAL~~
4. When requesting inventory status, due regard to habitability of particular areas must be exercised. Specific permission to enter evacuated areas must be granted by the Senior Shift Supervisor /EDO.

5. Instruct where to forward inventory results.
COMMUNICATIONS NETWORK E CONTROL POINT 200 611 642 201 623 644 DISCUSSION _ In the event of an emergency, normal supplies will probablf prove inadequate. Quick estimation of consumption rates must be made in order to determine the quantities needed and delivery frequency for additional supplies. Early notification of supplying vendors will assist them in (,) accomodating increased demand. Provisions must be made to receive inventory, control, distribute, and reorder the materials arriving on site. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments.
~~....................... - .......----- _=_------_-= _ .............- __----__= ........~~
O Page 2 of 6 Rev. 1
EP IV-212 O , Prepared B w - Reviewed By: 1 7'
/;
pa en Head ate Reviewed By: , i Dath Assistant to Manager . Reviewed By: An u tation Quallt? Assurance Engineer
~~Date SORC Meeting No.: b/ - / / / / O/2 7!b'l Date' s~~
~~Approved By: / Manager - Sarlem Generating Station~~
///2[N ' 4) ate Approved By: *
~~I LI Manager - Emergency Preparedness Date O~~
1 1 O l l Page 3 of 6 Rev. 1
EP IV-212 ATT. 1 l l ATTACRMENT 1 [) CATEGORY VENDOR # Multichannel Analyzers 6,26,29,31 Film /TLD badges 12,20,21,33,37 Ion Chambers 1,2,11,34,40 Protective Clothing 1,2,8,10,12,19 j Decon Chemicals, Equip. & Processes 1,2,7,11,17,18,33,39 i 2,3,4,6,10,11,12,13,14,15,19,20, Radiation Detectors 21,22,26,27,29,31,34,37,38,40 Solid State Detectors 6,13,21,29,31 Dosimeters / Dosimeter Chargers 2,10,11,12,19,20,38 Counting Gases 11,24,27 H.P. Services 1,2,3,4,5,11,12,15,16,17,lP, J,36 Count Rate Meters 2,11,13,22,27,29 Radiation Monitors 2,4,6,10,11,12,13,19,22,26,27,33, 34,40 Radiation counters / Systems 2,3,4,6,7,10,11,12,13,15,20,22,26, 27,29,34,38,40 (,/ Radiation Detector Shields 3,4,11,12,13,15,19,26,27 Radiation Shielding 4,7,8,9,10,11,18,19,20 Rad Waste Equipment 3,7,14,16,17,20,39 Radiation Protection 7,12,19,32,33,36 Remote Handling Equipment 10,16,19 Air Samplers 4,12,33 Semiconductors 13,29 Shielding 8,10,13,19,20 counter / Detector Tubes 4,10,11,12,13,22,34,38 Whole Body R/A Counters 3,13,15,20,33 Computers 6,9,15,26,29 Batteries 21 1 Respiratory Protection 25,35 I sI Page 4 of 6. Rev. 1
EP iv-212 ATT. 2 ATT^ ara,12 ! O DME L PHONE NUMBER l O 3R VACY A T F0RMATION 1 O Page 5 of 6
EP IV-212
~~-- - _ _ _ _ ._ ATT. 3 _ . _ _ . .~~
p ATTACHMENT 3 V STOCK ITEMS ITEM CODE ITEM DESCRIPTION ITEM CODE ITEM DESCRIPTION 22-2344 Protector Hearing 22-2675 Respirator Disposable 22-2345. Coverall Cotton Yel 44 22-2692 Rope Poly Yellow & Red 22-2347 Coverall Cotton Yel 48 22-2724 Stanchion Weighted Base 22-2348 Coverall Cotton Yel 52 22-2725 Suit Nuclear Large . 22-2349 Coverall Cotton Yel 56 22-2726 Suit Nuclear X-Large 22-2354 Filtr Radionuclid Resp 22-2727 Suit Acid 2 Pc w/ hood 22-2385 Glove Vinyl AR-3000 22-2731 Sheeting FR-2016 22-2386 Glove. Vinyl AR-3000 22-2732 Sheeting White Plastic 22-2388 Glove Flannel A-124 22-2734 Sh't'g Yel Poly 18X150 22-2389 Glove Latex Anti-C 9 22-2735 Sht Yel Herc 54x100 22-2390 Glove Latex Anti-C 11 41-0325 Battery 22-1/2V 5156 22-2401 Glove Cotton 12 OZ 41-0327 Battery 915 AA EDC 22-2451 Head Assy Air Sampler 41-0329 Battery Unit Cell D 22-2455 Hood Cotton Anti-C Yel 41-0331 Battery 1-1/2V 735 22-2590 Liner Glove Anti-C Wh 41-0332 Battery Pack FL LT 23 22-2591 Liner cap Anti-C Yel 41-0333 Battery 1-1/2V E93 22-2276 Bag Plastic Yel 12X18 41-0334 Battery Mallory RM42R 22-2277 Bag rtastic Ye1 18X24 41-0335 Battery 2.7V Maltr132R 22-2278 Bag Plastic Yel 35X55 41-0337 Battery 3V Ever W-356 22-2281 Brick Virg Lead L.248C 41-0338 Battery 8.4V Mal TR146 22-2289 Boot Rubber Size 11 41-0341 Battery 9V Ever #1222 22-2290 Boot Rubber Size 12 41-0347 Battery AAA #49F1170 22-2292 Booty 17" Yellow Disp 41-0348 Battery 4.5V MW-1306 22-2295 Blanket Lead Wool RA130 41-0349 Battery Mercury 49F423 22-2296 Blanket Lead L136AY.S 41-0350 Battery 6V Rayovac 918 22-2305 Coat Lab Ye1 Dac 38/40 41-0351 Battery 1.35v 49F500 22-2304 Coat Lab Yel Dac 42/44 41-0352 Battery .10V TR136R-8 22-2307 Coat Lab Yel Dac 46/48 41-0353 Battery 7.5V Type 7211 22-2308 Coat Lab Tyvek Disp 22-2310 Cap Surgeon Disposable 22-2313 Cap Top Guard 22-2314 Cap Suspension Top Gu 22-2316 Cap Sus Top Grd DK82797 22-2317 Cover Shoe Yel Disp 22-2335 Coverall Tyvek Disp 22-2336 Coverall Cotton Yellow 22-2647 Pad Step-Off 22-2651 Shroud Inner W-5051 22-2652 Shroud Outer W-5055 22-2653 Shroud Inner W-2815 n 22-2654 Shroud Outer W-5053 1 k)\ j Page 6 of 6 Rev. 1
EP IV-301 EMEPGENCY PROCEDURE EP IV-301 (s) s- INTERIM POST-ACCIDENT PRIMARY COOLANT SAPPLING APPLICATION After a reactor accident in which a significant fraction of the core fission-product inventory is released, normal sampling will not be possible because of the extremely high radiation fields. The Sentry High Radiation Sampling System will be used for obtaining diluted and undiluted samples and performing certain in-line analyses during accident and conditions. Until this system is operational, the interim post-accident sampling system can be used to withdraw a single diluted reactor coolant sample under accident conditions. Either of two (2) reactor coolant hot legs or either of the RHR's can be sampled utilizing the Interim System. Sampling is performed by purging a temporary sample line from the outlet of a sample cooler to a shielded waste bottle. A four-way valve captures approximately 0.09 ml of the sample in this line. When the valve is rotated 90*, dilution water flushes the sample into a serum vial. The 1:100 diluted sample is used for hydrogen and boron analyses. The gas phase is analyzed for hydrogen and fission gas and the liquid phase is analyzed for boron and other fission products. The procedure considers fission gas, hydrogen, and the high radiation fields. Design bases of the interim system are provided in Attachment 1. ('] ( 8PPARATUS Details for fabrication and a list of material required for the interim system are provided in Attachment 2. PRECAUTIONS
1) Post-accident reactor coolant is extremely radioactive. Gases released from the sampling operation will be mostly hydrogen and fission gases. Airborne fission gases could result in extremely high radiation fields and hydrogen collected in waste bottles without a inert cover gas may result in an explosive mixture. The relatively small amount of halogen gases can cause very significant contamination problems.

2) Avoid cross-contamination by disposing of labware as radioactive waste. Any droplets of liquid from this operation will result in high surface contamination.

3) Frequently change rubber gloves when diluting and analyzing samples.
NOTE Normally, the Chemistry Counting Room would be designated the " hot" lab. In the event of an accident, the Radiation Protection Counting Room is more likely to retain a low background. Inform requestors where to deliver samples. () A separate procedure shall be used for sample collection and handling until it is delivered to the appropriate counting facility. Page 1 of 26 gey. 1
\
l l IP IV-301 l l l (]) EPERE0VISITES M INITIAL ( A. RADIATION PROTECTION i i 1. Verify that Radiation Protection has a high range (0 - 1000 R/hr) , survey meter for surveying all sampling and analysis operations.
2. Verify all personnel are wearing protective clothing, required respirators, and dosimetry as specified by Radiation Protection.

3. Verify that all personnel have been thoroughly briefed by Radia-tion Protection as per EP IV-106, "ALARA Task Review Instructions".
~~2 i B. FUME HOOD PREPARATf0N i j j~~
/]
~~(_- 1. Perove all non-essential equipment from the fume hood which is to 4 be used for sample dilutions and analyses. i~~
2. Assemble a body shield in the fume hood using leak bricks. A stack of 2 X 4 X 8 inch lead bricks, five high and three long will supply adequate shielding.

3. Place a metal tray within the fume hood to contain all dilution and analysis liquids.
4
~~4. . Place a box of tissue inside the fume hood.~~
Tape a yellow poly bag within the fume hood with the top of the S. bag cut approximately two inches. The bag is to be used for containing all solid waste material generated during dilution 1 operations. j () 6. Place a strip of blotter paper in front of the fume hood and tape the edges to the floor. Page 2 of 26 Rev. 1
I EP IV-301 PREREQUISITES O IIME INITIAL B. FUME HOOD PREPARATION (CONTINUED)
7. Place several pairs of rubber gloves on the lip of the fume hood in a position to permit easy and fast donning.

8. Prepare a shielded waste container for disposal of waste sample' solutions.
~~C. FUME HOOD APPARATUS AND REAGENTS~~
~~1. Verify the following apparatus and reagents are available for performing boron analysis.~~
a) Fisher Accumet pH meter [ b) Three (3) Nalgene 30-ml plastic beakers filled with 4.5 ml of demineralized wat er c) Eppendorf or oxford 1-m1 pipette and tips d) oxford adjustable 1-5 ml pipette and tips el oxford 500 ul pipette and tips l f) Demineralized water l g) Fluoroborate Specific Ion Electrode h) Plastic Single Junction Reference Electrode
~~1) Stopwatch for timing analyses j) Saturated Sodium Fluoride Solution k) 10 N Sulfuric Acid~~
() 1) 20 ppm Boron standard m) Magnetic stirrer and microstirring bar - n) Current calibration curve Page 3 of 26 Rev. 1
EP IV-301 () PREREQUISITES (CONTINUED) IlgE INITIAL C. FUME HOOD APPARATUS AND REArENTS (CONTINUED)
2. Soak the electrodcs in demineralized water for at least 10 minutes, or as long as possible prior to use.

3. Standardize the fluoroborate system using the relative millivolt mode as detailed in Procedure PD-3.2.080.

4. Verify the following apparatus is available for performing gas sampling and dilution.
~~a) Snare for rumple transfer f-'g b) I cc and 5 cc gas syringes V c) 67 ce gas dilution bulb d) 5 ce gas counting vials e) Plastic wrap~~
~
~~5. Verify the following apparatus and reagents are available for performing liquid sampling and dilution.~~
a) Crucible tongs b) Tweezers c) 25 ul Oxford pipette and tips d) 100 ul Oxford pipette and tips e) 250 ul Oxford pipette and tips () ~ f) 500 ul Oxford pipette and tips g) Liquid counting vials, filled with 10 ml of demineralized water Page 4 of 26 Rev. 1
EP IV-301 PPEREOUISITES (CONTINUED) TIME INITIAL C. FUME HOOD APPARATUS AND REAGENTS (CONTINUED) h) Plastic wrap , i) 100 ml volumetric flask, filled with demineralized water D. GAS CHROMATOGRAPH
1. Place several lead bricks on the lab bench near the gas chromato-graph *or sample shielding.

2. Verify that a sufficient supply of argon carrier gas is available to the gas chromatograph.
~~O 3. Verify that the gas chromatograph is in a Standby condition with a current calibration check performed prior to initiating sampling.~~
~~4. Verify the following items are available near the gas chromato-graph.~~
~~a) 100 and 1000 ul gas syringes b) Yellow poly bag containing absorbent material~~
. c) Cord or tape d) Snare and tongs e) Calibration curve O )
Page 5 of 26 Rev. 1
EP IV-301 () PREREQUISITES (CONTINUED) IldE INITIAL E. POST-ACCIDENT SAMPLING SYSTEM
~~1. Open or check open the following valves:~~
~~a) Valve il b) Valve #2 c) Valve #4 d) Gas vent line isolation valve~~
2. Align, Valve #3 to the horizontal position.

3. Back purge the waste bottles with an inert gas for a minimum of five minutes.

4. Close Valve #2 and #4. .

5. Close the gas vent line isolation valve.

6. Secure inert gas supply.

7. . Verify the following items are available for the Post-Accident Sampling Systems
. a) Lab jack b) 5 cc syringe with needle c) 20 cc syringe d) Stopwatch e) Wood block with sample bottle Page 6 of 26 Rev. 1
EP IV-301 Q PREREQUISITES (CONTINUED) 11gi INITIAL E. POST-ACCIDENT SAMPLING SYSTEM (CONTINUED) f) Adjustable wrench ; g) 7/16 inch open end wrench h) 11/16 inch open end wrench PROCEDURE TIME INITIAL A. SAMPLING TEAM NO. 1 () 1. Enter the primary sample room and verify that the reactor coolant sampling system is isolated at the containment penetration valves, 1(2)SS104 and 1(2)SS33.
2. Check for green closed indication lights for valves ll(21)SS32, 13(23)SS32, 11(21)SS22, and 12(22)SS22 on Panel 307-1(2).

3. Attach the syringe containing 15 ml of DM water to the sample dilution line. Ensure that the diluter valve, valve 83, is in ,
~~the up/down position. Force enough water from the syringe to allow water to flow from the hypodermic needle in a solid stream~~
~~, at the needle tip. Ensure that 9.0 ml of water remains in the syringe. . NOTE See Figure 1 in Attachment 2 for valve identification.~~
~~4. Switch the diluter valve, Valve 83, to the horizontal position to~~
[ s- accept sample flow when the isolation valves are opened. l l Page 7 of 26 Rev. 1
l l
\
~~EP IV-301 () PROCEDURE (CONTINUED) IlgE INITIAL S. Position the sample vial in the wooden block holder into position~~
~~under the needle at the dilute.r valve. Use a lab jack or other supporting objects as appropriate.~~
~~6. Visua?.ly verify that the needle has punctured the septum.~~
~~Evacuote the Wheaton sample bottle with a gas syringe. a~~
7. Step back from the sample static- and carefully position the syringe in the designated holder with the s ample dilution line fully extended from the sample station.

8. Actuate the switch to raise the sample transfer dumbwaiter to the sample room position. If the equipment is inoperable, notify supervision to have a carrier on standby to hand carry the sample g to the laooratory.
t
9. Close or check closed valve 1(2)SS24 and 1(2)SS35.

10. Open the reactor coolant primary sample si.1k Valve No. 1(2)SS46 to relieve pressure on the sample line. Break the sample line connection on the outlet of the sample cooler and reconnect the temporary line of the emergency sampling system.
CAUTION l , When reconnection is made, use extreme care not to cross-thread the fitting. The connection should be tightened securely to avoid any leak-age of the highly radioactive liquid flowing through this line. i l
~~11. Inspect the sampling system. Ensure all fittings are tight.~~
O
~~12. If either RHR is to be sampled, proceed to Step 14.~~
Page 8 of 26 Rev. 1
EP IV-301 (G_,/ PROCEDURE (c0NTINUED) 11ME INfTIAL
13. If either RCS hot leg is to be sampled, request the Control Rcom operator to open the containment isolation valves, 1(2)SS104 and 1(2)SS33. Open valves No. 1, 1(2)SS35, and No. 2. Open the reactor coolant sample panel isolation valve 11(21)SS32 or ,
~~13(23)SS32, depending on which hot leg is to be sampled. Check for red light open position indication at sample panel 307-1(2) . Proceed to Step 16. MONITOR DOSE RATES.~~
14. For a RHR heat exchanger outlet sample, open valve 1(2)SS24.

15. Open valves No. 1 and No. 2. Open RHR Heat Exchanger Outlet f Sample Isolation valve ll(21)SS22 or 12(22)SS22, depending on which heat exchanger is to be sampled. Check for red light open
~~\- position indication at sample panel 307-1(2).~~
~~MONITOR DOSE RATES.~~
16. Crack open valve No. 4. Rapidly adjust the flow rate to approximately 0.42 gpm on the flow meter. Observe the flow meter from outside the cubical using the mirror mounted on the opposite wall.

17. Note the time that flow was established and immediately exit the
~~. sample room. Relay the sample time to Team No. 2 so that the sample can be collected after a three minute purge.~~
~~B. SAMPLING TEAM NO. 2~~
1. Af ter the sample line has purged to waste for approximately three minutes, isolate the sample by rotating the diluter valve (Valve No. 3) 90* and immediately deliver 9.0 ml of water using the C-)' syringe, and secure flow with Valve No. 4, then rotate Valve No. 3 90* using the valve reach rods.
Page 9 of 26 Rev. 1
EP IV-301 1 ((() PROCEDURE (CONTINUED) , IldE INITIAL
2. Observe the flow meter using the wall mounted mirror and verify no flow.

3. If RCS is sampled, close reactor coolant sample panel isolation valve 11(21)SS32 or 13(23)SS32, if RHR heat exchanger outlet is sampled, close RHR sample isolation valve ll(21)SS22 or 12(22)SS22 and immediately exit the sampling room.

4. Immediately after exiting, notify the Control Room operator to close containment isolation valves 1(2)SS104 and 1(2)SS33 for RCS sample.
~~C. HYDROGEN ANALYSIS AND TRANSFER - TEAM NO. 3 () 1. Immediately lower the septum bottle from the needle. Hold the wooden block with one hand during this operation.~~
~~2. Place the sample behind several lead tricks on the lab bench near the gas chromatograph.~~
~~' 3. Using a gas syringe, withdraw a 100 ul or 1 ml aliquot directly from the serum bottle.~~
CAUTION ! Keep the needle tip well above the liquid level so that only the gas is withdrawn. Page 10 of 26 Rev. 1
EP IV-301 (]) PROCEDURE (c0NTINUED) 11gi INITIAL NOTE Assuming a 6.09 ml diluter value volume and a 8.0 mi serum bottle gas space, the following hydrogen concentrations should be expected: cc H 2 /kg nH 2 100 0.11 . 500 0.56 1000 1.12 2000 2.25 5000 5.62
~~4. Inject the sample into the gas chromatograph and record the aliquot in Step No. 1 of the Dissolved Hydrogen Data Calculation Sheet in Attachment No. 3.~~
~~( NOTE A 100 ul injection will' result in approximately~~
*1.4 pci of gaseous activity being released by the gas chromatograph to the room one hour after the accident.
5. Place the sample vial into a yellow poly bag containing absorbent material. Tie the bag closed with cord or use tape to close the I bag.

6. Leave the sample room or chemistry laboratory and notify j laboratory personnel that the sample is ready for dilutions and analysis.
~~I l~~
~~7. Af ter approximately 20 minutes, hav@ u ne person enter the primary sample room and collect the chromatcty;aph for evaluation.~~
O 8. Calculate the approximate hydrogen concentration using the , Dissolved Hydrogen Data Calculation Sheet in Attachment No. 3. t Page 11 of 26 Rev. 1 ,
EP IV-301 a (]) PROCEDURE (CONTINUED) TIME INITIAL
9. After several days or when Radiation Protection determines DATE TIME conditions are safe, open the gas vent valve and allow the highly radioactive gases in the bottle to escape into the operating fume hood. ,
~~1< j D. ANALYSIS AND SAMPLE DfLUTION~~
~~1. Initial Operations a) Using a snare, transfer the sample behind the lead bricks inside the fume hood.~~
b) Remove the wooden block from the poly bag and place the r block mehind the lead bricks. fs V c) Take radiation readings at the front of the fume hood. NOTE Steady the wooden block with one hand as appropriate while withdrawing samples from the vial.
~~2. Gaseous Activity 1,~~
a) Withdraw a 1.0 ce gas aliquot from the gas in the serum bottle using a 5 cc Hamilton syringe. Inject the sample aliquot into a 67 ce gas dilution bulb. l b) Evacuate a gas counting vial. Inject a 1.0 cc aliquot (or l smaller) of the diluted gas into the vial for counting. O c) Record the injected aliquot (cc) in Step No. 3 of the Gaseous Activity Data Calculation Sheet. I Page 12 of 26 Rev. 1
EP IV-301
~~/~'\ PDOCEDURE (c0NTINUED)~~
~~V g INfTfAL 1 d) Wrap the counting vial in plastic wrap. NOTE , 2 The vial will contain a 0.14 uCi under worse~~
~~case conditions.~~
~~e) Analyze the sample for fission gas activity. NOTE If the dead tLme on the MCA is excessive, increase the lower level discriminator 133~~
~~setting to bias out Xe activity and recount. Prepare a second sample for Xe~~
() using a 0.1 cc aliquot from the 67 dilution bulb with the lower level discriminator at the normal setting. I i f) Calculate the gaseous activity level using the Gaseous Activity Data Calculation Sheet in Attachment No. 3. l l
~~3. Isotopic Liquid Sample Analysis NOTE Ensure that the hydrogen results are accept-able before proceeding with this step.~~
a) Hold the wooden block with one hand and remove the septum cap using crucible tongs. Lower the glass shield on the fume hood and remove the septum using tweezers. Discard the septum cap and septum as radioactive waste. Close the fume hood. O Page 13 of 26 Rev. 1
~~. _ . .-~. - - - _ _ - --~~
~~EP IV-301~~
~~~ - -- .~~
PROCEDURE (CONTINUED) 11g1 INITIAL b) After approximately five m'nutes, open the fume hood. Pipette a 25 ul aliquot into the previously filled 100 ml volumetric flask. Discard the tip as radioactive waste. Cap and flask and carefully mix. , c) Pipette 100 to 500 ul of the second dilution into the
, previously filled counting vial and dis. card the tip. Cap the vial and wrap with plastic wrap. Record the aliquot volume pipetted into the counting vial in Step No. 3 of the *iquid Activity Data Calculation Sheet.
d) Remove the vial from the hood and wrap with plastic wrap a second time. e) Count the sample on the MCA. I O f) Calculate the original sample activity using the Liquid Activity Data Calculation Sheet in Attachment No. 3.
4. Sample for Boron Analysis a) Carefully place the tip of the 500 ul pipette into the serum bottle and pipette 500 ul of the sample to each of the 30 mi beakers containing 4.5 ml water. Discard the, pipette tip as radioactive waste.
~~1 l~~
~~! b) Analyze the duplicate samples for boron using procedure P D- 3. 2. 0 8 0.~~
c) Calculate the ppm boron in the original sample using the Boron Data ~41culation Sheet in Attachment No. 3. O l Page 14 of 26 Rev. 1 l
EP IV.301
~~/ CALCULATIONS See Attachment No. 3.~~
ACCEPTANCE CRITERIA N/A REFERENCES NUREC 0578 and Ni<C Clarification letters dated October 13, 1979. NOTE Forward all completed forms to the Assistant to Manager (SGS). Attach any referenced completed EP's or attachments. Prepared By: /M o_ " vi-Reviewed By: _
~~/ O!d [a k/~~
~~F D pa~r 4en Head / Datd Reviewed By: /O 0 I _s to Manager Date~~
~~/ /~~
Reviewed By: w ((/7/7lfhf 8 Datt Station Quality Assurance Engineer SORC Meeting No.: b l ~' l8l /C 7 I Dat'e Approved By: / ///_6/M Date~ Manager - S41em Generating Station Approved By: * . t I O EL k Manager - Emergency Preparedness Date' O l { l L Page 15 of 26 Rev. 1
~~. _ . . . ~ . . . - . . - - . _ - . .. - -- - .. . _ . . _ . - - _ _ _ _ _ _ - . - _ . _ . . _ . - .~~
~~n. . - . _ . - . _ _ ~~~
EP IV-301 l l s ATTACHMENT 1 (]) DESIGN BASES FOR INTERIM SAMPLING SYSTEM PARAMETER VALUE No. of post-accident sample 1 i t i Hydrogen 2000 cc/kg i Radioactivity in diluted sample 900 uCi [ 1
~~Dose rate of diluted sample~~

Unshielded: 1350 R/hr at 1 ems 356 mR/hr at 2 ft. 1 Shielded with 2 in. lead: 67 R/hr contacts 18 mP/hr at 2 ft. Purge Volumes i Inactive purge 3.0 gal., max ) Post-accident liquid 1.26 gal., max s t i Maximum total of gas generation in waste - 10400 cc 9 25C Estimated pressure in waste gas container 31 psia l Estimated hydrogen concentration in waste gas 32.4 V/o Dose rate of: Waste with 1.26 gal in sand-packed drum 9 10 ft, with 4 in. 94 mR/hr of lead and 9 in, of concrete. 4 ft. of 1/8 in. sample line 9 2 ft. with equivalent of 238 mR/hr j 2 in. of lead. 6 ft. of 1 in. Tygon vent line for gases e 4 ft. from waste bottle with no shielding, I hour after accident: ; 4 No Dilution 55.9 R/hr 1:3 Dilution 18.6 R/hr Three teams are required to perform the entire sampling operation. Ea-h team consists of a Chemistry sampler and a Radiation Protection person, i ..I i l Page 16 of 26 Rev. 1
~~. _ _ . , _ . . . - . _ , . . ~ _ . , _ _ _ _~~
~~EP IV-301 ATTACHMENT 2 O FABRICATION AND MATERIALS f!EEDED FOR THE INTEP.lM SAFPLING SYSTEM 1~~
1. Design Figures 1 through 4 illustrate the basic sampling design.

2. Fabrication .
Fabricate the interim post-accident sampling system as illustrated in Figures 1 through 4 Ensure that the following are taken into account. 4 (1) Purge the waste 11guld and gas bottle with inert to provide &n inert atmosphere , during post-accident sampling, as the explosive limit for hydrogen could be exceeded. (2) Measure the active volume of the four-way diluter valve prior to installation. This may be accomplished by filling the valve with a 100 ppm chloride standard solution and diluting with 9.0 ml of water to make a 1 ppm sample for analysis using the spectrophotometric chloride method. Perform three measurements and calculate the i average volume of the diluter valve from I V d
* (Av9. ppm chloride measured) X 9.0 ml/100 ppm O (3) Pack the diluter valve and associated piping in three inches of lead shot.
(4) Drill a wooden block approximately two feet long at one end so that.the Wheaton sample bottle fits with approximately one inch extended above the top of the block. Clue the bottle into the block holder.
~~3. List of Materials obtain the following materials for f abricating the interim post-accident sampling system:~~
~~JNTERIM SAMPLING SYSTEM~~
1. Waste sottles, 5 gal. ................................................................. 2

2. Steel drums ............................................................................ 2

3. Lead bricks, 2 X 4 X 8 in. ........................................................... 144 4 Lea d s ho t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A s R equ i r ed

5. Tygon tubing, 1 in. .......................................................... As Required

6. Isolation valve for vent ............................................................... 1

7. 1/8 in. OD 0.035 in ID SS caps tubing for sample lines ....................... As Required

8. 40 in, reach rod for valves ............................................................ 1

9. 20 ce syringe with Luer-Loc tip graduation to 0.2 ml (Hamilton No.1020TSS) ........... 1 l
~~O 10. 11. Hypodermic needle, point style No. 2 16 gauge X 4 in. (Hamilton No. N716) ............. 2 Lat jack, 3 x 3 in base, or appropriate support material for wood block .............. 1~~
12. Whitey 4-way ball valve (SS-43YHF2 3-43-00125) ......................................... 1 Page 17 of 26 Rev. 1
*P IV-301 ATTACHPENT 2 ~
~~(CONTINUED)~~
~
~~INTERIM SAM? LING SYSTEM (CONTINUED)~~
~
13. Vent line outlet isolation valve ...................................................... 1

14. Radiarm, 60 in. (Atomic Products No. 010-060) .........................................1,

15. Radiarm, 48 in. (Atomic Products No. 010-048) ......................................... 1

16. Wheaton sample vials, 16 ml (No. 224806) ............................................ Case

17. Wheaton open top screw caps (No. 240515) ............................................ Case

18. Wheaton solid screw caps (No.18-425) ............................................... Case
~~] 19. Wheaton septa, 13 X 20 (No. 240585) ................................................. Case~~
~~20. CTFE tube fittings and washer -~~
~~1/4 X 20 for 1/8 in. OD tubing (Hamilton No. 88807) ...................... Pack of 10 Spare washers (Hamilton No. 88826) ....................................... Pack of 10~~
21. CTTE female Luer connector 1/4 X 28 0.060 in. bore (Hamilton No. 12834) ................ 2

22. Male Luer connector 1/4 X 28 0.060 in. bore (Hamilton No. 328825) ...................... 2

23. TFE tubing, 1/8 in. CD X 1/16 in ID (Hamilton No. 88922) ........................... 10 ft.

24. Planging tool kit (Hamilton No. 88821) ................................................. 1

25. Wood block with bore for 16 ml Wheaton sample bottle, 24 in. long ...................... 2 l
~~O SAMPLING AND DILUTION~~
1. Lead bricks, 2 X 4 X B in. ........................................................... 24

2. Crucible tongs modified with red rubber hose over tips ................................ 1

3. Tweezers ............................................................................... 1

4. Volumetric flask, 100 ml .............................................................. 1

5. Eppendorf or Oxford micro pipetting. system with disposable tips for 25, 100 and 50 ul .2

6. Eppendorf or Oxford macro pipetting system with assorted tips for 1 and 4 ml .......... 1

7. Na lg ene be akers , pla s tic , 3 0 ml in holde rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

8. Waste bottle, shielded with funnel in top ............................................. 1

9. Wash bottle ............................................................................ 1

10. Gas dilution bulb, 67 cc with septum .................................................. 1

11. Gas counting vial .....,................................................................ 2

12. Liquid counting vials .................................................................. 2

13. Plastic wrap ..................................................................... 1 roll

14. Mirror ................................................................................ 1

15. Poly bags .................................................................... As Required

16. Snare .................................................................................. 2
~~. 17. 5 cc Hamilton gas syringe (Hamilton No.1005TLL) ...................................... 1~~
18. I cc Hamilton gas syringe (Hamilton No. 100lTLL) ...................................... 1

19. Hypodermic needles, point style No. 2 (22 gauge X 2 in. No. N722) ...................... 4
( Page 18 of 26 Rev. 1
_ _ _ = . _ _ _ _ _ _ _ . . _ _ _ _ _ _ . . __ _ _. _ _ _ i E? IV-301 l Q ATTACW.ENT 3 1 STEP RECORD i 1. Microliters of sample injected into the gas chromatograph.
2. Chromatograph peak area in millimeters.

3. Microliters of H C Yre8ponding to peak area.
2
4. Divide microliters in Step No. 3 by microliters in Step No. 1 and multiply by 100 to determine t H 2*

5. Multiply 4 H2 in Step No. 4 by 900 to yield ccH 2/Kg. ,
~~FORMULA~~
~
~~tH 2X 10 X Vg(cc) ccH2 /X9 " Vd (ml) X 10-3(Kg/ml) 1 Where: 10' converts percent to a decimal V = 8 cc, serum bottle gas space g Vd = 0.09 ml, diluter valve volume~~
~~-3 10 converts m1 to kg i~~
~~REDUCED FORMULA ccHy /Kg = 4 H X 889 2 I i i i i Page 19 of 26 ,,y, y j~~
~~P IV-301~~
~~" - " - - + ew e f .- .w,-_~~
~~t ATTACHPENT 3 O (CONTINUED) l I RECORD STEP~~
~
~~1. Mierocuries/cc of isotope measured.~~
4
2. Multiply Step No. 1 value by 3.0 X 10 .

3. Record aliquot injected into the counting vial (cc).
~~I 4. Divide Step No. 2 value by Step No. 3 value to yield pCi/ml. 1 1 i FORMULA~~
~~Gaseous activity, DCi/ml =~~
Vd(ml) X Vg (cc) XV3(cc) i Where: V = 8 cc, serum bottle gas space 9 () V2 = 67 cc, dilution bulb volume i V4 = 5 cc, counting vial volume Vd = 0.09 al, diluter valve volume Vy = 1.0 cc, aliquot injected into dilution valve t ' V 3 = X cc, aliquot injected into counting vial REDUCED FORMULA uCi/ml = pCi/cc X 29,778 - 3 i I I { i i l Pace 20 of 26 ,, , y
~~.~ . - - . - . . - - . . . . . ~ . . . - _ . . _ . _ - . - . -- . . - _ - . ._. .- . - _ _ _ _ . = _ - -- ,~~
EP IV-301 'l ATTACHPENT 3 a () (CONTINUED) STEP RICCRD t
~~1. Microcuries/ml of isotope measured.~~
6
2. Multiply Step No. I value by 4.0 X 10 ,

3. Record aliquot volume (ml) pipetted into counting vial.

4. Divide Step No. 2 value by Step No. 3 value to yield UCi/ml.
~~l j 4~~
~~FORMULA i Liquid Activity (pci/ml) =~~
~~uCi/ml measured X iV (ml) XV3(ml) X V 5 I"II V d I"1I~~
Y2 ("II

Y 4 (* I t
Where: Vg = 9.0 ml, syringe water volume V3 = 100 m1, volumetric flask volume v = 10 ml, counting vial volume 5 Vd = 0.09 m1, diluter, valve volume V = 0.025 m1, aliquot delivered to volumetric flask 2 v4 = X m1, aliquot pipetted into counting vial f i REDUCED TORMULA l i uCi/ml = pCi/ml measured X 4.0 X 10 6 V < 4 i l 1 . 4 i i Page 21 of 26 ,,,y, g
~~. . . _ . .~. ._. . .. . _ _ _ . _ _ . _ _ . . ._. _ . _ . _ _ _ _ _ . . _ _ . . . _ .~~
d EP IV-301 ATTACiffliT 3 (CONTINUED) i - STEP PICORD 1 i 1. Boron concentration measured (ppm).
~~2. Multiply Step No. 1 value by 1,000 to yield ppm boron in sample.~~
~~FORMULA~~
~~! ppm Boron Concentration = ppm Boron measured X gV (ml) X V3 (ml) *Y Vd("l) 2I "1I 4~~
i Where: Vg = 9.0 ml, syringe water volume V3 = 5.0 ml, final sample volume i Vd = 0.09 ml. diluter valve volume l V = 0.50 m1, sample aliquot 2 REDUCED FORMULA i i ppm Boron concentration = ppm Boron measured X 1,000 3 J J ) 1 a ! i O Page 22 of 26 . Rev. 1 1
~~, . - , . - . - _ . - . _ _ - - . . . - , . .. .. .-..I~~
~~. . _ - _}}~~

ML20041D263

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