Text

Document Transmittal Form, EPIP059, List of Updated Documents, Table of Contents - Figure 1-2
	ML030410289
Person / Time
Site:	Salem, Hope Creek
Issue date:	01/31/2003
From:	; Public Service Enterprise Group
To:	David Pinckney; Document Control Desk, Office of Nuclear Security and Incident Response
References
	EPIP059
	Download: ML030410289 (158)
	v • d • e

PSEG NUCLEAR ONSITE IMPLEMENTING PROCEDURES January 31, 2003 CHANGE PAGES FOR REVISION #29 The Table of Contents forms a general guide to the current revision of each section of the Onsite EPEPs. The changes that are made in this TOC Revision #29 are shown below. Please check that your revision packet is complete and remove the outdated material listed below:

ADD REMOVE Paae Description Rev. Paqe Description Rev.

Paae ALL TOC 29 ALL TOC 28 All NC. EP-EP.ZZ-0101 02 All NC.EP-EP.ZZ-010! 01 All NC.EP-EP.ZZ-0202 05 All NC. EP-EP. ZZ-0202 04 All NC. EP-EP.ZZ-0203 04 All NC.EP-EP.ZZ-0203 03 All *SC EP-EP.Z--0205 03 All SC.EP-EP.ZZ-0205 02 All *HC.EP-EP.ZZ-0301 03 All HC.EP-EP.ZZ-0301 02 All *SC EP-EP.ZZ-0301 04 All SC.EP-EP.ZZ-030L 03 All NC.EP-FD-.ZZ-0304 07 All NC.EP-EP.ZZ-0304 06 All NC.EP-EP.ZZ-0305 02 All NC.EP-EP.ZZ-0305 01 All NC.EP-EP.ZZ-0306 01 All NC.EP-EP.ZZ-0306 00 All NC.EP-EP.ZZ-0311 03 All NC.EP-EP.ZZ-0311 02 All NC.EP-EP.ZZ-0312 04 All NC.EP-EP.ZZ-0312 03

NOTE: SC.EP-EP.ZZ-0205(Q) goes behind the green 205 tab HC.EP-EP.ZZ-0301(Q) goes behind the blue 301 tab SC.EP-EP.7.Z-0301(Q) goes behind the green 205 tab EPEP-AIJ1ofJ 1 of 1

EPIP T.O.C.

Pg. 1 of 2 PSEG NUCLEAR LLC PSE&G EMERGENCY PLAN ONSITE IMPLEMENTING PROaTFM-M TABLE OF CONTENTS U,UII 0UL January 31, 2003 O #

Revision Number Effective Number Pages Date NC.EP-EP. ZZ-0101 (Q) ACTIONS REQUIRED AT 02 is 01/31/2003 UNAFFECTED STATION NC.EP-EP.ZZ-0102(Q) EMERGENCY COORDINATOR 05 22 10/11/2002

RESPONSE

NC.EP-EP.ZZ-020 (Q) TSC - INTEGRATED 05 23 07/31/2002 ENGINEERING RESPONSE NC.EP-EP.ZZ-0202 (Q) OPERATIONS SUPPORT 05 28 01/31/2003 CENTER (OSC) ACTIVATION AND OPERATIONS NC.EP-EP.ZZ-0203 (Q) ADMINISTRATIVE SUPPORT/ 04 17 01/31/2003 COMMUNICATION TEAM RESPONSE - TSC EPIP 204H EMERGENCY RESPONSE 57 26 11/22/2002 CALLOUT/PERSONNEL RECALL EPIP 204S EMERGENCY RESPONSE 57 25 11/22/2002 CALLOUT/PERSONNEL RECALL HC.EP-EP.ZZ-0205 (Q) TSC - POST ACCIDENT 03 39 02/06/2002 CORE DAMAGE ASSESSMENT SC.EP-EP.ZZ-0205 (Q) TSC - POST ACCIDENT 03 82 01/31/2003 CORE DAMAGE ASSESSMENT HC.EP-EP.ZZ-0301 (Q) SHIFT RADIATION 03 21 01/31/2003 PROTECTION TECHNICIAN

RESPONSE

SC.EP-EP.ZZ-0301(Q) SHIFT RADIATION 04 35 01/31/2003 PROTECTION TECHNICIAN

RESPONSE

EPIP-TOC-COMMON Rev. 29

EPIP T.O.C.

Pg. 2 of 2 PSEG NUCLEAR LLC EMERGENCY PLAN ONSITE IMPLEMENTING PROCEDURES TABLE OF CONTENTS January 31, 2003 Revision Number Effective Number Pages Dare NC.EP-EP.ZZ-0302 (Q) RADIOLOGICAL ASSESSMENT 05 19 07/03/2002 COORDINATOR RESPONSE NC.EP-EP.ZZ-0303(Q) CONTROL POINT - 02 25 07/03/2002 RADIATION PROTECTION RESPONSE NC.EP-EP.ZZ-0304 (Q) OPERATIONS SUPPORT 07 26 01/31/2003 CENTER (OSC) RADIATION PROTECTION RESPONSE NC.EP-EP.ZZ-0305 (Q) POTASSIUM IODIDE (KI) 02 10 01/31/2003 ADMINISTRATION NC.EP-EP.ZZ-0306 (Q) EMERGENCY AIR SAMPLING 01 12 01/31/2003 NC.EP-EP.ZZ-0307 (Q) PLANT VENT SAMPLING 02 13 07/03/2002 NC.EP-EP.ZZ-0308 (Q) PERSONNEL/VEHICLE 00 16 02/29/2000 SURVEY AND DECONTAMINATION NC.EP-EP.ZZ-0309 (Q) DOSE ASSESSMENT (MIDAS) INSTRUCTIONS 05 40 10/04/2002 NC.EP-EP.ZZ-0310(Q) RADIATION PROTECTION 05 43 10/04/2002 SUPERVISOR - OFFSITE AND FIELD MONITORING TEAM RESPONSE NC.EP-EP.ZZ-0311(Q) CONTROL POINT 03 18 01/31/2003 CHEMISTRY RESPONSE NC.EP-EP.ZZ-0312 (Q) CHEMISTRY SUPERVISOR - 04 26 01/31/2003 CP/TSC RESPONSE NC.EP-EP.ZZ-0313(Q) ADVANCED DOSE ASSESSMENT (MIDAS) INST.'RUCTIONS 02 34 10/04/2002 EPIP-TOC-COMMON Rev. 29

PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR LLC NC.EP-EP.ZZ-0312(Q) - REV. 04 CHEMISTRY SUPERVISOR - RESPONSE USE CATEGORY: II REVISION

SUMMARY

1. Revised name of procedure and the name of the position from Chemistry Supervisor - CP/TSC - Response to Chemistry Supervisor - Response throughout the procedure.

2. Revised the position that approves emergency plan implementing procedures from Vice President Operations to Director Operations.

3. Revised the name of Attachment 5 throughout the procedure by adding /High Activity Samples.

4. Revised the name of Figure - 1 throughout the procedure by replacing the word PASS with High Activity Samples.

5. Reworded the note after Step 5.1 for better clarification.

6. Revised Step 5.1.1 by having the Chemistry Supervisor reporting to the TSC initially.

7. Revised Step 5.1.15 to say For Hope Creek.

8. Replaced the word PASS with High Activity Samples in Step 5.1.18.

9. Added High Activity Samples to Step 5.1.27. -. . .

10. Added High Activity Samples to note after Step 5.1.33. , .;

11. Added High Activity Samples to Step 5.1.34. .

12. Added Cross References 7.2.6 through 7.2.11.

13. Deleted PAS from Salem systems.

14. Replaced PASS with High Activity Samples from Attachment 5, Step 2.0 and 2.1.

15. Clarified Step 1.1, Step 2.1, and 3.1 of Attachment 8 and Step 1.1 of Attachment 9 to say, "Ensures The Following Happens.

16. This revision satisfies the requirement for a biennial review.

17. Deleted RCS/RHR as a type of sample taken at Salem in Attachment 5. Steps 1.1 and 1.2. This type of sample is not required for Salem.

18. Indicated Step 5.1.34 and the Note prior to this step was only for Hope Creek. This is not required for Salem.

IMPLEMENTATION REQUIREMENTS:

Implementation Date /' J APPROVEDr

. Emergency Preparedness Manager bate APPROVED: - -

/Dir ctor Operations Date

NC.EP-EP.ZZ-0312(Q)

CHEMISTRY SUPERVISOR - RESPONSE TABLE OF CONTENTS SECTION TITLE PAGE 1.0 P UR P O S E ........................................................................................ .. 2 2.0 P RER E Q UIS ITES ................................................................................... 2 2.1 Prerequisites To Be Followed Prior To Implementing This P ro c e d u re ..................................................................................... 2 3.0 PRECAUTIONS AND LIMITATIONS .................................................. 2 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure ............................... 2 4.0 EQ UIPM E NT R EQ UIR E D .................................................................... 2 5.0 P R O C E D UR E .................................................................................. . 2 5.1 The Chemistry Supervisor Should Perform The Following ........... 2 6.0 R E C O R D S ...................................................................................... . . 7 7.0 R E F E R E NC E S .................................................................................. ..7 7.1 References.. ....................................................... .. 7 7.2 Cross References ..................................................................... 7 7.3 Com m itments ........................................................................... 8 ATTACHMENTS ATTACHMENT 1 Salem and Hope Creek Chemistry Systems .................................. 9 ATTACHMENT 2 Chem istry G uidelines - Power Operation ..................................... 10 ATTACHMENT 3 Chemistry Guidelines - Power Reduction ................................. 11 ATTACHMENT 4 Chemistry Guidelines - Salem Reactor Trip ................................. 13 ATTACHMENT 5 Chemistry Guidelines - PASS/High Activity Samples ................ 14 ATTACHMENT 6 Chem istry G uidelines - Outside System s ..................................... 17 ATTACHMENT 7 Chemistry Guidelines - Primary to Secondary Leak (S A LE M O N LY ) .......................................................................... 18 ATTACHMENT 8 Assembly/Accountability Instructions - Control Point .................. 19 ATTACHMENT 9 Control Point Evacuation Checklist .......................................... 21 FORMS FORM 1 - Accountability Station Attendance Sheet .......................................... 23 FIGURES FIGURE 1 - Salem High Activity Sample Storage Location ............................... 24 FIGURE 2 - Hope Creek PASS Storage Location .............................................. 26 Nuclear Common Page I of 26 Rev. 04

NC.EP-EP.ZZ-0312(Q) 1.0 PURPOSE Provide instruction and guidance to the Hope Creek/Salem Chemistry Supervisor during a declared emergency.

2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure 2.1.1 Implement this procedure at an Alert or higher event classification, at the request of the Operations Supervisor (OS), or at the request of the Emergency Duty Officer (EDO), or Radiological Assessment Coordinator (RAC).

2.1.2 Personnel who implement this procedure shall be trained and qualified in accordance with Emergency Preparedness training requirements.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure 3.1.1 Copies of additional attachments should be made to record recurring steps, as appropriate.

3.1.2 The user may deviate from following procedure steps in written order if it is thought by the user that emergency conditions warrant it.

3.1.3 It is recommended that initials be used instead of check marks, if more then one person implements this procedure.

4.0 EQUIPMENT/MATERIAL REQUIRED As provided in the Emergency Response Facility.

5.0 PROCEDURE NOTE The Chemistry Supervisor reports directly to the Radiological Assessment Coordinator (RAC).

5.1 The Chemistry Supervisor Should Perform The Following:

NOTE The Chemistry Supervisor may locate at the CP or the TSC, as conditions warrant.

5.1.1 REPORT initially to the TSC.

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NC.EP-EP.ZZ-0312(Q) 5.1.2 REPORT to the RAC and obtain a briefing- This may be done over the phone.

5.1.3 OBTAIN a briefing from the Chemistry Shift Techni cian located at the CP.

5.1.4 OBTAIN a current status of the Chemistry related systems for Salem or Hope Creek, as applicable, listed in Attachment 1, Salem/Hope Creek Chemistry Systems.

5.1.5 NOTIFY the Control Room (CR) that all Chemistry Sample requests should be directed through you.

5.1.6 OBTAIN Chemistry log from Chemistry Technician and ensure log is being kept.

5.1.7 DOCUMENT the status of Chemistry related systems in the Chemistry log, if plant conditions change.

5.1.8 EVALUATE the chemistry related systems impacted during the emergency, and brief the RAC as conditions warrant.

5.1.9 REFER to Attachment 2, Chemistry Guidelines - Power Operation, for actions to consider, if the plant is operating.

5.1.10 REFER to Attachment 3, Chemistry Guidelines - Power Reduction, for actions to consider, if there has been a power reduction >15%.

5.1.11 For Salem: REFER to Attachment 4, Chemistry Guidelines - Reactor Trip, for actions to consider, if there has been a Reactor Trip.

5.1.12 For Hope Creek: REFER to HC.CH-GP.ZZ-0006(Q),

Chemistry Scram Response, for actions if there has been a Reactor Scram.

5.1 13 INITIATE an emergency sample log, as necessary.

5.1 14 For Salem: IF a primary to secondary leak is suspected or is in progress. THEN REFER to Attachment 7. Chemistry Guidelines - Primary to Secondary Leak, for actions that should be considered for implementation.

5.1.15 For Hope Creek: REFER to Attachment 6 IF:

Status of outside systems is required during power operation.

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"* Actions to Outside Systems are required due to power reduction.

"* Actions to Outside Systems are required due to Reactor SCRAM.

"* Chemistry Technicians are to be sent outside the Protected Area.

5.1.16 COORDINATE and direct emergency chemistry actions, sampling, and analysis functions.

CAUTION Elevator use should be limited to transporting equipment unless Site Protection indicates that the elevator is needed to move an injured person, 5.1.17 For Hope Creek: IF PASS sampling is likely to be performed at Hope Creek THEN VERIFY that the Service Radwaste Elevator is operational, (The Service Radwaste Elevator Number is 31-04 and is energized from MCC 00B474-034)._

5.1.18 COORDINATE the activation of high activity sampling systems.

(Guidance and information are provided in Attachment 5.

Chemistry Guidelines - PASS/High Activity Samples).

5.1.19 COORDINATE applicable surveillances with the RAC and the Shift Chemistry Technician.

NOTE The Chemistry Supervisor after OSC Coordinator notification, may dispatch an individual, in lieu of a team. The individual should be in contact with the Control Point or the OSC via some type of audio communications, (page. radio.

or telephone), and should check in every 15 minutes.

Using an individual in lieu of a team should be the exception and not the norm.

5.1.20 USE a team in the field instead of an individual IF:

"* Exposure is expected to exceed 1000 mRem.

"* The task would require entry into "Harsh Environment Area", (i.e.: a steam atmosphere, a heat stress area, etc.).

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NC.EP-EP.ZZ-0312(Q) 0 Acts of sabotage or suspected sabotage.

5.1.21 ENSURE that the Radiation Protection Supervisor - Exposure Control or the OSC Coordinator has been notified prior to dispatching Chemistry Teams. This should be done remotely (telephone, page, radio. etc.).

5.1.22 DISPATCH Chemistry Teams as required for appropriate actions (i.e., sampling, chem feed controls, etc.).

5.1.23 EVALUATE sample analysis data, as results become available.

5.1.24 MAINTAIN communications with the Chemistry Technicians at the CP. and brief as conditions warrant.

NOTE The Salem Containment Sump pH must be adjusted to a value > 7.0 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of initiation of recirculation. This is required to preclude chloride induced stress corrosion cracking of stainless steel.

EP96-005 5.1.25 IF the SALEM Containment Spray did not activate, THEN SAMPLE the SALEM Containment Sump for pH and chlorides within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initiation of recirculation mode of core cooling, 5.1.26 IF the sample results of the Salem Containment Sump indicate a pH of < 7.0. THEN REQUEST the TSC to establish a plan to increase pH to a value > 7.0 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of recirculation actuation, 5.1.27 NOTIFY the RAC and Core thermal Hydraulics Engineer

- TSC of PASS/high activity sample analysis results.

5.1.28 CONSIDER the status of liquid effluent releases using appropriate Chemistry procedure(s). to quantify sample results.

5.1.29 ASSIST in the evaluation and resolution of radioactive waste problems and activities as conditions warrant, 5.1.30 BRIEF the RAC as data and information warrant.

5.1.31 REQUEST that the RAC augment chemistry staff as necessary.

5.1.32 BRIEF the RAC of potential unmonitored release paths as situations warrant.

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NC.EP-EP.ZZ-0312(Q) 5.1.33 IF HOPE CREEK'S Standby Liquid Control has been injected, THEN consider refilling the Hope Creek SLC tank using Procedure HC.CH-AD.BH-0001 (Q).

NOTE - HOPE CREEK ONLY In accordance with NUREG 0737, PASS shall be analyzed for chlorides within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months during post accident conditions. The following steps outline how this should be done to meet this criteria as the need arises.

5.1.34 FOR HOPE CREEK ONLY PERFORM the following steps to ship a PASS to BWX Technologists for analysis:

A. NOTIFY the Radiation Protection Supervisor Radioactive Material Control (RPS-RMC) that the NUPAC PAS - 1 Shipping Cask is needed to transport a large volume PASS/High Activity sample offsite to Babcock and Wilcox.

B. PHONE Robert Smith at 205-992-6820 or the PIMS Technician at 803-776-4714 to request the Shipping Cask.

NOTE The following information should be given to BWX Technologists:

"* The name of the person calling and the plant involved.

"* The name and phone number of the responsible person at the utility to whom follow-up communication should be addressed.

" The number and type of samples to be shipped (liquid and/or gaseous).

" Measured radiation levels from the shipping container on contact and at three feet. If not known at time of initial phone call, call back as soon as the values are known.

" The estimated shipping time and time of arrival at the Laboratory. If not known at time of initial phone call, call back as soon as the ETA is known.

C. NOTIFY BWX Technologists that a PASS/High Activity sample is going to be shipped to them for chloride analysis at 434-522-5833.

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D. TRANSPORT and load the PASS/High Activity sample as directed by the RPS-RMC.

NOTE Assembly shall be implemented after the declaration of an Alert Emergency declaration. Accountability shall be implemented after the declaration of a Site Area Emergency, and/or implemented at any time after Assembly, at the discretion of the Emergency Coordinator.

5.1.35 COORDINATE Accountability with the Shift Radiation Protection Technician (SRPT) or the Onshift Radiation Protection Technician (ORPT), utilizing Attachment 8, Assembly/Accountability Instruction - Control Point.

5.1.36 COORDINATE with the RAC, SRPT/ORPT, and Chemistry Technician - CP, relocation of the Control Point. if required.

Utilize Attachment 9, Chemistry - Control Point Evacuation Checklist.

5.1.37 Salem Chemistry COORDINATE with Hope Creek Chemistry to act as Salem's Count Room, if the Salem Count Room cannot be used 5.1.38 Hope Creek Chemistry COORDINATE with Salem Chemistry to act as Hope Creek's Count Room, if the Hope Creek Count Room cannot be used.

6.0 RECORDS Return completed procedure and any pertinent data to the Emergency Preparedness Manager.

7.0 REFERENCES

7.1 References PSEG Nuclear Emergency Plan 7.2 Cross References 7.2.1 NC.EP-EP.ZZ-031 1(Q), Control Point - Chemistry Response 7.2.2 NC.EP-WB.ZZ-0001(Z), Emergency Preparedness Phone Directory 7.2.3 HC.CH-AD.BH-0001 (Q). Chemistry Addition To The Standby Liquid Control System 7.2.4 HC CH-TI.ZZ-0003(Q), Environmental Monitoring and Compliance Sampling Nuclear Common Page 7 of 26 Rev. 04

NC.EP-EP.ZZ-0312(Q) 7.2.5 HC.CH-SA.HA-0001(R), Sampling The Offgas System From 10-C 335 Panel 7.2.6 HC.CH-EO.SH-0007(Q), Transporting Post Accident Sample System Samples 7.2.7 HC.CH-GP.ZZ-0006(Q), Chemistry SCRAM Response 7.2.8 SC.CH-AB.CBV-1 076(Q), Containment Atmosphere Sampling Under Accident Conditions.

7.2.9 SC.CH-AB. RC-1075(Q), Sampling Reactor Coolant And RHR Heat Exchanger Outlet Under Accident Conditions.

7.2.10 SC.CH-AB.RC-1085(Q), Post Accident Boron Sample Analysis Using Selective Ion Electrode 7.2.11 SC.CH-AB.RC-1080(Q), Reactor Coolant Sample Transfer And Dilution Under Accident Conditions 7.2.12 SC.CH-AB.RC-1090, Post Accident Reactor Coolant Sample Analysis Hood Setup.

7.3 Commitments Emergency Preparedness Commitment EP96-005 Nuclear Common Page 8 of 26 Rev. 04

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ATTACHMENT 1 Page 1 of 1 SALEM AND HOPE CREEK CHEMISTRY SYSTEMS 1.0 Salem Systems

"* (CP) Condensate Polishing System

"* (DM) Demineralized Water Make Up

"* (CF) Chemical Feed Systems

"* (SS) Sampling Systems

"* (CL) Chlorination Systems

"* (LW) Non-Radioactive Liquid Waste Disposal System 2.0 Hope Creek Systems

"* (AK) Condensate Demineralizers

"* (AN) Demineralized Water Make Up, Storage and Transfer

"* (AQ/BQ) Chem. Control - Zinc - Condensate and Feedwater

"* (AX) Hydrogen and Oxygen Injection Systems

"* (BG) Reactor Water Clean Up System Filtration and Demineralization (RWCU)

" (DD) Circ Water Hypochlorination

(DE) Circ Water Caustic Addition

"* (DF) Cooling Tower Blowdown Dechlorination

"* (ED) RACS Demineralization System (Reactor Auxiliary Cooling System)

"* (EG) SACS Demineralization System (Safety Auxiliary Cooling System)

"* (EQ) Service Water Hypochlorination

"* (GB) Chilled Water System Filtration and Demineralization

"* (LB) Storm Drainage

"* (LD) Chemical Waste

"* (LE) Oily Waste

"* (RC) Process Sampling

"* (SH) PASS Sampling

"* (HA) Offgas System Nuclear Common Page 9 of 26 Rev. 04

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ATTACHMENT 2 Page 1 of 1 CHEMISTRY GUIDELINES - POWER OPERATION 1.0 Salem 1.1 IF a RCS sample is requested, and general area dose rates at the primary sample panel permit, THEN SAMPLE RCS using appropriate Chemistry procedure.

1.2 IF dose rates at the sample panel do not permit, THEN REFER to Attachment 5, Chemistry Guidelines - PASS/High Activity Samples.

1-3 IF the data obtained is out of specification or suspect, THEN OBTAIN and analyze the applicable sample(s).

1.4 DETERMINE if the status of the Demin Water Storage Tanks are at an acceptable level, 1.5 IF tank levels are not acceptable, THEN MAKE - UP to the tanks using appropriate Chemistry procedures.

2.0 Hope Creek 2.1 REVIEW current reactor water chemistry data.

2.2 IF a Reactor Water sample is requested, and general area dose rates at the sample panel permit, THEN SAMPLE Reactor Water at the sample panel.

2.3 IF dose rates at the sample panel do not permit, THEN REFER to Attachment 5, Chemistry Guidelines - PASS/High Activity Samples.

2.4 SAMPLE the Off Gas system, as required, using appropriate procedures.

2.5 OBTAIN current chemistry data on the Condensate Polisher system and review instrument readings, 2.6 CHECK the status of the Demin Water Storage Tanks on panel 0OCl 18 and make up to demin water tanks as required.

2.7 CHECK status of the outside systems (Service Water, Circ Water. and Cooling Tower Blowdown) lAW Attachment 6.

Chemistry Guidelines - Outside Systems.

2.8 CHECK status of the Hydrogen Water Chemistry Injection System._

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ATTACHMENT 3 Page 1 of 2 CHEMISTRY GUIDELINES - POWER REDUCTION 1.0 Salem 1.1 IMPLEMENT the actions listed in Attachment 6, Chemistry Guidelines - Outside Systems, Section 1.0.

1.2 IF dose rates permit, THEN OBTAIN an RCS sample 2-6 hours after a power reduction of >15%/hr. at normal sampling locations using appropriate Chemistry procedure.

1.3 IF dose rates do not permit. THEN REFER to Attachment 5, Chemistry Guidelines - PASS/High Activity Samples.

1.4 IF the data obtained is out of specification or suspect, THEN OBTAIN and analyze the applicable sample(s).

1.5 CHECK the status of the Demin Water Storage Tanks and determine if they are at an acceptable level.

1.6 IF tank levels are not acceptable, THEN MAKE - UP to the tanks using appropriate Chemistry procedures.

1.7 UTILIZE other Chemistry Department procedures for power reduction as appropriate, 2.0 Hope Creek 2.1 MONITOR the effect of reduced power on outside systems lAW HC.CH-TI.77-0003(Q).

2.2 CHECK the status of the RWCU System, and if appropriate, reset vessel flow at the RWCU Panel 10076.

2.3 REVIEW all instrument readings from the RWCU sample panels.

2.4 IF dose rates permit at the sample panel, THEN OBTAIN a Reactor Water sample 2-6 hours after the power reduction at the normal sample point.

2.5 IF dose rates do not permit. THEN REFER to Attachment 5.

Chemistry Guidelines - PASS/High Activity Samples.

2.6 SAMPLE the Off Gas System as required lAW procedure HC.CH-SA.HA-0001(R).

2.7 OBTAIN current chemistry data on the Condensate System.

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ATTACHMENT 3 Page 2 of 2 2.8 REVIEW instrument readings at the Condensate Polishers and ensure that flows are above 3000 gpm.

2.9 CHECK the status of the Demin Water Storage Tanks at Panel 0OCl 18 and make up to the demin tanks as required.

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ATTACHMENT 4 Page 1 of 1 CHEMISTRY GUIDELINES - SALEM REACTOR TRIP 1.0 Salem Trip 1.1 IF dose rates permit, THEN OBTAIN an RCS sample 2-6 hours after a power reduction of > 15%/hr. at normal sampling locations using appropriate Chemistry procedure.

1.2 IF dose rates do not permit- THEN REFER to Attachment 5, Chemistry Guidelines - PASS/High Activity Samples.

1.3 CHECK the status of the Condensate Polishers and isolate vessels as necessary to maintain adequate flow for the in service vessels.

1.4 CHECK the status of the Demin Water Storage Tanks and determine if they are at an acceptable level.

15 IF the Demin Water Storage Tank's levels are not acceptable.

THEN MAKE - UP to the tanks using appropriate Chemistry procedures.

1.6 UTILIZE other Chemistry Department procedures for shutdown as appropriate.

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ATTACHMENT 5 Page 1 of 3 CHEMISTRY GUIDELINES - PASS/HIGH ACTIVITY SAMPLES NOTE The plant's current operational condition will determine the appropriate sample location.

Utilize the sample location lists below to help in making this determination.

1.0 SALEM SAMPLE TYPES 1.1 IF samples are requested for fuel damage assessment, THEN OBTAIN a sample using the preference list for sample type listed belowý

"* RCS Loop - Liquid

"* RHR/Containment Sump - Liquid 1.2 IF samples are requested for source term determination, THEN OBTAIN a sample using the preference list for sample type listed below

"* RCS Loop - Liquid

"* RHR/Containment Sump - Liquid 1.3 IF the Containment is to be vented or purged, THEN OBTAIN a sample from the Containment Atmosphere - Gas.

2.0 COORDINATION AND STORAGE OF HIGH ACTIVITY SAMPLE AT SALEM STATION NOTE Figure - 1, Salem High Activity Sample Storage Location, illustrates the high activity sample storage locations outlined in step 2.1.

2.1 REFER to Figure - 1 to ensure the transportation and storage of high activity samples in one of the acceptable storage locations listed below occurs Nuclear Common Page 14 of 26 Rev. 04

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ATTACHMENT 5 Page 2 of 3

"* Blowdown panel room, elevation 100'. A lead brick cave will be available for optimum shielding. (a)

"* Fuel handling annex (small truck bay) elevation 100'. (b)

"* Hot drum storage cask labyrinth, adjacent to Fuel Handling Building yard. elevation 100'. (c)

"* Hot drum storage area, elevation 100', Solid Radwaste. (d)

"* Waste evaporator bottoms hold tank area, elevation 100'. (e) 2.2 ENSURE that radiation protection provides escorts, survey:

posting, and shielding as appropriate.

2.3 ENSURE that all samples are labeled, and entered in the Chemistry Emergency Log including storage location.

2.4 KEEP the Chemistry Supervisor informed of transportation and storage activities.

NOTE The plant's current operational condition will determine the appropriate high activity sampling location. Utilize the sample location lists below to help in making this determination.

3.0 HOPE CREEK SAMPLE TYPES 3.1 IF samples are requested for fuel damage assessment, THEN OBTAIN a sample using the preference list for sample location listed below

"* Jet Pump - Liquid

"* RHR - Liquid (RHR Loop A - Pumps A and C)

(RHR Loop B - Pumps B and D)

"* Torus- Gas

"* Drywell Atmosphere - Gas 3.2 IF samples are requested for source term determination.

THEN OBTAIN a sample using the preference list for sample location listed below:

"* Drywell Atmosphere - Gas

"* Torus - Gas Nuclear Common Page 15of 26 Rev. 04

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ATTACHMENT 5 Page 3 of 3

"* Jet Pump - Liquid

"* RHR - Liquid (RHR Loop A - Pumps A and C (RHR Loop B - Pumps B and D) 3.3 IF the Drywell is to be vented, THEN OBTAIN a sample using the preference list for sample location listed below:

"* Torus - Gas

"* Drywell Atmosphere - Gas

"* Jet Pump - Liquid

"* RHR - Liquid (RHR Loop A - Pumps A and C)

(RHR Loop B - Pumps B and D) 4.0 APPLICABLE HOPE CREEK PASS PROCEDURES

"* (HC.CH-EO.SH-0001Q) Post Accident Sample Panel Operation

"* (HC.CH-EO.SH-0004Q) Post Accident Sample Analysis

"* (HC.CH-EO.SH-0005Q) Post Accident Sample Dilution

"* (HC.CH-EO.SH-0007Q) Transporting Post Accident Sampling System Samples 5.0 COORDINATION AND STORAGE OF PASS AT HOPE CREEK STATION 5.1 Transport and store post accident samples lAW procedure HC.CH-EO.SH-0007(Q), as thought necessary by the Chemistry Supervisor.

5.2 REFER to Figure - 2, Hope Creek PASS Storage Location, for acceptable locations.

5.3 ENSURE that radiation protection provides escorts, survey, posting, and shielding as appropriate.

5.4 ENSURE that all samples are labeled, and entered in the sample log, including storage location.

5.5 KEEP the Chemistry Supervisor informed of transportation and storage activities.

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NC.EP-EP.ZZ-0312(Q)

ATTACHMENT 6 Page 1 of 1 CHEMISTRY GUIDELINES - OUTSIDE SYSTEMS 1.0 Dosimetry ENSURE that all personnel dispatched to the outside systems wear there dosimetry at all times.

2.0 Communications ENSURE that all personnel dispatched to the outside systems have a portable radio and maintain communications with the CR, OSC, TSC, or CP as appropriate.

3.0 HOPE CREEK ACTIONS DURING POWER OPERATION 3.1 CHECK the status of (EQ) Service Water Hypochlorination.

3.2 CHECK the status of (DD) Circ Water Hypochlorination.

3.3 CHECK the status of (DE) Circ Water Caustic Addition.

3.4 CHECK the status of (DF) Cooling Tower Blowdown Dechlorination.

4.0 HOPE CREEK ACTIONS DURING POWER REDUCTION 4.1 DECREASE (EQ) Service Water Hypochlorination.

4.2 DECREASE (DD) Circ Water Hypochlorination.

4.3 DECREASE (DE) Circ Water Caustic Addition.

4.4 INCREASE (DF) Cooling Tower Blowdown Dechlorination.

4.5 ANALYZE the effluent at the Cooling Tower Blowdown.

5.0 HOPE CREEK ACTIONS AFTER A REACTOR SCRAM 5.1 ISOLATE (EQ) Service Water Hypochlorination.

5.2 ISOLATE (DD) Circ Water Hypochlorination.

5.3 ISOLATE or Secure (DE) Circ Water Caustic Addition.

5.4 INCREASE (DF) Cooling Tower Blowdown Dechlorination.

5.5 ANALYZE the effluent at the Cooling Tower Blowdown.

Nuclear Common Page 17 of 26 Rev. 04

NC.E P-EP.ZZ-0312(Q)

ATTACHMENT 7 Page 1 of 1 CHEMISTRY GUIDELINES - PRIMARY TO SECONDARY LEAK (SALEM ONLY) 1.0 POWER OPERATION and POWER REDUCTION FOR SALEM 1.1 IF appropriate, THEN SAMPLE and analyze the following for isotopic content:

"* Steam Generator Liquid

"* RCS Liquid

"* Air Ejector Effluent 1.2 IF appropriate, THEN NOTIFY Radiation Protection that radiological surveys in the secondary plant may be necessary, with emphasis on filters and demineralizers.

2-0 SALEM REACTOR TRIP 2.1 REQUEST that the control room open the blowdown isolation valves.

2.2 IF appropriate, THEN SAMPLE and analyze the following for isotopic content

Steam Generator Liquid 0 RCS Liquid 2.3 IF appropriate, THEN NOTIFY Radiation Protection that radiological surveys in the secondary plant may be necessary, with emphasis on filters and demineralizers Nuclear Common Page 18 of 26 Rev. 04

NC.EP-EP.ZZ-0312(Q)

ATTACHMENT 8 Page 1 of 2 ASSEMBLY/ACCOUNTABILITY INSTRUCTIONS - CONTROL POINT 1.0 IMPLEMENTATION OF ASSEMBLY AT THE CONTROL POINT 1,1 The Chemistry Supervisor Or Designee SHALL Ensure the Following Happens:

NOTE Assembly/Accountability actions at the Control Point are to be coordinated with the SRPT/ORPT and the RAC.

1.1.1 ASSEMBLE all Chemistry Personnel at the Control Point.

1.1.2 DIRECT personnel exiting the RCA to proceed to their accountability station or direct them to assemble in change areas dependent on radiological conditions.

1.1.3 DIRECT personnel remaining at the Control Point to sign in on the Accountability Station Attendance Sheet (Form - 1)._

1.1.4 IF accountability implementation is called for. THEN PROCEED to step 2.0 of this attachment.

2.0 IMPLEMENTATION OF ACCOUNTABILITY 2 1 The Chemistry Supervisor Or Desiqnee SHALL Ensure the Following Happens:

T -0 MIN 2.1.1 IF the Radiation Alert Alarm and page announcement sounds, "ALL ACCOUNTABILITY STATIONS IMPLEMENT ACCOUNTABILITY".

THEN ENSURE all personnel at the Control Point, including ail personnel in the Rad Pro. Break Room and Change Areas. have passed their photobadges through the special accountability cardreader located at the Control Point.

Nuclear Common Page 19 of 26 Rev. 04

NC.EP-EP.ZZ-0312(Q)

ATTACHMENT 8 Page 2 of 2 T - + 20 MIN 2.1.2 WHEN the page announcement sounds, "ALL ACCOUNTABILITY STATIONS COMPLETE YOUR ACCOUNTABILITY", THEN ENSURE that any personnel arriving at the Control Point since the initial call for accountability also have passed their photobadges through the Control Point accountability cardreader.

2.1.3 DIRECT all stragglers (personnel arriving at the Control Point after 30 minutes have lapsed) to pass their photobadge through the accountability cardreader and report the badge number(s) of stragglers to the Security Center (Ext. 2223).

2.1.4 MAINTAIN continuous accountability until Hope Creek~s/Salem's emergency is terminated.

2.1.5 IF the Automated Accountability System malfunctions, THEN REFER to step 3.0.

3.0 AUTOMATED ACCOUNTABILITY SYSTEM MALFUNCTION 3.1 The Chemistry Supervisor Or Designee SHALL Ensure the Following Happens:

3.1.1 IF the automated accountability system malfunction, THEN PROVIDE a copy of the Accountability Station Attendance Sheet, Form - 1, to the Security Force Member dispatched to the Control Point Nuclear Common Page 20 of 26 Rev. 04

NC.EP-EP.ZZ-0312(Q)

ATTACHMENT 9 Page 1 of 2 CONTROL POINT EVACUATION CHECKLIST 1.0 EVACUATION OF THE CONTROL POINT 1.1 The Chemistry Supervisor Or Designee Should Ensure The Following Happens:

1.1.1 ENSURE Chemistry personnel are assisting Radiation Protection personnel in evacuation of the Control Point.

1.1.2 ENSURE that the TSC and Control Room are kept aware of the new location.

1.1.3 ENSURE the following equipment is included in the Control Point evacuation.

"* Movable Counting Room Equipment.

"* Dosimeters, additional TLDs from the Control Point.

"* Emergency Logbooks.

"* Portable Survey Equipment.

"* Survey materials (air sample filters etc.).

"* SCBA and spare tanks

"* Respirators and canisters.

"* Protective Clothing.

"* Posting Materials and Barricades.

"* Emergency Plan Implementing Procedures,

"* Event Classification Guide.

"* Station Procedures.

1.1.4 NOTIFY the RAC of the new telephone numbers.

1.1.5 NOTIFY the RAC when the new Control Pont has become operational 1.1.6 RE-ESTABLISH the operability of the evacuated equipment as soon as possible.

1.1.7 MONITOR continuously Chemistry personnel exposure. Rotate personnel as appropriate to ensure dose limits are not exceeded.

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ATTACHMENT 9 Page 2 of 2 1.1.8 ENSURE all pertinent information is entered in log books.

1.1.9 USE the equipment checklist and note deficiencies.

1.1.10 IF additional materials or services are required due to relocation, THEN CONTACT the RAC.

NOTE A list of categories, corresponding Vendors and telephone numbers is provided in the EP Phone Directory, NC.EP-WB.ZZ 0001(Z), located at the Control Point, TSC, Control Room, and EOF. For PSEG stockroom items refer to SAP.

1.1.11 WHEN requesting inventory status, THEN GIVE due regard to habitability of particular areas.

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NC.EP-EP.ZZ-0312(Q)

FORM - 1 Page 1 of 1 ACCOUNTABILITY STATION ATTENDANCE SHEET Facility: CR, CP, TSC, OSC Date:

(circle)

LAST NAME/FIRST NAME BADGE NUTMIBER Attach additional pages with appropriate information as needed.

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NC.EP-EP.ZZ-0312(Q)

FIGURE - 1 Page 1 of 2 SALEM HIGH ACTIVITY SAMPLE STORAGE LOCATION ELEVATION 100 FOOT Nuclear Common Page 24 of 26 Rev- 04

NC.EP-EP.ZZ-0312(Q)

FIGURE - 1 Page 2 of 2 Blowdown panel room, elevation 100'. A lead brick cave will be available for optimum shielding. (a)

Fuel handling annex (small truck bay) elevation 100'. (b)

Hot drum storage cask labyrinth, adjacent to Fuel Handling Building yard, elevation 100'. (c)

Hot drum storage area, elevation 100',

Solid Radwaste.(d)

Waste evaporator bottoms hold tank area, elevation 100'. (e)

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NC.EP-EP.ZZ-0312(Q)

FIGURE - 2 PAGE 1 OF 1 HOPE CREEK PASS STORAGE LOCATION AREA LAB CAUBRATION CHUE1 AND REPAIR STORAGE SHOP SERVICE/RADVASTE AREA 124' ELE'VATION Nuclear Common Page 26 of 26 Rev. 04

PSEG Internal Use Only PSE&G NUCLEAR LLC Page 1 of 1 NC.EP-EP.ZZ-0311 (Q) Rev. 03 CONTROL POINT - CHEMISTRY RESPONSE USE CATEGORY: -l REVISION

SUMMARY

1. Added Salem references for new sampling procedures to Section 7.0, References.

2. Revised the title to Figure - 1 to Salem High Activity Sample Storage Location and revised the title in all references made to Attachment 5 throughout this procedure.

3. Revised the title to Attachment 5 to Chemistry Guidelines - PASS/High Activity Sample and revised the title in all references made to Attachment 5 throughout this procedure.

4. Revised Step 5.1.11 to say For Hope Creek.

5. Attachment 5, 2.0, Deleted PASS and added high activity samples.

6. Attachment 5. revised Step 2.1 from PASS to high activity samples.

7. Revised the Chemistry Supervisor - CPITSC to Chemistry Supervisor throughout the procedure.

8. Attachment 5. note after Step 2.4, revised PASS to high activity samples.

9 Revised the position that approves emergency plan implementing procedures from Vice President - Operations to Director Operations

10. This revision satisfies the requirement for a biennial review.

11. Removed RCS/RHR gas sample from Attachment 5. Step 1.1 and 1.2 as a type of sample available at Salem (it is no longer required).

IMPLEMENTATION REQUIREMENTS:

Procedure Implementation Date& -

APPROVED Emergency Preparedness Manager Date APPROVED // //t/Y Dhte

3

NC.EP-EP.ZZ-0311 (Q)

CONTROL POINT - CHEMISTRY RESPONSE TABLE OF CONTENTS SECTION TITLE PAGE 1.0 P UR P O S E .......................................................... ....................................... . . . 2 2 .0 P R E R E Q UIS IT E S ............................................................................................ 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure . 2 3.0 P R ECA UT IO NS A ND LIM ITA T IO NS ................................................................ 2 3.1 Precaution and Limitations To Be Followed Prior To Implementing This P ro c e d u re ............................................................................................. 2 4 .0 E Q UIP ME NT R E Q UIR E D ................................................................................ 2 5 .0 P R O C E DUR E ................................................................................................... 2 5.1 The Chemistry Shift Technician Should ...................................... .... 2 5.2 T he C hem istry Technicians S hould ....................................................... 4 6 .0 R E C O R D S .............................. . ........................................................ ....... .... 4 7 .0 R E F E R E NC E S .............. 4.......................

4 7 .1 R e fe re n c e s ............................. .................. 4.......................

4 7 .2 C ro s s R e fe re n c e s ... ............................ ......... ..................... .......... 4 ATTACHMENTS ATTACHMENT 1 - Salem and Hope Creek Chemistry Systems ................................... 6 ATTACHMENT 2 - Chemistry Guidelines - Power Operation ................. ................... 7 ATTACHMENT 3 - Chemistry Guidelines - Power Reduction 8...............................

B ATTACHMENT 4 - Chemistry Guidelines - Salem Reactor Trip .................................. 10 ATTACHMENT 5 - Chemistry Guidelines - PASS/High Activity Sample ..................... 11 ATTACHMENT 6 - Chemistry Guidelines - Outside Systems ................................... 14 ATTACHMENT 7 - Chemistry Guidelines - Primary to Secondary Leak (S A LE M O NLY ) ....... ... ......................................... .1. 5 FIGURES FIGURE 1 - Salem High Activity Sample Storage Location .................................. 16 FIGURE 2 - Hope Creek PASS Storage Location ............................................. 18 NUCLEAR COMMON Page 1 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q) 1.0 PURPOSE This procedure provides instructions and guidance for Chemistry Technicians assigned to the Control point during an emergency at Hope Creek or Salem Generating Station.

2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure Individuals who will implement this procedure:

"* Chemistry Shift Technician - (Chem Shift Tech)

"* Chemistry Technician(s) - (Chem Tech) 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations To Be Followed Prior To Implementing This Procedure:

3.1.1 It is recommended that initials be used in the place keeping sign-offs, instead of checkmarks, if more than one person may implement this procedure.

3.1.2 The user may deviate from following procedure steps in written order if it is thought by the user that emergency conditions warrant it.

31.3 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.

4.0 EQUIPMENT REQUIRED As provided in the Emergency Response Facility.

5.0 PROCEDURE 5.1 The Chemistry Shift Technician Should:

5.1.1 OBTAIN a current status of the emergency from the Control Room.

5.1.2 PROVIDE to the Control Room a current status of the chemistry related system parameters, as requested.

5.1.3 MAINTAIN communications with the Control Room until the Chemistry Supervisor arrives.

5,1.4 REFER to Attachment 1, Salem and Hope Creek Chemistry Systems.

for a list of chemistry systems and abbreviations.

NUCLEAR COMMON Page 2 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q) 5.1.5 NOTE which chemistry related systems are being operated in manual and in automatic, as necessary.

NOTE Equipment status, events, plant conditions, dictate the appropriate response actions including the timely notification of the Chemistry Duty Supervisor, if one is not present.

5.1.6 IF plant conditions change, THEN the Chemistry Shift Technician should document the status of Chemistry related systems, in the Control Point log book.

5.1.7 REPORT any abnormalities and/or system changes to the Operations Superintendant (OS). Emergency Duty Officer (EDO). Radiological Assessment Coordinator (RAC), or Chemistry Supervisor, as appropriate.

5.1.7 IF the plant is operating, THEN refer to Attachment 2, Chemistry Guidelines - Power Operation, for actions to consider.

5.1.9 IF there has been a power reduction > 15%. and/or turbine run back, THEN refer to Attachment 3 Chemistry Guidelines - Power Reduction, for actions to consider.

5.1.10 FOR SALEM: IF there has been a Reactor TRIP, THEN refer to Attachment 4. Chemistry Guidelines - Salem Reactor Trip. for actions to consider.

5.1.11 FOR HOPE CREEK: REFER to Attachment 6 IF:

A. Status of Outside Systems is required during power operation B Actions to Outside Systems are required due to power reduction C. Actions to Outside Systems are required due to Reactor SCRAM.

D. Chemistry Technicians are to be sent outside the Protective Area NUCLEAR COMMON Page 3 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q) 5.1.12 FOR HOPE CREEK ONLY: OBTAIN from the Radiation Protection Supervisor - Exposure Control (OSC) information concerning exposure hazards present at the Reactor Water Clean Up sample station.

5.1.13 OBTAIN samples using the appropriate systems and procedures for sampling high activity samples, as directed. (Refer Attachment 5, Chemistry Guidelines - PASS/High Activity Samples, for actions to consider when sampling PASS/high activity samples).

5,114 FOR SALEM ONLY:.IF it is thought to be a primary to secondary leak.

THEN refer to Attachment 7, Chemistry Guidelines - Primary to Secondary Leak.

5.1.15 MAINTAIN a log of all data. information, and actions, until relieved by the Chemistry Supervisor.

5.1 16 WHEN the Chemistry Supervisor arrives, THEN brief him/her and turn over the Chemistry Log.

5.2 The Chemistry Technicians Should:

5.2.1 OPERATE Chemistry Control Systems, as directed by the Chemistry Supervisor or Shift Chemistry Technician, using the applicable chemistry procedures 5.2.2 OBTAIN and analyze accident samples as directed by the Chemistry Supervisor or Shift Chemistry Technician, using the applicable chemistry procedures 5.2.3 TRANSMIT status and analysis results to Chemistry Supervisor or Shift Chemistry Technician 5.24 STORE PASS/high activity isotopic samples in accordance with Figure

- 1 (SALEM) or Figure - 2 (Hope Crek).

6.0 RECORDS Return completed procedure and any information or data thought to be pertinent to the Emergency Prepaedness Manager 70 REFERENCES 7.1 References 7.1.1 PSEG Nuclear Emergency Plan 7.2 Cross References NUCLEAR COMMON Page 4 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q) 7.2.1 NC.EP-EP.ZZ-0312(Q), Control Point Chemistry Response 7.2.2 HC.CH-TI.ZZ-003(Q), Environmental Monitoring and Compliance Sampling 7.2.3 HC.CH-SA.HA-0001(R), Sampling The Offgas System From 10-C-335 Panel 7.2.4 HC.CH-EO.SH-0001(Q), Post Accident Sample Panel Operation 7.2.5 HC.CH-EO.SH-0004(Q), Post Accident Sample Analysis 7.2.6 HC.CH-EO.SH-0005(Q), Post Accident Sample Dilution 7.2.7 HC.CH-EO.SH-0007(Q), Transporting Post Accident Sample System Samples 7.2.8 SC.CH-AB.CBV-1 076(Q), Containment Atmosphere Sampling Under Accident Conditions.

7.2.9 SC.CH-AB.RC-1075(Q), Sampling Reactor Colant and RHR Heat Exchanger Outlet Under Accident Conditions.

7.2.10 SC.CH-AB.RC-1085(Q), Post Accident Boron Sample Analysis Using Selective Ion Electrode.

7.2.11 SC.CH-AB.RC-1090(Q), Reactor Coolant Sample Transfer and Dilution Under Accident Conditions.

7.2.12 SC.CH-AB.RC-1080(Q), Reactor Coolant Sample Transfer and Dilution Under Accident Conditions.

NUCLEAR COMMON Page 5 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

ATTACHMENT 1 Page 1 of 1 SALEM AND HOPE CREEK CHEMISTRY SYSTEMS 1.0 Salem Systems

"* (CP) Condensate Polishing System

"* (DM) Demineralized Water Make Up

"* (CF) Chemical Feed Systems

"* (SS) Sampling Systems

"* (CL) Chlorination Systems

"* (LW) Non-Radioactive Liquid Waste Disposal System 2.0 Hope Creek Systems

"* (AK) Condensate Demineralizers

"* (AN) Demineralized Water Make Up, Storage and Transfer

"* (AQ/BQ) Chem. Control - Zinc - Condensate and Feedwater

"* (AX) Hydrogen and Oxygen Injection Systems

(BG) Reactor Water Clean Up System Filtration and Demineralization (RWCU)

(DD) Circ Water Hypochlorination

(DE) Circ Water Caustic Addition

(DF) Cooling Tower Blowdown Dechlorination

(ED) RACS Demineralization System (Reactor Auxiliary Cooling System)

(EG) SACS Demineralization System (Safety Auxiliary Cooling System)

(EQ) Service Water Hypochlorination

(GB) Chilled Water System Filtration and Demineralization

(LB) Storm Drainage

(LD) Chemical Waste

(LE) Oily Waste

((RC) Process Sampling

(SH) PASS Sampling

(HA) Offgas System NUCLEAR COMMON Page 6 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

ATTACHMENT 2 Page 1 of 1 CHEMISTRY GUIDELINES - POWER OPERATION 1.0 Salem 1.1 IF a RCS sample is requested, and general area dose rates at the primary sample panel permit, THEN SAMPLE RCS using appropriate Chemistry procedure.

1.2 IF dose rates at the sample panel do not permit, THEN REFER to Attachment 5, Chemistry Guidelines - PASS/

High Activity Sample.

1.3 IF the data obtained is out of specification or suspect, THEN OBTAIN and analyze the applicable sample(s).

1.4 DETERMINE if the status of the Demin Water Storage Tanks are at an acceptable level.

1.5 IF tank levels are not acceptable, THEN MAKE - UP to the tanks using appropriate Chemistry procedures.

2.0 Hope Creek 2.1 REVIEW current reactor water chemistry data.

2.2 IF a Reactor Water sample is requested, and general area dose rates at the sample panel permit.

THEN SAMPLE Reactor Water at the sample panel.

2.3 IF dose rates at the sample panel do not permit, THEN REFER to Attachment 5, Chemistry Guidelines - PASS/

High Activity Sample.

24 SAMPLE the Off Gas system, as required, using appropriate procedures.

2.5 OBTAIN current chemistry data on the Condensate Polisher system and review instrument readings.

2.6 CHECK the status of the Demin Water Storage Tanks on panel 0OCl 18 and make up to demin water tanks as required.

2 7 CHECK status of the outside systems (Service Water, Circ Water, and Cooling Tower Blowdown) lAW Attachment 6, Chemistry Guidelines - Outside Systems.

2.8 CHECK status of the Hydrogen Water Chemistry Injection System NUCLEAR COMMON Page 7 of 18 Rev. 03

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ATTACHMENT 3 Page 1 of 2 CHEMISTRY GUIDELINES - POWER REDUCTION 1.0 Salem 1.1 IMPLEMENT the actions listed in Attachment 6, Chemistry Guidelines - Outside Systems, Section 1.0.

1.2 ENSURE that all personnel dispatched to outside systems have a portable radio and maintain communications with the Control Point, Control Room, or the OSC, as applicable.

1.3 IF dose rates permit, THEN OBTAIN an RCS sample 2-6 hours after a power reduction of > 15%/hr. at normal sampling locations using appropriate Chemistry procedure.

1.4 IF dose rates do not permit, THEN REFER to Attachment 5, Chemistry Guidelines - PASS/

High Activity Samples, 1.5 IF the data obtained is out of specification or suspect, THEN OBTAIN and analyze the applicable sample(s).

1.6 CHECK the status of the Demin Water Storage Tanks and determine if they are at an acceptable level 1.7 IF tank levels are not acceptable, THEN MAKE - UP to the tanks using appropriate Chemistry procedures.

18 UTILIZE other Chemistry Department procedures for power reduction as appropriate.

2.0 Hope Creek 2.1 MONITOR the effect of reduced power on outside systems lAW HC.CH-TI.ZZ-0003(Q).

2.1 1 CONSIDER implementing the actions listed in Attachment 6.

Chemistry Guidelines - Outside Systems. Section 2.0.

2.2 CHECK the status of the RWCU System, and if appropriate.

reset vessel flow at the RWCU Panel 1O-C-076.

2 3 REVIEW all instrument readings from the RWCU sample panels.

24 IF dose rates permit at the sample panel.

THEN OBTAIN a Reactor Water sample 2-6 hours after the power reduction of > 1 5%/hr at the normal sample point.

NUCLEAR COMMON Page 8 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

ATTACHMENT 3 Page 2 of 2 2.5 IF dose rates do not permit, THEN REFER to Attachment 5,Chemistry Guidelines - PASS/

High Activity Samples.

2.6 SAMPLE the Off Gas System as required lAW procedure HC.CH SA.HA-0001 (R) 2.7 OBTAIN current chemistry data on the Condensate System.

2.8 REVIEW instrument readings at the Condensate Polishers and ensure that flows are above 3000 gpm.

2.9 CHECK the status of the Demin Water Storage Tanks at Panel 0OCl 18 and make up to the demin tanks as required.

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ATTACHMENT 4 Page 1 of 1 CHEMISTRY GUIDELINES - SALEM REACTOR TRIP 1.0 Salem Trip 1.1 IF dose rates permit, THEN OBTAIN an RCS sample 2-6 hours after a power reduction of > 15%/hr. at normal sampling locations using appropriate Chemistry procedure.

1.2 IF dose rates do not permit; THEN REFER to Attachment 5, Chemistry Guidelines - PASS/

High Activity Samples.

1.3 CHECK the status of the Condensate Polishers and isolate vessels as necessary to maintain adequate flow for the in service vessels.

1.4 CHECK the status of the Demin Water Storage Tanks and determine if they are at an acceptable level.

15 IF the Demin Water Storage Tank s levels are not acceptable.

THEN MAKE - UP to the tanks using appropriate Chemistry procedures.

1.6 UTILIZE other Chemistry Department procedures for shutdown.

as appropriate.

NUCLEAR COMMON Page 10 of 18 Rev. 03

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ATTACHMENT 5 Page 1 of 3 CHEMISTRY GUIDELINES - PASS/HIGH ACTIVITY SAMPLING NOTE The plant's current operational condition will determine the appropriate sample location.

Utilize the sample location lists below to help in making this determination.

1.0 SALEM SAMPLE TYPES 1.1 IF samples are requested for fuel damage assessment, THEN OBTAIN a sample using the preference list for sample type listed below:

"* RCS Loop - Liquid

"* RHR/Containment Sump - Liquid 1 .2 IF samples are requested for source term determination, THEN OBTAIN a sample using the preference list for sample type listed below:

"* RCS Loop - Liquid

"* RHR/Containment Sump - Liquid 1.3 IF the Containment is to be vented or purged, THEN OBTAIN a sample from the Containment Atmosphere - Gas.

20 COORDINATION AND STORAGE OF HIGH ACTIVITY SAMPLES AT SALEM STATION NOTE Figure - 1. Salem High Activity Storage Location, illustrates the high activity storage locations outlined in step 2 1.

2.1 REFER to Figure - 1 to ensure the transportation and storage of high activity samples in one of the acceptable storage locations listed below occurs.

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ATTACHMENT 5 Page 2 of 3

" Blowdown panel room, elevation 100'. A lead brick cave will be available for optimum shielding. (a)

"* Fuel handling annex (small truck bay) elevation 100'. (b)

"* Hot drum storage cask labyrinth, adjacent to Fuel Handling Building yard, elevation 100'. (c)

"* Hot drum storage area, elevation 100', Solid Radwaste. (d)

"* Waste evaporator bottoms hold tank area, elevation 100'. (e) 2.2 ENSURE that radiation protection provides escorts, survey, posting, and shielding as appropriate.

2.3 ENSURE that all samples are labeled, and entered in the Chemistry Emergency Log including storage location 2.4 KEEP the Chemistry Supervisor informed of transportation and storage activities.

NOTE The plant's current operational condition will determine the appropriate high activity sampling location. Utilize the sample location lists below to help in making this determination.

3.0 HOPE CREEK SAMPLE TYPES 3 1 IF samples are requested for fuel damage assessment.

THEN OBTAIN a sample using the preference list for sample location listed below

"* Jet Pump - Liquid

"* RHR-- Liquid (RHR Loop A - Pumps A and C)

(RHR Loop B - Pumps B and D)

"* Torus - Gas

"* Drywell Atmosphere - Gas 3.2 IF samples are requested for source term determination.

THEN OBTAIN a sample using the preference list for sample location listed below

Drywell Atmosphere - Gas NUCLEAR COMMON Page 12 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

ATTACHMENT 5 Page 3 of 3

"* Torus - Gas

"* Jet Pump - Liquid

"* RHR - Liquid (RHR Loop A - Pumps A and C (RHR Loop B - Pumps B and D) 3.3 IF the Drywell is to be vented, THEN OBTAIN a sample using the preference list for sample location listed below:

"* Torus- Gas

"* Drywell Atmosphere - Gas

"* Jet Pump - Liquid

"* RHR - Liquid (RHR Loop A - Pumps A and C)

(RHR Loop B - Pumps B and D) 4.0 APPLICABLE HOPE CREEK PASS PROCEDURES (HC. CH-EO.SH-0001Q) Post Accident Sample Panel Operation S(HCGCH-EO.SH-0004Q) Post Accident Sample Analysis S(HC.CH-EO SH-00050) Post Accident Sample Dilution S(HC.CH-EO.SH-0007Q) Transporting Post Accident Sampling System Samples 5.0 COORDINATION AND STORAGE OF PASS AT HOPE CREEK STATION 5.1 TRANSPORT and store post accident samples lAW procedure HC.CH-EO.SH-0007(Q). as thought necessary by the Chemistry Supervisor.

5.2 REFER to Figure - 2, Hope Creek PASS Storage Location, for acceptable locations.

5 3 ENSURE that radiation protection provides escorts. survey, posting, and shielding as appropriate.

54 ENSURE that all samples are labeled, and entered in the sample log, including storage location, 5.5 KEEP the Chemistry Supervisor informed of transportation and storage activities.

NUCLEAR COMMON Page 13of 18 Rev. 03

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ATTACHMENT 6 Page 1 of 1 CHEMISTRY GUIDELINES - OUTSIDE SYSTEMS 1.0 Communications ENSURE that all personnel dispatched to the outside systems have a portable radio and maintain communications with the CR. OSC, TSC. or CP as appropriate.

2.0 HOPE CREEK ACTIONS DURING POWER OPERATION 2.1 CHECK the status of (EQ) Service Water Hypochlorination.

22 CHECK the status of (DD) Circ Water Hypochlorination.

2.3 CHECK the status of (DE) Circ Water Caustic Addition.

2.4 CHECK the status of (DF) Cooling Tower Blowdown Dechlorination.

3.0 HOPE CREEK ACTIONS DURING POWER REDUCTION 31 DECREASE (EQ) Service Water Hypochlorination.

3.2 DECREASE (DD) Circ Water Hypochlorination.

3,3 DECREASE (DE) Circ Water Caustic Addition.

34 INCREASE (DF) Cooling Tower Blowdown Dechlorination.

3.5 ANALYZE the effluent at the Cooling Tower Blowdown.

40 HOPE CREEK ACTIONS AFTER A REACTOR SCRAM 4 1 ISOLATE (EQ) Service Water Hypochlorination_

4.2 ISOLATE (DD) Circ Water Hypochlorination.

4 3 ISOLATE or Secure (DE) Circ Water Caustic Addition.

44 INCREASE (DF) Coo!ing Tower Blowdown Dechlorination.

4 5 ANALYZE the effluent at the Cooling Tower Blowdown.

NUCLEAR COMMON Page 14 of 18 Rev. 03

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ATTACHMENT 7 Page 1 of 1 CHEMISTRY GUIDELINES - PRIMARY TO SECONDARY LEAK (SALEM ONLY) 1.0 POWER OPERATION and POWER REDUCTION FOR SALEM 1.1 IF appropriate.

THEN SAMPLE and analyze the following for isotopic content:

"* Steam Generator Liquid

"* RCS Liquid

"* Air Ejector Effluent 1.2 IF appropriate.

THEN NOTIFY Radiation Protection that radiological surveys in the secondary plant may be necessary. with emphasis on filters and demineralizers.

2.0 SALEM REACTOR TRIP 2.1 REQUEST that the control room open the blowdown isolation valves.

2.2 IF appropriate, THEN SAMPLE and analyze the following for isotopic content:

"* Steam Generator Liquid

"* RCS Liquid 2,3 IF appropriate.

THEN NOTIFY Radiation Protection that radiological surveys in the secondary plant may be necessary, with emphasis on filters and demineralizers NUCLEAR COMMON Page 15 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

FIGURE - 1 Page 1 of 2 SALEM HIGH ACTIVITY SAMPLE STORAGE LOCATION ELEVATION 100 FOOT NUCLEAR COMMON Page 16 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

FIGURE - 1 Page 2 of 2

"* Blowdown panel room, elevation 100'. A lead brick cave will be available for optimum shielding. (a)

"* Fuel handling annex (small truck bay) elevation 100'. (b)

"* Hot drum storage cask labyrinth, adjacent to Fuel Handling Building yard, elevation 100'. (c)

"* Hot drum storage area, elevation 100',

Solid Radwaste.(d)

"* Waste evaporator bottoms hold tank area, elevation 100'. (e)

NUCLEAR COMMON Page 17 of 18 Rev. 03

NC.EP-EP.ZZ-0311 (Q)

FIGURE - 2 PAGE 1 OF 1 HOPE CREEK PASS STORAGE LOCATION RESPIRATOR REPAIR FACILITY F- D

-1 INSTURMANT IL- ISSUE CONTROLLED ACCESS II EQUIPMENT REMOVAL AREA AREA D RiD PRO COUNT ROOM CONTROlmLE CORRIDOR J II

-Ii cumA 11 CHEN COUNTING AB ROOM IL TECH OFFICE E -InM ELECTRICAL ACCESS PASS AREA SUPERVISOR'S SAMPLE OFFICE STORAGE CONTROLLED CAVE HOT CHEM LAB CALIBRATION CIEM AND REPAIR STORAGE SHOP SERVICE/RAD'IASTE AREA 124' ELEVATION NUCLEAR COMMON Page 18 of 18 Rev. 03

PAGE 1 OF 1 PSEG NUCLEAR LLC NC.EP-EP.ZZ-0306 (Q) - REV. 01 EMERGENCY AIR SAMPLING USE CATEGORY: II REVISION

SUMMARY

1. This revision satisfies the requirement for a biennial review.

2. Revised Cm 3 to cc in Form - 1 to be consistent throughout the procedure.

3. Revised Manager - EP & IT to Emergency Preparedness Manager throughout the procedure.

4. Revised the position responsible for approving emergency preparedness documents from Vice President Operations to Director Operations per revision 11 of emergency plan, section 17.

IMPLEMENTATION REQUIREMENTS Implementation Date: 5- 2,-v Z'

APPROVED: ___________ __________ /-7 -t 6~

Em gency Preparedness Manager Date APPROVED: /j )/_,_

Director Operations Date T0I , .

NC.EP-EP.ZZ-0306 (Q)

EMERGENCY AIR SAMPLING TABLE OF CONTENTS SECTION TITLE PAGE TABLE OF CONTENTS 1 1.0 P UR P O S E ............................................................ 2 2.0 PREREQ UISITES .................................................. 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure .......................................... 2 3.0 PRECAUTIONS AND LIMITATIONS ........................ 2 3.1 Precautions And Limitations To Be Followed Prior To Implementing This Procedure ....................... 2 4.0 EQUIPMENT / MATERIAL REQUIRED ....................... 2 4.1 Personnel Protective Equipment ....................... 2 4.2 Sampling and Counting Equipment ............... 3 5.0 PROCEDURE ................................. 3 5.1 Preparation For Emergency Air Sampling ...... 3 5.2 Performing Emergency Air Sampling ............... 5 5.3 Analyzing Emergency Air Samples ............... 6 6.0 R E CO R D S ........................................................... 6

7.0 REFERENCES

.................................................. 6 7.1 R eferences .................................................. 6 7.2 Cross References .......................................... 6 ATTACHMENTS Emergency Air Sampling Assembly 7 FORMS Form 1 NC.EP-EP.ZZ-0306-1 Emergency Air Sample and Analysis.. 8 Nuclear Common Page 1 of 12 Rev. I

NC.EP-EP.ZZ-0306 (Q) 1.0 PURPOSE To provide guidance for Radiation Protection Technicians (RPT) and the Radiation Protection Supervisors (RPS) to perform emergency grab sampling of airborne radioactive material.

2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure 2.1.1 Implement this procedure at:

The discretion of the Operations Superintendent (OS).

The discretion of Radiological Assessment Coordinator (RAC).

2.1.2 The RPS has been directed or has determined that emergency grab air sampling is to be performed by RPT(s).

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations To Be Followed Prior To Implementing This Procedure:

3.1.1 It is recommended that initials be used in the place keeping sign-offs, instead of checkmarks, if more than one person may implement this procedure.

3.1.2 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.

3.1.3 Steps listed in this procedure may be performed in the order deemed appropriate for the emergency situations. Only steps applicable to the specific emergency need be performed.

4.0 EQUIPMENT 4.1 Personnel Protective Equipment 4.1.1 Protective clothing and equipment listed in the appropriate Radiation Work Permit (RWP) or as determined necessary by the SRPT, Onshift Radiation Nuclear Common Page 2 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

Protection Technician (ORPT), Radiation protection Supervisor Exposure Control (RPS - EXP) or RAC.

4.2 Sampling and Counting Equipment 4.2.1 Count room equipment including:

"*Multi-channel analyzer (MCA)

"*Shelves, fixtures, and geometries for counting cartridges, filters, poly bottle or vials on the MCA

"*Vials and needles for fractioning the 1 liter poly bottle sample, if required NOTE The equipment listed in 4.2.2 to 4.2.9 should be obtained from the emergency locker at the affected unit CP and instrument issue room. If necessary, equipment may be obtained from the unaffected units CP and instrument issue.

4.2.2 Emergency air sample assembly as shown in Attachment 1, Emergency Air Sampling Assembly.

4.2.3 Silver zeolite sampling cartridges.

4.2.4 Parliculate air filters.

4.2.5 1 liter poly bottle with septum lid.

4.2.6 RASP air sample pump and connecting hoses.

4.2.7 Plastic bags large enough to contain the emergency air sample assembly.

4.2.8 Tape 4.2.9 Radiation survey instruments, Eberline RO-2/RO-2A, or equivalent.

5.0 PROCEDURE 5.1 Preparation For Emergency Air Sampling 5.1.1 SRPT/ORPT/RPS-EXP/RPS should:

Nuclear Common Page 3 of 12 Rev. I

NC.EP-EP.ZZ-0306 (Q)

A. EVALUATE the radiological conditions a sampling team is expected to encounter.

B. CREATE a sampling team plan lAW NC.EP-EP.

ZZ-0304 (Q) Operational Support Center Radiation Protection Response.

C. ENSURE the sampling team signs on appropriate RWP.

D. ESTABLISH arrangements for sample analysis including:

"* DELIVERY point for samples.

"* DIRECTING the count room to be prepared for sample analysis.

5.1.2 RPTs on the sampling team should:

A. OBTAIN 1 liter poly bottle with septum lid.

B. FILL the bottle with water, cap bottle, place in plastic bag, and tape the bag closed.

C. OBTAIN a 9.5 liter Marinelli emergency air sample assembly as shown in Attachment 1.

5.1.3 IF the marinelli is not reading between 20 and 30 inches of mercury on the gauge, THEN evacuate the 9.5 liter marinelli in a clean, low-background area in the following manner:

A. REMOVE the sample head and attach a vacuum hose to the sample head connection at the isolation valve.

B. CONNECT the other end of the vacuum hose to a RASP vacuum pump or equivalent.

C. OPEN the isolation valve and start the vacuum pump.

D. EVACUATE the marinelli to as close to 30 inches of Mercury (in./Hg), as possible, indicated on the vacuum gauge.

E. CLOSE the isolation valve and stop the RASP pump, when maximum vacuum has been reached.

F. REMOVE the vacuum hose from the isolation valve.

G. ATTACH the sample head.

Nuclear Common Page 4 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q) 5.1.4 INSPECT the sample head to ensure that gaskets and 0-rings are intact, clean and properly seated. Replace if necessary.

5.1.5 LOAD the sample head with a particulate paper filter and silver zeolite cartridge, ensuring the cartridge is properly inserted lAW the labeled flow direction arrow.

5.1.6 BAG the emergency air sample assembly in a plastic bag and tape so that only the isolation valve and sample head is exposed.

5.1.7 IMPLEMENT Form 1, Emergency Air Sampling and Analysis, for documenting sample and analysis data 5.2 Performing Emergency Air Sampling 5.2.1 RPTs on the Sampling Team should:

A. ATTEND the sampling team briefing.

B. PROCEED to the designated sampling point.

5.2.2 PERFORM the sampling by:

A. RECORD the vacuum gauge reading on the 9.5 liter emergency air sample assembly on Form- 1.

B. OPEN the emergency air sample assembly isolation valve.

C. CLOSE the isolation valve and record the time on Form 1, when the pressure gauge reads zero.

D. OPEN the bag containing the 1 liter poly bottle.

E. UNCAP the 1 liter poly bottle.

F. POUR the water out.

G. RECAP the 1 liter poly bottle.

H. RESECURE the bag and record sample time on Form 1.

I. PROCEED to a pre-designated or low-dose area.

J. REMOVE the particulate filter and silver zeolite cartridge from the emergency air sample assembly bagging both of them.

K. SURVEY the air sample components Nuclear Common Page 5 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

L. RECORD survey results on the bags.

M. DELIVER the air samples and Form 1 to the pre-designated pickup location for analysis.

N. NOTIFY the RPS-EXP of the survey results on the bagged samples.

5.3 Analyzing Emergency Air Samples NOTE The quick "rule-of-thumb" calculations are rough estimates of airborne activity. Sample analysis on a Multi - Channel Analyzer (MCA) should be performed on all emergency air samples, except the 9.5 liter marineli, and results recorded in the appropriate section of Form - 1.

5.3.1 PERFORM AND RECORD the quick "rule-of-thumb" estimates of airborne activity in accordance with the instructions in Form 1.

5.3.2 DELIVER the emergency air samples to the count room for follow-up analysis.

6.0 RECORDS Return completed procedure and any information or data thought to be pertinent, to the Emergency Preparedness Manager.

"-7 REFERENCES

7.1 REFERENCES

7.1.1 NUREG-0737, Clarification of TMI Action Plan Requirements, November 1980.

7.1.2 NUREG-4297, Source Size Correction Factor 7.1.3 Rad Health Handbook, Gamma Constants for 1-131 and Xe-133.

7.2 CROSS REFERENCES 7.2.1 PSEG Nuclear Emergency Plan Nuclear Common Page 6 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

ATTACHMENT 1 Page 1 of 1 EMERGENCY AIR SAMPLE ASSEMBLY VACUUM GAUGE 31/

10O Nuclear Common Page 7 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

Form -1 Page 1 of 5 EMERGENCY AIR SAMPLING AND ANALYSIS (FORM 1)

Date: Plant / Unit (circle) Salem 1 Salem 2 Hope Creek 1.0 9.5 LITER MARINELLI EMERGENCY AIR SAMPLE ASSEMBLY:

Location: Gauge Reading (in. Hg)

(prior to sampling)

Sample Time: Corrected Volume (cc)

(from table below)

Gauge Volume Gauge Volume Gauge Volume (in. Hg) (cc) (in. Hg) (cc) (in. Hg) (cc) 30 9500 26.5 8392 23 7283 29.5 9342 26 8233 22.5 7125 29 9183 25.5 8075 22 6967 28.5 9025 25 7917 21.5 6808 28 8867 24.5 7758 21 6650 27.5 8708 24 7600 20.5 6492 27 8550 23.5 7442 20 6333 Post-Sampling Contact Dose (mR/hr)

(marinelli)

Post-Sampling Contact Dose (mRPhr)

(bagged silver zeolite cartridge)

Post-Sampling Contact Dose (mR/hr)

(bagged particulate filter)

Nuclear Common Page 8 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

Form -1 Page 2 of 5 2.0 AIR SAMPLE ANALYSIS: RULE OF THUMB METHODS METHOD "A": DETERMINATION OF NOBLE GAS (N/G) SAMPLE CONCENTRATION UTILIZING THE ONE FOOT RULE OF THUNB.

1. Fill in the blanks 1 through 9 listed below.

2. Do not complete remaining steps if MCA printout is attached.

3. Record the One Foot dose rate in Space A and C.

4. Record the Time and Date the One Foot dose rate was taken in Space B.

5. Multiply the value in Space C by the value in Space D.

6. Record the answer in Spaces E and F.

7. Record the Volume Reading from blank 9 in Space G.

8. Divide the value in Space F by the value in G.

9. Record the answer in Space H. This will be the N/G Sample Concentration in uCi/cc.

(BLANKS 1-9)

1. Air Sample Number: 2. RWP Number:

3. Location: 4. Date/Time: - - / .

(Sample Collected) (Sample Collected)

5. Type of Sample: 6. Person Performing Analysis:

7. Multi Channel Analysis (MCA) Printout Attached YES/NO (circle one)

8. General Area Dose Rate at Detector well if MCA printout is Attached mR/hr.

9. Volume Obtain From Page 1 of Form - 1: cc.

(SPACES A-H)

A. mR/hr B. Date/Time: /

(1 Foot Dose Rate) (1 Foot Dose Rate Was Taken)

C. R/hr * (D. 0.18 ) = E. uCi (1 Foot Dose Rate) (Conversion Factor)

F. uCi / G. cc = H _ _ _ uCi/cc (Volume from Blank 9) (Sample Concentration)

Nuclear Common Page 9 of 12 Rev. I

NC.EP-EP.ZZ-0306 (Q)

Form -1 Page 3 of 5 METHOD "B": DETERMINATION OF N/G SAMPLE CONCENTRATION UTILIZING THE TWO FOOT RULE OF THUMB.

1. Fill in the blanks 1 through 9 listed below.

2. Do not complete remaining steps if MCA printout is attached.

3. Record the Two Foot dose rate in Space A and C.

4. Record the Time and Date the Two Foot dose rate was taken in Space B.

5. Multiply the value in Space C by the value in Space D.

6. Record the answer in Spaces E and F.

7. Record the Volume Reading from blank 9 Space G.

8. Divide the value in Space F by the value in G.

9. Record the answer in Space H. This will be the N/G Sample Concentration in uCi/cc.

(BLANKS 1-9)

1. Air Sample Number: 2. RWP Number:

3. Location: 4. Date/Time: - - /

(Sample Collected) (Sample Collected)

5. Type of Sample: 6. Person Performing Analysis:

7. Multi Channel Analysis (MCA) Printout Attached YES/NO (circle one)

8. General Area Dose Rate at Detector well if MCA printout is Attached mR/hr.

9. Volume Obtain From Page 1 of Form - 1 cc.

(SPACES A-H)

A. mR/hr B. Date/Timie:/

(2 Foot Dose Rate) (2 Foot Dose Rate Was Taken)

C. mR/hr * (D. .56 ) = E. uCi (2 Foot Dose Rate) (Conversion Factor)

F. uCi / G. cc = H. uCi/cc (Volume from Blank 9) (Sample Concentration)

Nuclear Common Page 10 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

Form -1 Page 4 of 5 METHOD "C": DETERMINATION OF IODINE SAMPLE CONCENTRATION UTILIZING THE ONE FOOT RULE OF THUMB.

1. Fill in the blanks 1 through 9 listed below.

2. Do not complete remaining steps if MCA printout is attached.

3. Record the One Foot dose rate in Space A and C.

4. Record the Time and Date the One Foot dose rate was taken in Space B.

5. Multiply the value in Space C by the value in Space D.

6. Record the answer in Spaces E and F.

7. Record the Volume Reading from blank 9 in Space G.

8. Divide the value in Space F by the value in G.

9. Record the answer in Space H. This will be the Iodine Sample Concentration in uCi/cc.

(BLANKS 1 - 9)

1. Air Sample Number 2. RWP Number:

3. Location: 4. Date/Time:_ - /

(Sample Collected) (Sample Collected)

5. Type of Sample:. 6. Person Performing Analysis:

7. Multi Channel Analysis (MCA) Printout Attached YES/NO (circle one)

8. General Area Dose Rate at Detector well if MCA printout is Attached mR/hr.

9. Volume Obtain From Page 1 of Form - 1: cc.

(SPACES A-H)

A. mR/hr B. Date/Time: 1 Foot Dose Rate /Was T-aken)

(1 Foot Dose Rate)

C. mR/hr * (D. 400 ) = E. uCi (1 Foot Dose Rate) (Conversion Factor)

F. uCi / G. cc = H. uCi/cc (Volume from Blank 9) (Sample Concentration)

Nuclear Common Page 11 of 12 Rev. 1

NC.EP-EP.ZZ-0306 (Q)

Form -1 Page 5 of 5 METHOD "D": DETREMINATION OF IODINE SAMPLE CONCENTRATION UTILIZING THE TWO FOOT RULE OF THUMB.

1. Fill in the blanks 1 through 9 listed below.

2. Do not complete remaining steps if MCA printout is attached.

3. Record the Two Foot dose rate in Space A and C.

4. Record the Time and Date the Two Foot dose rate was taken in Space B.

5. Multiply the value in Space C by the value in Space D.

6. Record the answer in Spaces E and F.

7. Record the Volume Reading from blank 9 in Space G.

8. Divide the value in Space F by the value in G.

9. Record the answer in Space H. This will be the Iodine Sample Concentration in uCi/cc.

(BLANKS 1-9)

1. Air Sample Number: 2. RWP Number:

3. Location: 4. Date/Time: - - /

(Sample Collected) (Sample Collected)

5. Type of Sample: 6. Person Performing Analysis:

7. Multi Channel Analysis (MCA) Printout Attached YES/NO (circle one)

8. General Area Dose Rate at Detector well if MCA printout is Attached mR/hr.

9. Volume Obtain From Attachment 3: cc (SPACES A-H)

A. mR/hr B. Date/Time: /

(2 Foot Dose Rate) (2 Foot Dose Rate Was Taken)

C. mR/hr * (D. 1600 ) = E. uCi (2 Foot Dose Rate) (Conversion Factor)

F. uCi / G. c = H. uCi/cc (Volume from Blank 9) (Sample Concentration)

Nuclear Common Page 12 of 12 Rev. 1

Page 1 of 1 PSEG NUCLEAR LLC NC.EP-EP.ZZ-0305 (Q) - REV. 02 POTASSIUM IODIDE (KI) ADMINISTRATION USE CATEGORY: II REVISION

SUMMARY

1. Added the November 2001 Food and Drug Administration Guidance (Potassium Iodide As A Thyroid Blocking Agent In Radiation Emergencies) to the reference Section 7.0.

2. Revised the position that approves emergency plan implementing procedures from Vice President - Operations to Director Operations.

3. This revision satisfies the requirement for a biennial review.

IMPLEMENTATION REQUIREMENTS r %

Procedure Implementation Date: /1--3. .

f. . ,

p. :

L,!1 7'-

APPROVED:- ij _-/_-__

Emerg lcy Preparedness Manager Date APPROVED:

Director Operations Date

NC.EP-EP.ZZ-0305 (Q)

POTASSIUM IODIDE (KI) ADMINISTRATION TABLE OF CONTENTS Section Title Page 1 .0 P UR P O S E .................................................................................................... 2 2 .0 P R E R E Q UIS IT E S ......................................................................................... . 2 2.1 Prerequisites To Be Followed Prior To Implementing This P ro c e d u re .............................................................................. 2 3.0 PRECAUTIONS AND LIMITATIONS .......................................................... 2 3.1 Precautions And Limitations To Be Followed Prior To Implementing T h is P ro ce d u re ....................................................................... . 2 4.0 EQUIPMENT/ MATERIAL REQUIRED .......................................................... 3 5 .0 P R O C E D UR E ................................................................................................. 3 5.1 Evaluate The Need For KI Use In The Following Manner ............... 3 5.2 KI Issue And Documentation Should Be Performed In The F o llo w ing m a n n e r ................................................................... 4 6 .0 R E C O R D S ... ............................................................................................ .... 4 7 .0 R E F E R E NC E S .......................................................................................... .... . 4 7 .1 R e fe re n c e s .................... ........... ...................................... . .... 4 7 .2 C ro ss R efe re nce s ................................................................... . 5 ATTACHMENTS Thyroid Committed Dose Rate vs. Iodine-1 31 6 Concentration .......... Package Insert for Thyro-Block Tablets ............................................... 7 FORMS FORM - 1 KI SIDE EFFECTS/ADMINISTRATION SIGN - OFF F O R M... ... ... ... ... ... ... ... ............................. ... ....................... ... ... ... ... . 9 Nuclear Common Page 1 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q) 1.0 PURPOSE This procedure provides guidance to emergency response personnel for administration of Potassium Iodide (KI) during an emergency at Hope Creek or Salem Nuclear Generating Stations.

2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure 2.1.1 This procedure should be implemented by the Radiological Assessment Coordinator (RAC), or the Operations Superintendent (OS), if the RAC has not yet arrived.

2.1.2 Implement this procedure at:

The discretion of the RAC, or the OS, if the RAC has not yet arrived.

The discretion of the Radiological Support Manager (RSM), or the Operations Superintendent (OS) if the RSM has not yet arrived.

When airborne 1-131 levels are > 5E-7 uCi/cc.

When a calculated dose of 10 Rem 1-131 to the thyroid is likely to be received.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations To Be Followed Prior To Implementing This Procedure:

3.1.1 Administer KI to Emergency Response Personnel When:

Airborne 1-131 levels are > 5E-7p.Ci/cc.

A calculated dose of 10 Rem 1-131 to the thyroid is likely to be received.

When the RAC feels it is necessary.

When the RSM feels it is necessary.

3.1.2 Authority to administer KI to onsite personnel shifts from the OS to the RAC, when the RAC assumes his/her duties.

Nuclear Common Page 2 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q) 3.1.3 The RSM assumes authority to administer KI to offsite personnel when the RSM assumes his/her duties.

3.1.4 Lack of available KI tablets should not prevent life-saving operations from being initiated.

3.1.5 KI may be taken up to four hours after an exposure and still provide a 50%

reduction in dose received.

3.1.6 KI should be continued for ten days (one tablet per day), after KI is administered, radioiodine concentration is verified and/or calculated dose is determined.

3.1.7 The Medical Director must approve additional dosage.

3.1.8 It is recommended that initials be used in the place keeping sign-offs, instead of checkmarks, if more than one person may implement this procedure.

3.1.9 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.

4.0 EQUIPMENT/ MATERIAL REQUIRED Thyro-Block Tablets are supplied in the Emergency Response Facility equipment lockers and kits.

5.0 PROCEDURE 5.1 Evaluate The Need For KI Use In The Following Manner:

5.1.1 IF airborne 1-131 levels are > 5E-74.Ci/cc, THEN the RAC or RSM should consider KI administration.

5.1.2 DETERMINE the Committed Dose Rate from the airborne 1-131 cloud using Attachment 1, Thyroid Committed Dose Rate vs.

Airborne Iodine-131 Concentration.

NOTE KI is located in emergency equipment lockers in the Control Room, Control Point, TSC, and Onsite/Offsite Field Team Kits.

Nuclear Common Page 3 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q) 5.2 KI Issue And Documentation Should Be Performed In The Following Manner:

5.2.1 OBTAIN the KI tablets from emergency equipment lockers and kits.

5.2.2 ENSURE all personnel being administered KI read Attachment 2.

Package Insert For Thyro-Block Tablets, prior to taking KI.

5.2.3 ENSURE all personnel being administered KI fill out and sign in appropriate area of page 1 of Form - 1, KI Side Effects/

Administration Sign Off Form, prior to taking KI.

5.2.4 ADMINISTER one KI tablet to each individual that could enter a high level of radioiodine concentration.

5.2.5 ENSURE Form - 1, page 2, is filled out after the administration of KI.

5.2.6 INFORM the Medical Department of individuals administered KI.

6.0 RECORDS Return completed procedure, original copies of Forms to the Emergency Preparedness Manager and forward or FAX copies of Form-i, page 2, to the Medical Department.

7.0 REFERENCES

7.1 References 7.1.1 Salem and Hope Creek UFSAR Section 13.3, Emergency Planning.

7.1.2 Federal Register, December 15, 1978: Potassium Iodide as a Thyroid Blocking Agent in a Radiation Emergency: Proposed Recommendation for Use.

7.1.3 Package Insert for THYRO-BLOCK TABLETS, IN-0472-01, Rev. 4/85, Wallace Laboratories, Division of Carter-Wallace, Inc; Cranbury, New Jersey 08512.

7.1.4 PSEG Nuclear Emergency Plan 7.1.5 Potassium Iodide As A Thyroid Blocking Agent In Radiation Emergencies Food and Drug Administration Guidance, November 2001 Nuclear Common Page 4 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q) 7.2 Cross References 7.2.1 NC.EP-EP.ZZ-0301(Q), Shift radiation protection response 7.2.2 NC.EP-EP.ZZ-0302(Q). Radiological Assessment Coordinator Response 7.2.3 NC.EP-EP.ZZ-0310(Q),Radiation Protection Supervisor - Offsite and Field Monitoring Team Response Nuclear Common Page 5 of 10 Rev. 02

A ,CHMENT1 NC.EP-EP.ZZ-0305(Q, UCi1cc I 131 THYROID COMMITTED DOSE RATE VS. IODINE - 131 CONCEN 1 .OOE-05 i--F * + + I- 4--4 4 ____--_

-i--F 4 4- 4- 4- 4--L-I-.J-

+ F-F-f F 4- 4- 4- 4-.--4------J-J-

- F +/- 4 4- F-F-F F 4- 4- 4 4-4--

___________ t -f F + + -----F I--i- F 4- .J-L---4 f F 4 F 4- 4-4--i--4-4 4- F 4- 4 1 F-i--F F +-+ + -F-4-4--

1.00E-06 1.OOE-07 1 .OOE-08 1.OOE-09 ILJ IUU 1UUU 10000 COMMITTED mrern/hr to the THYROID (This graph was generated using the 1131 Dose Commitment Conversion Factor of approximately 2.OE+09 mR/hr/uci/cc for adult provided in the ODCM).

NUCLEAR COMMON Page 6 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q)

ATTACHMENT 2 PAGE 1 OF 2 PACKAGE INSERT FOR THYRO - BLOCK TABLETS 1.0 HOW POTASSIUM IODIDE WORKS

"* Certain forms of iodine help your thyroid gland function properly. Most people get the iodine they need from foods, and iodized salt. The thyroid can "store" or hold only a certain amount of iodine.

" In a radiological emergency, radioactive iodine may be released into the air.

This material may be inhaled or ingested. It may enter the thyroid gland and cause damage. The damage would probably not be detected for years.

Children are most sensitive to thyroid damage.

" If you take potassium iodide, it will fill your thyroid gland with non-radioactive iodine. The non-radioactive iodine acts as a blocking agent reducing the chance that harmful radioactive iodine will enter the thyroid gland.

2.0 WHO SHOULD NOT TAKE POTASSIUM IODIDE NOTE You may take potassium iodide if you are taking medicine for a thyroid problem (for example, a thyroid hormone or anti-thyroid drug). Pregnant and nursing women, babies and children may also take potassium iodide.

2-1 People who should not take potassium iodide are:

People who are allergic to iodine.

"* People with kidney problems.

"* Persons on certain high blood pressure medications (ACE Inhibitors).

30 HOW AND WHEN TO TAKE POTASSIUM IODIDE

Potassium iodide should be taken as soon as possible after instructed by supervision. You should take one dose every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . More will not help you because the thyroid can "hold" only limited amounts of iodine. Larger doses will increase the risk of side effects. You will probably be told not to take the drug for more than ten days.

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NC.EP-EP.ZZ-0305 (Q)

ATTACHMENT 2 PAGE 2 OF 2 4.0 SIDE EFFECTS

" Usually, side effects of potassium iodide occur when people take higher doses for a long period of time. You should be careful not to take more than the recommended dose or take it for longer than instructed. Side effects are unlikely because of the low dose and the short time you will be taking the tablets.

" Possible side effects include skin rashes, swelling of the salivary glands, and "iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).

" A few people have an allergic reaction with more serious symptoms.

Serious symptoms include fever and joint pains, or swelling of parts of the face and body, and at times severe shortness of breath requiring immediate medical attention.

" Taking potassium iodide rarely causes over activity of the thyroid gland, under activity of the thyroid gland or enlargement of the thyroid gland (goiter).

5.0 WHAT TO DO IF SIDE AFFECTS OCCUR

If the side effects are severe or if you have an allergic reaction, stop taking potassium iodide and contact supervision.

Nuclear Common Page 8 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q)

FORM - 1 Page 1 of 2 KI SIDE EFFECTS/ADMINISTRATION SIGN - OFF FORM AUTHORIZED BY:

ADMINISTERED BY:

My signature indicates that I have read and understand pages 1 and 2 of Attachment 2, Package Insert For Thyroid-Block Tablets.

Nuclear Common Page 9 of 10 Rev. 02

NC.EP-EP.ZZ-0305 (Q)

FORM - 1 Page 2 of 2 KI SIDE EFFECTS/ADMINISTRATION SIGN - OFF FORM SOCIAL .I... AUTHORIZED ADMINISTERED NAME OF INDMIDUAL SEC. NO. DOSAGE BY BYDATEITIME COMMENTS

__....._______....____ __ DATEITIME __ __. ...

i +i 4 4 + 4 4 .4 T t I 4 t t 4 i i 4 i .4 I I 1 t i 4 t t t 4 4 t i 4i I F 4 + 4 4-f + 4 T t I 4 4 t +/- 4 + 4 t I +

I 1 t i 4.

i i i i

- ____________ ________________ I ___________________ _____________________

Nuclear Common Page 10 of 10 Rev. 02

PSEG Internal Use Only PSEG NUCLEAR LLC Page 1 of 1 NC.EP-EP.ZZ-0304 (Q) Rev. 07 OPERATIONAL SUPPORT CENTER (OSC) RADIATION PROTECTION RESPONSE USE CATEGORY: II REVISION

SUMMARY

1. This revision satisfies the requirement for a biennial review.

2. Revised who is responsible to approve emergency plan implementing procedures from Vice Presidet Operations to Director Operations.

3. Revised Attachment 6, R16 to say Salem Unit 2 Only.

4. Revised TLD to Dosimeter in step 2.1.2.

5. Added the title of the attachment being referred to in Step 5.1.5.

6. Reworded third bullet in note after Step 5.1.11.

IMPLEMENTATION REQUIREMENTS I 1 Implementation Date: i 3.5'- Z '-

C CI C...-

APPROVED: _-__.-_

Emergency Preparedness Manager Date APPROVED: A/iA /____

Director Operations Date

NC.EP-EP.ZZ-0304(Q)

TABLE OF CONTENTS Section Title Page 1.0 PURPOSE .................................................................................................... 2 2.0 PREREQUISITES ........................................................................................ 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure... 2 3.0 PRECAUTIONS AND LIM ITATIONS .......................................................... 2 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure .......................................................................................... 2 4.0 EQUIPM ENT REQUIRED ........................................................................... 2 5.0 PROCEDURE ............................................................................................. 3 5.1 The Radiation Protection Supervisor - Exposure Control Should Perform the Following ....................................................................... 3 5.2 Perform The Following Steps If Emergency Exposure is Required ........ 6 6.0 RECORDS .................................................................................................... 6

7.0 REFERENCES

............................................................................................. 7 7.1 References ........................................................................................ 7 7.2 Cross References .............................................................................. 7 7.3 Closing Documents ............................................................................ 7 ATTACHMENTS ATTACHMENT 1 Individual Radiation Exposure Record ............................................... 8 ATTACHMENT 2 ALARA Analysis Form ..................................................................... 10 ATTACHMENT 3 Selection And Authorization For Emergency Exposures .................. 12 ATTACHMENT 4 Onsite Protective Action Guidelines ................................................. 17 ATTACHMENT 5 Operation of The VAX LA120 Terminal ............................................ 18 ATTACHMENT 6 - RMS Quick Reference .......................................................... 21 FORMS FORM - 1 Habitability Log ........................................................................................... 25 FORM - 2 Individual's Current Yearly Dose .............................................................. 26 NUCLEAR COMMON Page 1 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q) 1.0 PURPOSE 1.1 To outline and describe the duties of the Radiological Protection Supervisor - Exposure Control (RPS-EXP).

1.2 To provide guidance to emergency response personnel for administration of Radiation Protection Team Response for the Operational Support Center (OSC) during an emergency at Hope Creek or Salem Nuclear Generating Station.

2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure.

Implement this procedure at:

"* The OS' discretion.

"* The manning of the OSC.

"* The declaration of an Alert.

2.2 All Onsite Emergency Response Organization members MUST have taken and PASSED Rad Worker Training/Rad Worker Requlification and have a DOSIMETER.

2.3 Personnel who implement this procedure shall be trained and qualified in accordance with (lAW) the Emergency Plan.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations To Be Followed Prior To Implementing This Procedure.

3.1.1 SALEM ONLY Dose Rates in the 78' Electrical Penetration Area could be higher than what is indicated on the R47 ARM. The R47 ARM is located across the room from Reactor Coolant System lines.

CAUTION should be exercised when entering this area.

It is recommended that initials be used in the place-keeping sign-off, instead of checkmarks, if more than one person may implement this procedure.

4.0 EQUIPMENT REQUIRED Equipment is provided In the Emergency Response Facility.

NUCLEAR COMMON Page 2 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q) 5.0 PROCEDURE 5.1 The Radiation Protection Supervisor - Exposure Control Should Perform The Following:

5.1.1 DIRECT habitability to be performed every 30 minutes and log the results on Form -1, Habitability Log.

5.1.2 COMPARE habitability results to Attachment 4, Onsite Protective Action Guidelines, and perform appropriate actions.

5.1.3 OBTAIN current status of the emergency from the OSCC.

NOTE

" An individual's yearly dose limit is automatically raised to 4500 mrem upon the declaration of an Alert or higher classification.

" The dose extension to 4500 mrem may be implemented in the PRORAD system. Attachment 1 has instructions on how to accomplish this task and return a person's dose limit to normal limits when appropriate.

" Dose Tracking may be performed using the PRORAD System instead of Attachment 1, Individual Radiation Exposure Record, if PRORAD is operational and the dose extension to 4500 mrem was implemented in the PRORAD system.

" No dose extension shall be allowed, if a person does not have a completed NRC Form 4 on record. The person's dose limit will be 400 mrem.

5.1.5 ENSURE 1.0 of Attachment 1, Individual Radiation Exposure Record is completed for the onsite emergency response personnel assigned to the OSC/CP.

5.1.6 ENSURE control of Attachment 1 is maintained in order to expedite and provide a tracking mechanism for OSC/CP personnel activities and exposures.

5.1.7 NOTIFY the OSCC prior to any CP teams being sent out into the plant and ensure they are tracked on the OSC Team Status Board.

NUCLEAR COMMON Page 3 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

NOTE An individual, in lieu of a team, may be dispatched by the OSCC. The individual should be in contact with the CP or OSC via some type of audio communications (page, radio, telephone, etc.) and should check-in every 15 or 30 minutes with the OSC or CP.

An individual should not be dispatched under the following circumstances:

"* An individual's exposure is expected to exceed 1000 mrem External Dose Equivalent (EDE).

"* The task would require entry into a "Harsh Environment Area",

(i.e., steam atmosphere, a heat stress area, etc.).

"* Acts of sabotage or suspected sabotage.

5.1.8 ENSURE all OSC and CP teams are made up of at least two people, unless a task meets the above note's criteria for dispatching an individual.

5.1.9 IF travel path dose rates, or dose rates at destination are

>1000 mR/hr EDE, THEN COMPLETE Attachment 2, ALARA Analysis Form.

5.1.10 IF travel path dose rates, or dose rates at destinations are

<1000 mR/hr EDE, THEN Attachment 2 does NOT have to be completed.

5.1.11 PROVIDE job status information to the Radiological Assessment Coordinator (RAC) concerning jobs, as thought appropriate.

NOTE

"* Radiological briefings of teams should take place during pre-job briefing. Two separate briefings (pre-job and radiological) should not be the normal method of performing OSC pre-job briefings.

"* No duplicate radiological briefings should take place at the Control Point prior to the OSC team entering the Radiological Control Area (RCA).

"* Pre-job briefings should try to meet a goal of not lasting longer than 20 minutes.

Circumstances may arise that make meeting this goal impossible, but the team should try to meet the 20 minute goal.

NUCLEAR COMMON Page 4 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q) 5.1.11 BRIEF all OSC team members on appropriate radiological conditions.

5.1.13 DEBRIEF all teams and ensure 2.0 of Attachment 1 is completed.

5.1.14 OBTAIN plant status updates from the OSCC.

5.1.15 OBTAIN current RMS status from the most appropriate location listed below:

(HOPE CREEK ONLY)

"* the VAX LA120 utilizing Attachment 5, Operation of the VAX LA120.

"* Control Point personnel (RM-1 1).

"* TSC Radiological Assessment personnel.

(SALEM ONLY)

"* Shift Radiation Protection Technician (SRPT)

"* Unit 2 RMS Computer

"* TSC Radiological Assessment personnel.

NOTE Noble Gas Offsite Dose Calculation Manual/Federal Limits for a Radiological Release are:

"* Hope Creek = 1.20E+04 uCi/Second

"* Salem = 2.42E+05 uCilSecond 5.1.16 ESTABLISH contamination controls (no eating, no drinking, no smoking, proper postings, setting up step off pads and friskers) when any of the following have occurred.

"* A radiological release > Noble Gas Offsite Dose Calculation Manual/Federal Limits is in progress.

"* The potential of a radiological release > Noble Gas Offsite Dose Calculation Manual/Federal Limits limit is in progress.

NUCLEAR COMMON Page 5 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

"* Normal RCA boundaries have been breached.

"* At the RAC's discretion.

5.1.17 IF conditions listed in Step 5.1.16 are met, THEN NOTIFY the RAC or SRPT of the changing conditions.

NOTE It is part of the RAC's responsibilities to establish best routes in and out of the Owner Control Area, if Step 5.1.16 has been implemented.

HOPE CREEK ONLY Movements of teams outside the Power Block should be coordinated with the RAC.

SALEM ONLY Movements of teams in the Yard Area should be coordinated with the RAC.

5.1.18 COORDINATE with the OSCC and the RAC transportation of injured person(s) or person(s) receiving exposures of > 5 rem acute EDE dose to appropriate medical facilities.

5.2 Perform The Following Steps If Emergency Exposure Is Required:

NOTE

" Voluntary consent, pre-job briefings, and EDO authorization for Life Saving Tasks, that require Emergency Exposure, should be done verbally prior to, or during, the OSC Team being dispatched.

" Attachment 3 should be completed as soon as possible, after the return of the OSC Life Saving Team's return.

5.2.1 IMPLEMENT Attachment 3, Selection and Authorization for Emergency Exposures.

6.0 RECORDS Return completed procedure, original copies of Attachments to the Emergency Preparedness Manager.

NUCLEAR COMMON Page 6 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

7.0 REFERENCES

7.1 References 7.1.1 EPA 400-R-92-001: October 1991 7.1.2 Roger E. Linneman, M.D., Correspondence Dated November 24, 1993 7.1.3 10CFR20, Standards for Protection against Radiation, December 31, 1992.

7.1.4 Nuclear Business Unit Emergency Plan 7.2 Cross References 7.2.1 NC.EP-EP.ZZ-0302(Q), Radiological Assessment Coordinator Response 7.2.2 NC.EP-EP.ZZ-0301(Q), Shift Radiation Protection Response 7.3 Closing Documents Closing Document-027Z (CD-027Z) NRC Inspection Item 354/85-44-01 NUCLEAR COMMON Page 7 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 1 PAGE 1 OF 2 INDIVIDUAL RADIATION EXPOSURE RECORD DATE/TIME:

1.0 INDIVIDUAL INFORMATION Name: Badge Number:

NOTE Dose Tracking SHOULD be performed using the PRORAD System instead of Attachment 1, if PRORAD is operational and the dose extension to 4500 mrem was implemented in the PRORAD system.

1.1 PERFORM the following to implement the PRORAD dose extension to 4500 mrem:

1.1.2 CONTACT the Nuclear IT Network Operations to execute the SQL script titled "Emergency Exposure Limits - Increase" to raise Emergency Responder's dose limits to 4500 mRem in PRORAD.

The NUCLEAR "IT" NETWORK OPERATIONS PHONE NUMBERS are:

PRIMARY PHONE NUMBER: DID x7008 [Located At Nuclear Administration Building (TB 2)]

SECONDARY PHONE NUMBER: NETS x5009 (Located at EOF).

1.2 PERFORM the following to return dose limits to normal:

1.2.1 REQUEST the RAC's permission to contact the Nuclear IT Network Operations person to execute the SQL script titled "Emergency Exposure Limits - Normal" to return Emergency Responder's dose limits to normal in PRORAD upon termination of the emergency.

1.2.2 IF the RAC gives permission; CONTACT the Nuclear IT Network Operations person to execute the SQL script titled "Emergency Exposure Limits - Normal" to return Emergency Responder's dose limits to normal in PRORAD upon termination of the emergency using the phone numbers listed below:

The NUCLEAR "IT" NETWORK OPERATIONS PHONE NUMBERS

PRIMARY PHONE NUMBER: DID x7008 [Located At Nuclear Administration Building (TB 2)]

SECONDARY PHONE NUMBER: NETS x5009 (Located at EOF).

NUCLEAR COMMON Page 8 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT I PAGE 2 OF 2 2.0 OBTAIN the following information of all OSC Team Members, if PRORAD is not being used and log it on Form - 2, Individual's Current Yearly Dose.

"* NAME

"* BADGE NUMBER

"* CURRENT YEARLY DOSE in (mRem) 2.1 Job Specific Information Initial When Team Dose Rec'd Yr. Remaining Entered into Number (mRem) Dose (mRem)* PRORAD

Year Remaining Dos, - (mRem) = [(4500 mRem - Current Year Dose) - Dose Received]

NUCLEAR COMMON Page 9 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 2 Page 1 of 2 ALARA ANALYSIS FORM NOTE Planned exposure to an individual that is projected to result in dose to an individual > 4500 mrem(EDE) in this calendar year requires Emergency Exposure Authorization and needs to meet the criteria of accident mitigation or life saving tasks lAW Attachment 3.

1.0 Projected Dose Analysis:

1.1 Entry Route:

1.1.1 Time Required to reach job site: (hours) 1.1.2 Dose Rate(s) in areas that need to be traversed:_ (rem/hr) 1.1.3 Calculated Dose (indiviual dose): (rem)

(1.1.1 1.1.2

1.

=

1.2 = 1.1.3) 1.2 Tasks to be Performed:

1.2.1 Time required to perform job: (hours) 1.2.2 Dose rate in job areas: (rem/hr) 1.2.3 Calculated Dose (individual dose): (rem)

(1.2.1

1.2.2 = 1.2.3) 1.3 Exit Routes:

1.3.1 Time Required to exit area: (hours) 1.3.2 Dose Rate(s) in areas that need to be traversed: _ (rem/hr) 1.3.3 Calculated Dose (individual dose):. (rem)

(1.3.1

1.3.2 = 1.3.3) 1.4 Total Individual External Dose Equivalent: (rem)

[(1.1.3 + 1.2.3 + 1.3.3 = 1.4) Total Individual EDE]

NUCLEAR COMMON Page 10 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 2 Page 2 of 2 2.0 Team Briefing 2.1 Information Covered During Briefing:_

2.2 Personnel Attending Briefing:

NUCLEAR COMMON Page 11 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 3 Page 1 of 5 SELECTION AND AUTHORIZATION FOR EMERGENCY EXPOSURES 1.0 Effects Of Exposure To Radiation on the Human Body 1.1 The Following Information Is Based on ACUTE EDE Exposure to Radiation.

600 to 1000 to 1000 to 0 to 100 100 to 200 200 to 600 1000 5000 5000 RANGE (rem) (rem) (rem) (rem) (rem) (rem)

Vomiting None 5 to 50% > 300 rem 100% 100% 100%

100%

Delay Time ------- 3 hr. 2 hr. 1 hr. 30 minutes Leading None Bone Marrow GI Tract Central Organ Nervous Ststem Character- None Moderate Severe leukopenia, Diarrhea, Convulsions istic Signs leukopenia hemorrhage, infection, fever, tremor, purpura, epilation at > electrolyte ataxia 300 rem loss Therapy Reassur- Blood Blood Marrow Maintain Sedatives ance Monitoring Transfusion transplant? electrolytes Growth Antibiotics factors?

Prognosis Excellent Excellent Good Guarded Grave to Hopeless Incidence None None 0 to 80% 80% to 90 to 100%

of Death 90%

Leukopenia - drop in leukocyte (white blood cell) count.

Purpura - formation of small splotchy red or purple spots on the skin caused by rupture of a capillary with leakage of a small amount of blood under the skin layers.

Epilation - loss of hair. Will generally grow back within a month.

Ataxia - loss of muscular coordination.

2.0 GENERAL INFORMATION LIFE SAVING EMERGENCY DOSE AUTHORIZATION:

"* Voluntary consent, pre-job briefings, and EDO authorization that require Emergency Exposure for LIFE SAVING TASKS should be done verbally and can be performed during, the OSC Team being dispatched.

"* This attachment (Attachment 3) should be completed as soon as possible, after the return of the OSC Life Saving Team's return.

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NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 3 Page 2 of 5

"* Emergency Exposure should only be authorized by the Emergency Duty Officer (EDO) and cannot be delegated. The OS has this responsibility until the EDO assumes his responsibilities.

"* EDO's Emergency Exposure authorization may be done via telephone.

"* Emergency Exposure should be voluntary.

"* Individual who do volunteer should:

Have attended and passed Radiation Worker Training

Be above age 45, if available, physically and technically qualified to perform the task.

Not have previously received Emergency Exposure.

"* Emergency Exposure received should be added to the individual's current occupational radiation exposure history.

"* An individual's exposure is not considered to be an Emergency Exposure if his or her total exposure for the year is < 4.5 rem upon finishing an accident mitigation or life saving task and may still volunteer to receive Emergency Exposure.

"* Declared pregnant women SHALL NOT be allowed to volunteer for Emergency Exposure.

3.0 EXPOSURE CRITERIA LIFE SAVING EMERGENCY

"* Any and all actions necessary to preserve life, including, but not limited to:

Removal of injured personnel.

Providing medical treatment/first aid.

Providing ambulance service to injured personnel.

"* Planned Emergency Exposure Limit (PEEL) for life saving is 75 rem EDE.

4.0 ACCIDENT MITIGATION EMERGENCY EXPOSURE CRITERIA

Any and all actions necessary to mitigate an accident, including, but not limited to:

Performance of actions to prevent immediate deterioration of the plant status.

NUCLEAR COMMON Page 13 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 3 Page 3 of 5

Performance of actions to cause significant reduction of onsite or offsite radiological hazards.

Planned Emergency Exposure Limit (PEEL) for accident mitigation is 25 rem EDE.

5.0 TEAM BRIEFING Information Covered During Briefing:

NUCLEAR COMMON Page 14 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 3 Page 4 of 5 6.0 VOLUNTARY CONSENT I, the under signed, volunteer for Emergency Exposure:

PEEL (REM) NAME SIGNATURE BADGE #

.4 4. 1*

t 7.0 EMERGENCY EXPOSURE AUTHORIZATION I hereby authorize the planned Emergency Exposure(s) for the individual(s) listed in Section 6 of (Voluntary Consent) of this Attachment.

Emergency Exposure Authorized by: (EDO)

DATE/TIME: - /

NUCLEAR COMMON Page 15 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 3 Page 5 of 5 8.0 ACTUAL EDE DOSE RECEIVED Name Current Dose Total Badge # (Print) Yr. Dose Received Dose (Print) _(REM) (REM) (REM)

4. T

4. + +/-

4. 4. .4- f L 4. +

4. 4. + + 4. T 4 4. 4. 4.

1 4. r r

-4 + I-

+ 4* I.

.4 4 4. t.

4 .4 I. I

+ 4 4. 4.

.4- 4 4. 4.

4. .4 + 4.

Initial when entered into PRORAD: DATE/TIME: - - /

NUCLEAR COMMON Page 16 of 26 Rev. 07

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ATTACHMENT 4 Page 1 of I ONSITE PROTECTIVE ACTION GUIDELINES 1.0 RADIATION LEVELS Dose Rate (mR/hr) Location Action

> 100 Onsite Evacuation of all nonessential personnel.

Consider evacuation of other personnel.

Dose Rate (mR/hr) Location Action

> 100 Control Room Consider evacuation OSC within one hour, TSC and/or relocation as Control Point appropriate.

Dose Rate (mR/hr) Location Action

> 1000 Onsite Evacuation of all nonessential personnel Consider immediate evacuation of remaining personnel.

Dose Rate (mR/hr) Location Action

> 1000 Control Room Consider immediate OSC evacuation, and/or TSC relocation upwind of Control Point the plume.

2.0 RADIOIODINE If the Iodine-1 31 equivalent is calculated or measured in concentrations greater than or equal to 5.OE-7 uCi/cc, consider the use of Potassium Iodide for thyroid blocking. This section is to be applied to areas, in which personnel are working or are planning to work.

Refer to NC EP-EP.ZZ-0305(Q), Potassium Iodine (KI) Administration, for additional information.

NUCLEAR COMMON Page 17 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 5 Page 1 of 3 OPERATION OF THE VAX LA120 TERMINAL 1.0 METEOROLOGICAL DATA 1.1 Perform The Following to Obtain Current 15 Minute Average Meteorological Data:

1.1.1 DEPRESS the RETURN key. (USERNAME should be displayed).

1.1.2 TYPE MET and depress the RETURN key NOTE The most current meteorological data should be printed out followed by the Main Meteorological Menu. If no other keys are depressed, the current 15 minute average data will be printed out every 15 minutes 1.1.3 ENTER Option 1 (Display Current Meteorological Data) and depress the RETURN key to receive the current 15 meteorological data print out.

1.2 Perform The Following Steps to Obtain Archived Meteorological Data:

1.2.1 DEPRESS the RETURN key. (USERNAME should be displayed) 1.2.2 TYPE MET and depress the RETURN key. (The most current meteorological data should be printed out followed by the Main Meteorological Menu).

1.2.3 ENTER Option 2 (Display Meteorological Data From Data Base) and depress the RETURN key. (Current system Date and Time will be displayed).

1.2.4 IF this is the data you want, THEN depress the RETURN key. (Your option will be printed out).

1.2.5 IF you want data from an another date and time, THEN go to Step 1.2.6.

1.2.6 ENTER START DATE and TIME as shown below and depress the RETURN key. (For December 27, 1989 at 0130 enter 27-DEC-1 989 "depress the space bar once" and enter 01:30).

NUCLEAR COMMON Page 18 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 5 Page 2 of 3

ENTER "Y" if the information is correct.

ENTER "N" if the information is not correct and reenter it as shown in Step 1.2.6.

1.2.7 ENTER the END DATE and TIME as shown below and depress the RETURN key. (For December 28, 1989 at 0230 enter 28-DEC-1989 "depress the space bar once" and enter 02:30).

1.2.8 ENTER "Y" if the information is correct or "N" if the information is not correct and re-enter it as shown in Step 1.2.8.

2.0 RMS AND MET DATA (FOR HOPE CREEK ONLY) 2.1 Perform The Following Steps To Obtain Current Instantaneous RMS And MET Data:

2.1.1 DEPRESS the RETURN key. (USERNAME should be displayed).

2.1.2 TYPE EOF and depress the RETURN key. (A prompt should be displayed asking for PASSWORD).

2.1.3 TYPE EOFUSER and depress the RETURN key. (EOF Plant Menu should be displayed.)

2.1.4 SELECT Option 1 for Hope Creek.

2.1.5 DEPRESS the RETURN key. (The EOF Report Options Menu will be displayed).

2.1.6 ENTER Option 1 (Current RMS Status) and depress the RETURN key. (The most current instantaneous RMS and 15 minute MET data will be printed out.)

2.2 Perform The Following Steps To Obtain 15 Minute Average RMS Data:

2.2.1 DEPRESS the RETURN key. (USERNAME should be displayed).

2.2.2 TYPE EOF and depress the RETURN key. (A prompt should be displayed asking for PASSWORD).

2.2.3 TYPE EOFUSER and depress the RETURN key. (The EOF Plant Menu should be displayed).

NUCLEAR COMMON Page 19 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 5 PAGE 3 OF 3 2.2.4 SELECT Option I for Hope Creek.

2.2.5 DEPRESS the RETURN key. (The EOF Report Options Menu should be displayed).

2.2.6 SELECT and ENTER Option 6 (15 Minute Historical Data).

(Current system date and time should be displayed. A prompt should be displayed for start date and time) 2.2.7 DEPRESS the RETURN key for 15 minute average RMS and MET data. (Your selection will be printed).

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NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 6 Page 1 of 4 RMS QUICK REFERENCE 1.0 HOPE CREEK NOTE All ARM's in the Reactor Building have MAXIMUM RANGES of 1.OOE+04 mR/hr, except for the Inner Tip Room Monitor (9RX699). The Inner Tip Room Monitor's MAXIMUM RANGE is 1.00E+07 mR/hr.

DAPA A and DAPA B (9RX635 and 9RX636) are high range ARMs in the Drywell. DAPA "A" is approximately twice as high as DAPA B under normal operating conditions. During a LOCA in the Drywell the two monitors should start to trend closer together due to the atmospheric conditions in the Drywell affecting both monitors equally. Increases on both of these monitors while DAPA A's reading stays about twice of what DAPA B is reading, would be an indication of fuel damage.

Ranges: 1.OOE+00 to 1.OOE+08 R/hr.

Tip Room Inner ARM (9RX699) is located on 102' elevation of the Reactor Building inside the Tip Room. This monitor has the highest range of any ARM in the Reactor Building and could give an idea of what the dose rates in the Reactor Building are after the other ARMs peg out high.

Ranges: 1.OOE+00 to 1.OOE+07 mR/hr Main Steam Line A - D monitors (9RX509-512) are four ARMs located in the ceiling of the Main Steam Tunnel. Increases in these monitors would be an indication of fuel damage. These monitors could increase due to shine from the Reactor Building, after a radiological release.

Ranges: 1.OOE+00 to 1.OOE+06 mR/hr Safeguard Instrument Room Monitor (9RX704) is an ARM located on 77' elevation of the Reactor Building. An increase on this monitor when the reactor SCRAMs with fuel damage could be due to shine from the Torus.

Ranges: 1.OOE-01 to 1.OOE+04 mR/hr NUCLEAR COMMON Page 21 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 6 Page 2 of 4 FRVS Effluent monitor (9RX680) monitors what is going out the FRVS Plant Vent. Under normal operating conditions Reactor Building ventilation would vent through the South Plant Vent. Under accident conditions or when manually initiated, Reactor Building Ventilation isolates and the Reactor Building will vent through the FRVS. FRVS is always a ground release. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.00E+1 2 uCi/Sec (THIS IS A GROUND RELEASE AT ALL TIMES).

North Plant Vent Effluent (NPV) monitor (9RX590) monitors Offgas and the chemistry lab fume hoods. NPV could be a ground or elevated release depending on the time of year and wind speed. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.OOE+12 uCi/Sec (THIS COULD BE A GROUND, ELEVATED, OR SPLIT WAKE RELEASE. A SPLIT WAKE RELEASE IS NOT A TRUE GROUND OR ELEVATED RELEASE).

South Plant Vent Effluent (SPV) monitor (9RX580) monitors Service Radwaste Building, Turbine Building and the Reactor Building (if FRVS hasn't been initiated). Values >

1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.OOE+12 uCi/Sec (THIS COULD BE A GROUND, ELEVATED, OR SPLIT WAKE RELEASE. A SPLIT WAKE RELEASE IS NOT A TRUE GROUND OR ELEVATED RELEASE).

Hardened Torus Vent Effluent (HTV) monitor (9RX518) would be used to vent the Drywell to relieve pressure. The path it would take would be through the Torus and take advantage of the scrubbing properties of the Torus water. Control Room operators would have to open a valve to use this release path. Sampling from the PASS Torus Gas Space should be performed to provide information as to what is being released. Values >

1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 0.00E+00 to 2.09E+1 2 uCi/Sec (THIS ISA GROUND RELEASE AT ALL TIMES).

2.0 SALEM RMS (UNIT 1 AND 2)

R2 is an Area Radiation Monitor (ARM) located in Containment on the 130' elevation.

Ranges: 1 E-01 to 1 E+04 mR/hr.

R7 is an ARM located in Containment on the 100' elevation, adjacent to the Seal Table Room.

Ranges: 1E-01 to 1E+04 mR/hr.

R1 OA is an ARM located in Containment on the 100' elevation next to the personnel airlock.

Ranges: 1E-01 to 1E+04 mR/hr.

NUCLEAR COMMON Page 22 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 6 Page 3 of 4 R10B is an (ARM) located in Containment on the 130' elevation next to the personnel airlock.

Ranges: 1 E-01 to 1E+04 mR/hr.

R16 (SALEM UNIT 2 ONLY)Plant Vent Stack is located in the Plant Vent duct at 194' elevation and monitors what is going out the Plant Vent stack.

Ranges: 1E+01 to 1E+06 CPM R34 is an ARM located in the Mechanical Penetration across from the 100' elevation Containment personnel Airlock.

Ranges: 1E-01 to 1E+06 mR/hr.

R44A is a High Range or Accident Area Radiation Monitor (HARM) located in Containment on the 130' elevation close to the personnel airlock.

Ranges: 1 E+00 to 1E+07 R/hr.

R44B is a (HARM) located in Containment on the 100' elevation between the R10A and R7 ARMs.

Ranges: 1 E+00 to 1E+07 R/hr.

R47 is an ARM located in the 78' Electrical Penetration. The PASS lines are located in the overhead. The skid and PASS lines may be the source of any increase in this area. This Penetration has its own ventilation flow path and will vent directly into the atmosphere. There is a potential for an unmonitored release from this Penetration.

Ranges: 1E-01 to 1E+07 mR/hr NOTE

"* All Emergency Grab Samples (Noble Gas, Iodine and Particulate) should be taken from the R45 Skid located in the R45 Shed.

"* Only one of the following Effluent Monitors (R41A, R41B, R41C, R45B or R45C) readings should be used in MIDAS Manual Mode.

R41A is the Low Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1 E-07 to 1E-01 uCi/cc (THIS IS A GROUND RELEASE AT ALL TIMES).

NUCLEAR COMMON Page 23 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

ATTACHMENT 6 Page 4 of 4 R41B is the Mid Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1 E-04 to 1E-02 uCi/cC(THIS IS A GROUND RELEASE AT ALL TIMES).

R41C is the High Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1E-01 to 1 E+05 uCi/cc (THIS IS A GROUND RELEASE AT ALL TIMES).

R41D is the Effluent Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: OE+00 to 1E+13 uCi/Sec (The R41D values should not be used in MIDAS to perform manual dose assessment calculations) (THIS IS A GROUND RELEASE AT ALL TIMES).

R45B is the "Backup" Mid Range Noble Gas Monitor and is located in the R45 Shed behind the Fuel Handling Building. This monitor should not be used unless the R41 monitors are inoperable.

Ranges: 1 E-03 uCi/cc to 1 E+01 uCi/cc (THIS ISA GROUND RELEASE AT ALL TIMES).

R45C is the "Backup" High Range Noble Gas Monitors and is located in the R45 Shed behind the Fuel Handling Building. This monitor should not be used unless the R41 monitors are inoperable.

Ranges: 1E-01 uCi/cc to 1E+05 uCi/cc (THIS ISA GROUND RELEASE AT ALL TIMES).

NUCLEAR COMMON Page 24 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

FORM - 1 Page 1 of I HABITABILITY LOG DATE: / /

DOSE RATE CONTAMINATION TIME LOCATION (mR/hr) (CPM) INITIALS I i 4 1 t T 1 4 t t 4- 1- t -r

.1. + -r 4- + i 4 1 L I 1 t I t I t t T J 1- T IF other means are used to ensure habitability, THEN list:

NUCLEAR COMMON Page 25 of 26 Rev. 07

NC.EP-EP.ZZ-0304(Q)

FORM - 2 Page 1 of I INDIVIDUAL'S CURRENT YEARLY DOSE NAME BADGE NUMBER CURRENT YEARLY.

DOSE (mRem)*

NUCLEAR COMMON Page 26 of 26 Rev. 07

PSEG Internal Use Only PAGE 1 OF 1 PSEG NUCLEAR LLC SC.EP-EP.ZZ-0301 (Q) - REV. 04 SHIFT RADIATION PROTECTION TECHNICIAN RESPONSE USE CATEGORY: II REVISION

SUMMARY

1. This revision satisfies the requirement for a biennial review.

2. Revised Attachment 3 to remove the "2" before the R3 and R6A monitors and added a "1".

3. Clarified the location of the OSC emergency locker key box in Section 4.0 (Equipment Required).

4. Deleted the Unit 1 R16 monitor from Attachment 2 and specified in Attachment 4 that R16 monitor is for Unit 2 only, in accordance with DCP 80030824 (50.54q was performed for the deletion of this radiation monitor from Section 10 of the PSEG Nuclear Emergency Plan).

5. Deleted the Unit 1 R43 monitor from Attachment 2 and Attachment 3 in accordance with DCP 80027246 (50.54q was performed for the deletion of this radiation from Section 10 of the PSEG Nuclear Emergency Plan).

6. Revised who approves our Emergency Plan Implementing Procedures from Vice President Operations to Director Operations. This is in accordance with the latest revision (Revision

11) of Section'17 of the Emergency Plan.

7. Revised Manager - EP & IT to Emergency Preparedness Manager throughout the procedure.

IMPLEMENTATION DATE: / /- ?c Z" APPROVED:, -.... _-/ - _

Emergency Preparedness Manager Date APPROVED: .ll/oA __.

Director - Operations Date PQ; FP \

CO2TV0OL C077#

SC.EP-EP.ZZ-0301 (Q)

SHIFT RADIATION PROTECTION TECHNICIAN RESPONSE TABLE OF CONTENTS Section Title Page 1.0 P UR P O S E ................................................................................................ .. . 2 2 .0 P R E R E Q U IS IT E S ....................................................................................... . . 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure ... 2 3.0 PRECAUTIONS AND LIMITATIONS .......................................................... 2 3.1 Precaution and Limitations To Be Followed Prior To Implementing This P ro c e d u re ....................................................................................... .. . 2 4.0 EQUIPMENT REQUIRED ........................................................................... 2 5 .0 P R O C E D UR E ............................................................................................ .. .3 5.1 T he S R P T S hould ........................................................................... . . 3 5.2 When the TSC is Activated, Perform the Following ................................ 3 6 .0 R E C O R D S ........................................................................................................ 3 7 .0 R E F E R E NC E S ........................................................................................... . . 4 7 .1 R efe re n ce s ....................................................................................... . . 4 7 .2 C ro ss R efe re nce s ............................................................................. . .4 ATTACHMENTS ATTACHMENT 1 - Shift Radiation Protection Technician Checklist .................................. 5 ATTACHMENT 2 - Radiological Assessment Data Sheet - Unit 1 ....................................... 10 ATTACHMENT 3 - Radiological Assessment Data Sheet - Unit 2 ....................................... 12 ATTACHMENT 4 - RMS Quick Reference ........................................................................... 14 ATTACHMENT 5 - Operating Instructions for the R - 45 Control Terminal .......................... 16 ATTACHMENT 6 - Operating Instructions for the Salem Unit 2 RMS Computer and The RM 2300 (R41 Monitor Values) .............................................................. 25 ATTACHMENT 7 - Salem Radiological Based Protective Action Recommendations and Recommended Protective Actions Worksheet ...................................... 28 ATTACHMENT 8 - Onsite Protective Action Guidelines ...................................................... 30 ATTACHMENT 9 - Contamination Control Guidance .......................................................... 31 ATTACHMENT 10 - Steam Generator Tube Leak/Rupture Guidelines ........................... 32 FORMS F o rm - 1 Ha b ita b ility Lo g ......................................................................................... . . 35 Salem Page 1 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q) 1.0 PURPOSE To outline and describe the Shift Radiation Protection Technician's (SRPT) duties during a declared emergency 2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure Implement this procedure at:

"* The discretion of the Operations Superintendent (OS) or Radiation Protection Supervision.

"* Upon a declaration of an Unusual Event or greater emergency classification.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure 3.1.1 It is recommended that initials be used in the place keeping sign-offs, instead of checkmarks, if more than one person may implement this procedure.

3.1.2 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.

3.1.3 The OS may change any priority concerning the SRPT's duties, as deemed necessary.

3.1.4 Steps listed in this procedure may be performed in the order deemed appropriate for the emergency situations. Only steps applicable to the specific emergency need be performed.

4.0 EQUIPMENT REQUIRED As provided at the Control Point and Control Room. (The key to the OSC emergency locker is located in the red key box at work control outside the Control Room)

Salem Page 2 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q) 5.0 PROCEDURE 5.1 The SRPT Should:

START completing Attachment 1, Shift Radiation Protection Technician(s) Checklist.

5.2 When the TSC is Activated Perform the Following:

5.2.1 COMPLETE the turnover of Dose Assessment/Station Status Checklist duties to the Radiation Protection Supervisor - Offsite or the Radiological Assessment Coordinator.

NOTE A complete listing of RMS monitors can be found in the RMS Manual (Unit 1 or 2).

5.2.2 IMPLEMENT Attachment 4, RMS Quick Reference, for an abbreviated list of RMS monitors and the R44 preplanned alternative methodology.

5.2.3 DOCUMENT monitors in Warning 'W' or Alarm "A" on Attachment 2, Radiological Assessment Data Sheet - Unit 1, or Attachment 3, Radiological Assessment Data Sheet - Unit 2.

5.2.4 DOCUMENT monitor values as instructed by the OS or Radiation Protection Supervision on Attachment 2, Radiological Assessment Data Sheet - Unit 1, or Attachment 3, Radiological Assessment Data Sheet - Unit 2.

5.2.5 TRANSMIT completed Attachment 2 or Attachment 3 via the FAX using the Group "C" key every 15 to 20 minutes or in the opinion of the SRPT, conditions warrant it.

5.2.6 PROVIDE a completed copy of Attachment 2 or 3 to the Radiation Protection Supervisor - Exposure Control (RPS-EXP) located in the OSC, every 15 to 20 minutes, or in the opinion of the SRPT, conditions warrant it.

6.0 RECORDS Return completed procedure and any information or data thought to be pertinent by the SRPT, to the Emergency Preparedness Manager.

Salem Page 3 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

7.0 REFERENCES

7.1 References PSEG Nuclear Emergency Plan LLC.

7.2 Cross References 7.2.1 NC.EP-EP.ZZ-0310(Q), Radiation Protection Supervisor - Offsite And Field Monitoring Team Response.

7.2.2 Salem Offsite Dose Calculation Manual (ODCM).

Salem Page 4 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 1 Page 1 of 5 SHIFT RADIATION PROTECTION TECHNICIAN CHECKLIST 1.0 SRPT INITIAL ACTIONS NOTE The order that the steps are followed in this attachment may be performed out of sequence, if the SRPT believes the emergency warrants it.

1.1 Perform the Following:

1.1.1 REPORT to the CR when an emergency is declared to receive a briefing from the OS.

1.1.2 PROVIDE a briefing to the OS, which should include the following Information:

"* Habitability of the Control Point and Control Room.

"* Any unusual dose rates observed on the way to the CR.

NOTE

" On a back shift, during a non-outage situation, there should be 2 Rad Pro Techs and 1 Chemistry Tech available at all times at Hope Creek.

" The Hope Creek Control Point may be contacted at extension 3741.

The staffing of the Salem Radiation Protection and Chemistry personnel.

1.1.3 REQUEST the status of the MET Tower's operability.

A. IF the MET Tower is not operational, THEN refer to step 1.1.9.

1.1.4 OBTAIN the identity of Communicator 2 (Name)

Salem Page 5 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 1 Page 2 of 5 1.1.5 TURN on the AMS located in the back of Unit 1 & Unit 2 CR.

1.1.6 REQUEST that the Emergency Vehicle from the Hope Creek Control Point (x3741) be delivered to the Unit 2 Steam Mixing Bottle Area or alternate location, depending on radiological conditions, and the keys delivered to the Salem CP when any of the following occur:

"* Upon an Alert declaration or higher.

"* When an Alert declaration or higher is about to be made.

"* If on/offsite monitoring is deemed necessary by the OS or Radiation Protection Supervision.

NOTE

" The SRPT should be generating page two of the Station Status Checklist (SSCL) for both Salem Unit One and Unit Two, for Common Site Events. The Hope Creek SRPT will be generating a SSCL for Hope Creek under these conditions.

" A blank SSCL, page 2, may be obtained from Communicator Number 2, if thought necessary.

1.1.7 IMPLEMENT NC.EP-EP.ZZ-0309(Q), Dose Assessment, to perform dose assessment and generate a SSCL pg. 2 every 30 minutes.

1.1.8 PERFORM the following steps, if automatic data acquisition MIDAS and/or the MET Computer is not operational:

" REFER to appropriate attachment, (Attachment 2, Radiological Assessment Data Sheet - Unit 1 or Attachment 3, Radiological Assessment Data Sheet - Unit 2).

" COMPLETE monitors with an

next to them, monitors in alarm, and the MET Data section listed on Attachments 2 and 3 every 15 minutes for the affected Unit.

Salem Page 6 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 1 Page 3 of 5 1.1.9 OBTAIN the MET data from the following, if the MET Computer is not operational:

"* Unit One Control Room

"* Hope Creek Control Point (extension 3741)

"* Hope Creek Control Room (extension 3059)

"* National Weather Service at 609-261-6604 or 609- 261- 6603.

1.1.10 IMPLEMENT NC.EP-EP.ZZ-0309(Q)/EPIP 309S, Dose Assessment, for instructions on performing dose assessment in the manual mode.

1.1.11 INPUT the appropriate effluent monitor and MET values manually into MIDAS to perform dose assessment in the manual mode.

NOTE Contact an Emergency Preparedness representative at x1 571 or 1157 concerning any MIDAS problems.

1.1.12 IF the MIDAS computer located in the CR is not operational, THEN use one of the MIDAS computers listed below:

"* Salem TSC

"* Hope Creek Control Point

"* Hope CreekTSC 1.1.13 DETERMINE appropriate PAR, if any, utilizing the most current SSCL and Attachment 7 Salem Radiological Based PARs and PAR Worksheet.

1.1.14 REVIEW the SSCL and the Radiological Based PAR with the OS Utilize Attachment 7 as needed to explain the PAR provided.

Salemn Page 7 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 1 Page 4 of 5 1.1.15 PROVIDE the signed SSCL to Communicator Number 2, or leave it with the OS, if he requests to keep it.

1.1.16 PERFORM habitability checks in the CR, and OSC if activated, every thirty minutes and record results on Form - 1, Habitability Log, unless told otherwise by the Operations Superintendent or the Rad Pro Supervisor-Exposure Control.

1.1.17 MAKE appropriate Onsite PAGs to the OS or RAC for Onsite locations using Attachment 8, Onsite Protective Action Guidelines.

1.1.18 ESTABLISH Contamination Controls (no eating, no drinking, no smoking, proper postings, setting up step off pads and friskers) when any of the following have occurred.

NOTE Noble Gas (NG) Federal Limits/Offsite Dose Calculation Manual (ODCM) Limits are 2.42E+05 uCi/second.

"* A radiological release > NG Federal Limits/ODCM Limits is in progress.

"* The potential of a NG radiological release Federal Limits/

ODCM Limits is thought to be high.

"* Normal RCA boundaries have been breached.

"* At the RAC's discretion.

NOTE A RM-14 or equivalent count rate meter should be positioned next to all newly placed contamination control step off pads.

Salem Page 8 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 1 Page 5 of 5 1.1.19 IMPLEMENT Attachment 9, Contamination Control Guidance, for how to limit access to certain areas and where to position step off pads.

1.1.20 NOTIFY the RAC and RPS-EXP of changing radiological conditions as determined from step 1.1.18.

1.1.21 ASSIST the OS with completion of Page 2 of the NRC Data Sheet, if asked to.

1.1.22 IMPLEMENT Attachment 10, Steam Generator Tube Leak/Rupture Guidelines, when thought appropriate.

1.1.23 IMPLEMENT Section 5.2 of this procedure, and follow appropriate steps, when the TSC is activated.

TURNOVER Given By: __ _ _ _ _ _ _ _ _ _ _ _ _ _

Date/Time:

TURNOVER Received By: Date/Time:-

Salem Page 9 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 2 Page 1 of 2 RADIOLOGICAL ASSESSMENT DATA SHEET - UNIT I Date :_Time:

Meteorological Data Back up MET data may be obtained by calling Hope Creek Control Point at 3741.

National Weather Service at (609) 261-6604 or (609) 261-6602 Wind Speed mph 33' mph 300' Wind Speed degrees 300' Wind Direction FROM degrees 33' Wind Direction FROM 0C 300-33' or Delta "T" 150-33' (use 300-33 if operational)

(circleone)

Plant Vent flow rate (1.25E + 05 if unknown) cfm Plant Vent and Containment Monitors Monitor Low High Number Name Value Units Warning Alarm Range Range IRIIA CTMT Particulate CPM W A 1E +01 1E +06 IR12A CTMT Noble Gas CPM W A 1E +01 1E +06 IR12B CTMT Iodine CPM W A 1E +01 1E +06

IR41A Low Range PV NG ýtCi/cc N/A N/A IE-08 1E-01

IR41B Mid Range PV NG p.Ci/cc N/A N/A 1E-04 1E+02

IR41C High Range PV NG p[Ci/cc N/A N/A 1E-01 IE+05 IR41D NG Effluent _ _ Ci/sec W A IE+00 IE+13 1R2 130 CTMT ARM mR/hr W A IE-01 IE+04 IRIOA I00' CTMT Persnl Hatch mR/hr W A IE-01 1E+04 iRIOB 130' CTMT Persnl Hatch mR/hr W A IE-01 1E+04 1R7 Seal Table. GA mR/hr W A IE-01 1E+04

-1R44A CTMT High Range R/hr W A IE+00 1E+07

+ IR44B CTMT High Range R/hr W A lE+00 1E+07

"* 1R45B Mid Range PV NG pCi/cc W A 1E-03 IE+01

"* 1R45C High Range PV NG _ _ Ci/cc W A 1E-01 1E+05 1R45D PV Filter Monitor CPM W A 1E+00 1E+06 1R53 MSL Process (N 16) CPM W A IE+01 1E+06

"* Complete every 15 minutes

+ Record Value if Onscale.

Salem Page 10 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 2 Page 2 of 2 fl at Time:

Monitor Low High Number Name Value Units Warning Alarm Range Range IRlA CRI General Area (GA) mR/hr W A IE-01 1E+04 IRIB Control Room Intake Duct CPM W A lE+01 IE+06 1R3 Chem Lab. GA mR/hr W A IE-01 lE+04 1R4 Charging Pump, GA mRlhr W A IE-01 IE+04 1R5 Spent Fuel Pool mR/hr W A IE-01 1E+04 1R6A Primary Sample Lab mR/hr W A IE-01 1E+04 1R9 New Fuel Storage. GA mR/hr W A IE-01 lE+04 IR13A Fan Coil Cooling CPM W A 1E+01 1E+06 IR13B Fan Coil Cooling CPM W A 1E+01 1E+06 IR13C Fan Coil Cooling CPM W A 1E+01 1E+06 IR13D Fan Coil Cooling CPM W A IE+01 1E+06 IR13E Fan Coil Cooling CPM W A 1E+01 IE+06 1R15 Condenser Air Ejector CPM W A 1E+01 1E+06 IR17A Component Cooling H 2 0 CPM W A 1E--+O 1E+06 IR17B Component Cooling H 2 0 CPM W A 1E+01 1E+06 IR18 Liquid Waste Release CPM W A 1E+01 IE+06 IR19A #11 S/G Blowdown CPM W A 1E+00 1E+06 IRI9B #12 S/G Blowdown CPM W A 1E+00 IE+06 IR19C #13 S/G Blowdown CPM W A 1E+00 1E+06 IR19D #14 S/G Blowdown CPM W A 1E+00 1E+06 1R20B Chemistr. Count Room mR/hr W A IE-01 1E+04 1R26 Rx Coolant Filter mR/hr W A IE-02 IE+03 IR31A Letdown HX Failed Fuel CPM W A 1E+01 1E+06 1R32A Fuel Handling Crane mR/hr W A IE-01 IE+06 1R34 North Pipe Pen mR/hr W A 1E+01 1E+06 1R36 Evap and Feed H 2 0 CPM W A 1E+01 1E+06 1R40 Condensate Filter mR/hr W A IE-01 1E+04 1R46 MSL Process mR/hr W A IE+00 IE+04 1R47 Electrical Pen High Range mR/hr W A IE-01 IE+07 2R52 PASS Room R/hr W A 1E+00 IE+04 Salem Page 11 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 3 Page 1 of 2 RADIOLOGICAL ASSESSMENT DATA SHEET - UNIT 2 Time:_

Date :

Meteorological Data Back up MET data may be obtained by' calling Hope Creek Control Point at 3741.

National Weather Service at (609) 261-6604 or (609) 261-6602 mph 33' Wind Speed 300' mph Wind Speed 300' degrees Wind Direction FROM 33' degrees Wind Direction FROM 0C 300-33' or Delta "T" 150-33' (use 300-33 if operational) (circle one)

Plant Vent flow rate (1.25E + 05 if unknovvn) cfm Plant Vent and Containment Monitors Monitor Low High Number Name Value Units Warning Alarm Range Range 2R1IA CTMT Particulate CPM W A 1E +01 1E +06 2R12A CTMTNG CPM W A IE +01 1E +06 2R12B CTMT Iodine CPM W A 1E +01 IE +06

2R41A Low Range PV NG 1ICi/cc N/A N/A 1E-08 1E-01

2R41B Mid Range PV NG p4Ci/cc N/A N/A 1E-04 IE+02

"*2R41C High Range PV NG ptCi/cc N/A N/A IE-01 IE+05 2R41D NG Effluent 4Ci/se W A lE+00 1E+13

"*2R16 PV Gross Effluent CPM W A IE+01 1E +06 2R2 130 CTMT ARM mR/hr W A IE-01 1E+04 2R0OA 100* CTMT Persnl Hatch mR/hr W A IE-01 IE+04 2R10B 130' CTMT Persnl Hatch mR/hr W A IE-01 1E+04 2R7 Seal Table, GA mR/hr W A IE-01 IE+04

+2R44A CTMT High Range R/hr W A 1E+00 1E+07

+2R44B CTMT High Range R/hr W A 1E+00 I E+07

2R45B Backup Mid Range PV NG .tCi/cc W A 1E-03 1E+01

"*2R45C Backup High Range PV NG _ _ Ci/cc W A 1E-01 IE+05 2R45D PV Filter Monitor CPM VW A 1E+00 IE+06 MSL Process (N 16) CPM W A 1E+01 1E+06 2R53_

Complete every 15 minutes

+ Record Value if Onscale Page 12 of 35 Rev. 04 Salem

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 3 Page 2 of 2 fl OtP Time:

Monitor Low High Number Name Value Units Warning Alarm Range Range 2R1A CR, General Area (GA) mR/hr W A IE-01 IE+04 2R1B CR Intake Duct CPM W A 1E+01 1E+06 1R3 Chem Lab. GA mR/hr W A IE-01 1E+04 2R4 Charging Pump, GA mR/hr W A IE-01 IE+04 2R5 Spent Fuel Pool mR/hr W A IE-01 1E+04 1R6A Primarv Sample Lab mR/hr W A IE-01 IE+04 2R9 New Fuel Storage. GA mR/hr W A IE-01 1E+04 2R13A Fan Coil Cooling CPM W A 1E+01 1E+06 2R13B Fan Coil Cooling CPM W A IE+01 IE+06 2R13C Fan Coil Cooling CPM W A 1E+01 IE+06 2R15 Condenser Air Ejector CPM W A 1E+01 1E+06 2R17A Component Cooling H 2 0 CPM W A 1E+01 1E+06 2R17B Component Cooling H 2 0 CPM W A 1E--01 E+06 2R18 Liquid Waste Release CPM W A 1E+01 1E+06 2R19A #21 S/G Blowdown CPM W A 1E+00 IE+06 2R19B #22 S/G Blowdown CPM W A IE+00 IE+06 2R19C #23 S/G Blowdown CPM W A IE+00 1E+06 2R19D #24 S/G Blowdown CPM W A 1E+00 1E+06 IR20B Chem Count Room (Unit 1) mR/hr W A IE-01 IE+04 2R26 Rx Coolant Filter mR/hr W A IE-01 1E+06 2R31 Letdown HX Failed Fuel CPM W A 1E+01 I E+06 2R32A Fuel Handling Crane mR/hr W A IE-01 1E+04 2R34 South Pipe Pen mR/hr W A IE+O1 1E+06 2R36 Evap and Feed H 2 0 CPM W A IE+00 1IE+06 2R40 Condensate Filter mR/hr W A IE-O1 IE+04 2R46 MSL Process MR/hr W A IE+00 1E+04 2R47 Electrical Pen High Range mR/hr W A IE-01 1E+07 2R52 PASS Room R/hr W A 1E+00 1E+04 2R53 N16 Main Steamlinc Nion CPM W A 1E+01 1E+06 Salem Page 13 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 4 Page 1 of 2 RMS QUICK REFERENCE Salem RMS (Unit 1 and 2)

R2 is an Area Radiation Monitor (ARM) located in Containment on the 130' elevation.

Ranges: 1 E-01 to 1E+04 mR/hr.

R7 is an ARM located in Containment on the 100' elevation, adjacent to the Seal Table Room.

Ranges: 1E-01 to 1E+04 mR/hr.

RIOA is an ARM located in Containment on the 100' elevation next to the personnel airlock.

Ranges: 1 E-01 to 1 E+04 mR/hr.

R10B is an (ARM) located in Containment on the 130' elevation next to the personnel airlock.

Ranges: 1E-01 to 1E+04 mR/hr.

R16 (UNIT 2 ONLY) Plant Vent Stack is located in the Plant Vent duct at 194' elevation and monitors what is going out the Plant Vent stack.

Ranges: 1E+01 to 1E+06 CPM R34 is an ARM located in the Mechanical Penetration across from the 100' elevation Containment personnel Airlock.

Ranges: 1E-01 to 1E+06 mR/hr.

R44A is a High Range or Accident Area Radiation Monitor (HARM) located in Containment on the 130' elevation close to the personnel airlock.

Ranges: 1E+00 to 1E+07 R/hr.

R44B is a (HARM) located in Containment on the 100' elevation between the R1OA and R7 ARMs.

Ranges: 1 E+00 to 1E+07 R/hr.

R47 is an ARM located in the 78' Electrical Penetration. The PASS lines are located in the overhead. The skid and PASS lines may be the source of any increase in this area.

This Penetration has its own ventilation flow path and will vent directly into the atmosphere. There is a potential for an unmonitored release from this Penetration.

Ranges: 1E-01 to 1E+07 mR/hr Salem Page 14 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACH MENT 4 Page 2 of 2 NOTE

"* All emergency Grab Samples (Noble Gas, Iodine and Particulate) should be taken from the R45 Skid located in the R45 Shed.

"* Only one of the following Effluent Monitors (R41 A, R41 B, R41 C, R45B or R45C) readings should be used in MIDAS Manual Mode. Refer below for the ranges of the monitors. Refer to NC.EP-EP.ZZ-0309(Q), Section 5.4 for more clarification concerning which plant vent effluent monitor value to use for performing dose assessment.

R41A is the Low Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1 E-08 to 1 E-01 uCi/cc R41B is the Mid Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1 E-04 to 1 E-02 uCi/cc R41C is the High Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1E-01 to 1E+05 uCi/cc R41 D is the Effluent Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: OE+00 to 1E+13 uCi/Sec (The R41 D should not be used in MIDAS to perform manual dose assessment calculations)

R45B is the "Backup" Mid Range Noble Gas Monitor and is located in the R45 Shed behind the Fuel Handling Building. This monitor should not be used unless the R41 monitors are inoperable.

Ranges: 1E-03 uCi/cc to 1 E+01 uCi/cc R45C is the "Backup" High Range Noble Gas Monitors and is located in the R45 Shed behind the Fuel Handling Building. This monitor should not be used unless the R41 monitors are inoperable.

Ranges: 1 E-01 uCi/cc to 1 E+05 uCi/cc Salem Page 15 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 5 Page 1 of 9 OPERATING INSTRUCTIONS FOR THE R-45 CONTROL TERMINAL 1.0 INFORMATION CONCERNING THE R-45 CONTROL TERMINAL

"* On the front panel of the R-45 Console (see DETAIL A of Figure 1) there are six System Status Annunciators. Below is a brief explanation of each.

"* The NORMAL (green) light will be lit if any channel in the system is NORMAL or ALARM OFF.

" All lights will be off if none of the channels in the system have been initialized.

" The MAINTENANCE (white) light will be lit if any channel in the system is in "Calibrate", "Maintenance", or "Check Source" status; "Standby" or "Flush" mode; or if any field unit is in "Local Control" (at the shed).

" The FAIL (yellow) light will be lit if any channel in the system is in "Fail External", "Fail High", or "Fail Low" status. This light will be lit if any field unit is determined to have lost AC power or to have failed via the communications programs.

" The TREND (yellow) light will be lit if any channel in the system has determines a trend alarm rate.

"* The ALERT (yellow) light will be lit if any channel in the system has determined an alert alarm level.

" The HIGH ALARM (red) light is lit when any channel in the system is in "High Alarm" or "Flow Alarm" status. On a new alarm condition, the light will be flashing until the switch (button) is depressed, which causes the light to stay on but silences the audible alarm.

" The AUDIBLE ALARM sounds at any change of status on any channel in the system.

This annunciation is an audible beep of approximately 1 second duration. Also, it sounds when the system is first started (or restarted) and when a high alarm occurs.

The alarm will sound until the HIGH ALARM light is depressed, thus acknowledging the condition.

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ATTACHMENT 5 Page 2 of 9

"* While entering commands onto the keyboards and after the operator finishes, information is displayed on the digital data display located above the keyboards (see Figure 1). If after approximately 15 seconds the operator does not touch the keyboards, the system returns to the ready mode (time and date are the only items displayed) and the operator may begin again.

" Information is obtained from the Control Terminal by entering commands on the keyboards. There are two keyboards: the Instruction Pad, and the Numeric Pad (see last page of this Attachment for diagram).

" The RUB OUT key functions like the backspace key on a computer keyboard, and if the operator makes an entry error he can correct it by pressing this key prior to pressing the enter key.

" Depress the up or down arrow key to see the information displayed on the digital readout.

"* Depress the keys in the following order: PRINT, FILE, ENTER to printout the information.

"* If the operator recalls a Historical Data File (10 MIN, HOUR, or DAY), there are additional options other than just looking at and/or printing the data. The operator can depress the DOWN ARROW KEY and then the ENTER KEY after the desired function appears on the digital display. The following is a brief explanation of each.

"* INTERPRETED -removes all abnormal data points and replaces them with points interpolated/extrapolated from the remaining "normal" data. If there is not enough data for this, then "INSUFFICIENT DATA" will appear in the display screen, meaning you cannot obtain this function.

"* INTEGRATED - is a summation beginning with the oldest data point.

"* AVERAGED - a single value will be displayed which is the mathematical average of the data over the time period of the file

"* RATE OF CHANGE - the increase over the two adjacent intervals, standardized to a "per hour" rate

"* RELEASE RATE - allows calculation of a release rate (uCi/min): the flow rate must be entered using the Numeric Pad in cc/min.

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ATTACHMENT 5 Page 3 of 9 2.0 OPERATING INSTRUCTIONS 2.1 Perform the Followina to Operate the R-45 Control Terminal.

NOTE

" The operator can obtain data by performing the steps listed below. If the operator has any problems or the monitor(s) are inoperable/failed, then contact the OS and/or I&C to fix or assist in fixing the problem.

" If after approximately 15 seconds the operator does not touch the keyboards, the system returns to the ready mode (time and date are the only items displayed) and the operator may begin again.

2.1.1 OBTAIN the R45 Control Key from the Control Room Operator, OS or l & C.

2.1.2 INSERT the key into the "Command Enable" slot and turn clockwise.

NOTE The data received from the SA-16 (Particulate and Iodine Channel) includes events from fission gas in the sample collector. The SA-16 radioiodine data is valid only when the "FLUSH" has been turned on. While the system is in "FLUSH" Mode, information can be obtained on the SA-16 channel. During this period the noble gas channels are not sampling plant vent flow and the data coming from them is NOT valid.

The "FLUSH"mode should be used only for the time period required to obtain radioiodine data from the SA-16 detector.

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ATTACHMENT 5 Page 4 of 9 2.1.3 DEPRESS the following keys, to enter the Flush Mode:

A. FLUSH B. ON C. 1 for Unit 1 D. 2 for Unit 2 E. ENTER 2.1.4 Leave the Flush Mode by depressing the following keys:

A. FLUSH B. OFF C. 1 for Unit 1 D. 2 for Unit 2 E. ENTER 2.1.5 DEPRESS the PRINT, ENTER keys to obtain the current status of all monitors/channels in a hard copy printout.

NOTE The following Channel Numbers represent these specific monitors.

CHANNEL NUMBER MONITOR REPRESENTED BY THE NUMBER 1 R45D (SA-16) Particulate and Iodine 2 R45A (SA-1 5) Noble Gas Background Subtract 3 R45C (SA-15) High Range Noble Gas 4 R45B (SA-14) Medium Range Noble Gas 2.1.6 DEPRESS the following keys. to obtain the current reading for a specific channel on the readout digital display:

A. DATA B. 1 for Unit 1 Salem Page 19 of 35 Rev. 04

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ATTACHMENT 5 Page 5 of 9 C. 2 for UNIT2 D. DOWN ARROW E. CHANNEL NUMBER F. ENTER G. DOWN ARROW Example:

DATA, 1, DOWN ARROW, 3, ENTER, DOWN ARROW. This will display current data for R45C, UNIT 1 2.1.7 DEPRESS the following keys, to obtain a printout of the above data:

A. PRINT B. FILE C. ENTER 2.1.8 DEPRESS the following keys, to obtain "10 MINUTE HISTORICAL DATA" for a specific channel that is displayed on the digital readout display. Choose only one type of historical data at a time.

A. HIST 10 MIN B. 1 for Unit 1 C. 2 for Unit 2 D. DOWN ARROW E. CHANNEL#

F. ENTER G. UP ARROW 2.1.9 DEPRESS the following keys, to obtain "HOUR HISTORICAL DATA" for a specific channel that is displayed on the digital readout display. Choose only one type of historical data at a time.

A. HIST HOUR B. 1 for Unit 1 C. 2 for Unit 2 D. DOWN ARROW Salem Page 20 of 35 Rev. 04

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ATTACHMENT 5 Page 6 of 9 E. CHANNEL#

F. ENTER G. UP ARROW 2.1.10 DEPRESS the following keys, to obtain "DAY HISTORICAL DATA" for a specific channel that is displayed on the digital readout display. Choose only one type of historical data at a time.

A. HIST DAY B. 1 for Unit 1 C. 2 for Unit 2 D. DOWN ARROW E. CHANNEL#

F. ENTER G. UP ARROW Example:

HIST HOUR, 2, DOWN ARROW, 4, ENTER, UP ARROW. This will display the 24 most recent averages for channel R45B on Unit 2 2.1.11 DEPRESS the following keys, to obtain a printout of the historical file specified:

A. PRINT B. FILE C. ENTER 3.0 ADDITIONAL KEYBOARD OPERATIONS 3.1 Perform the Following Steps to Silence/Clear Alarms, Turn On/Off Pump, or Expose a Check Source 3.1.1 OBTAIN the R45 key from I & C or the OS.

3.1.2 INSERT the key into the"Command Enable" slot and turn the key clockwise.

3.1.3 DEPRESS the following, to silence an alarm on a specified channel and unit:

A. ALM ACK Salem Page 21 of 35 Rev. 04

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ATTACHMENT 5 Page 7 of 9 B. 1 for Unit 1 C. 2 for Unit 2 D. DOWN ARROW E. CHANNEL NUMBER F. ENTER 3.1.4 DEPRESS the following keys, to clear high alarms for a specified channel and unit:

A. ALM CLR B. 1 for Unit 1 C. 2 for Unit 2 D. DOWN ARROW E. CHANNEL NUMBER F. ENTER 3.1.5 DEPRESS the following keys, to turn the 6 Ipm pump on or off:

A. PUMP B. ON or OFF C. 1 for Unit 1 D. 2for Unit 2 E. ENTER 3.1.6 DEPRESS the following keys, to expose the check source to a specified detector/channel:

A. CK SRC B. 1 for Unit 1 C. 2 for Unit 2 Salem Page 22 of 35 Rev. 04

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ATTACHMENT 5 Page 8 of 9 D. DOWN ARROW E. CHANNEL # (3 or 4)

F. ENTER 3.1.7 DEPRESS the following keys, to disable/re-enable the alarm function of specified channel and Unit:

A. ALM B. OFF or ON C. I for Unit 1 D. 2 for Unit 2 E. DOWN ARROW F. CHANNEL#

G. ENTER 3.1.8 DEPRESS the following keys, with the "Command" enable turned off and the key removed, to display the operational parameters of a specified channel and Unit:

A. FILE B. 1 for Unit I C. 2 for Unit 2 D. DOWN ARROW E. CHANNEL#

F. ENTER Salem Page 23 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 5 Page 9 of 9 PUSH TO ACKNOWLEDGE

-AUDIBLE ALARM HIST HIST HIST HIST MIN 10 HOUR DAY MIN DATA CK ALM ALM SRC ACK CLR FILE FILT FLUSH ALM STEP PRINT OFF PUMP STND ON BY INSTRUCTION PAD DETAIL A (SYSTEM ANNUNCIATOR PANEL (DRAWER PULLS OUT TO EXPOSE DETAIL B)

ENTER 7 8 9 EDIT 4 5 6 1 2 3 RUB 0 OUT NUMERIC PAD DETAIL C TYPICAL KEYBOARD DETAIL B (SYSTEM CONTROLLER PANEL)

Salem Page 24 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 6 Page 1 of 3 OPERATING INSTRUCTIONS FOR THE SALEM UNIT 2 RMS COMPUTER AND THE RM 2300 (R41 MONITOR VALUES)

NOTE

" This attachment provides guidance to allow access to the RMS computer for Unit 2. The main display indicates status (alarm, warning, no scan etc).

" Check the RMS computer time in the upper right hand corner of the screen with the Control Room clock. If the time is approximately correct and the seconds are updating, the data will be current. If the time/date is "frozen",

current data is not available. I&C RMS supervisor should be contacted. The time/date that appears should be the time the system malfunctioned.

" When obtaining RMS data without the computer, use RP1 panel & rack room strip charts.

1.0 OPERATING INSTRUCTIONS FOR THE SALEM UNIT 2 RMS COMPUTER 1.1 Perform the Following to Operate the Unit 2 RMS Computer 1.1.1 DEPRESS the following keys, to access all of the RMS monitor values:

A. Enable and Plant Location simultaneously B. "E" for all monitors C. <CR>

NOTE Any monitor in warning or alarm must be rechecked by strip chart integration in the rack room, behind the Control Room. Unit 2 strip chart recorders are limited, so data history must be checked by 15 minute averages on the computer.

1.1.2 PERFORM the following, for fifteen minute average data:

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SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 6 Page 2 of 3 A. DEPRESS the ENABLE & BARGRAPH keys simultaneously.

The bottom line on the screen will ask hourly or 15 minute average.

B. DEPRESS M & <CR> keys. Computer will then tell you to enter channel.

C. ENTER the monitor channel you wish to see (i.e."C2R16").

D. DEPRESS the <CR> key. You will be asked to enter scale.

NOTE Fifteen Minute averages begin and end on the quarter hour. Data is located to the left of the appropriate entry. Do not use "latest" data line as it is a 30 second average.

E. DEPRESS the <CR> key and the scale will be automatically adjusted & "auto range on" will be displayed. This mode will provide the four latest 15 minute averages only. The top entry is the oldest data, the bottom entry is the current 15 minute average data.

F. IF other 15 minute averages are needed for other monitor channels while in bar graph mode, THEN enter channel number ( i.e. "C2R16").

G. DEPRESS the <CR> key. Data/status will be provided.

2.0 OPERATION OF THE RM 2300 (R41 MONITORS)

Note The RM2300 computer is the controller for obtaining historical data for the R41 channels.

The RM2300 computer is in the rear rack room on U/1 on RACK 136. The computer for U/2 is in the front, on panel 2RP1. The upper left hand corner of the display has a tag that reads; "Sorrento Electronics".

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ATTACHMENT 6 Page 3 of 3 CAUTION Permission MUST be obtained from the Operations Superintendent or Control Room Operator prior to operating the RM 2300.

2.1 PERFORM the following to obtain 1 minute, 10 minute, hourly, or daily readings.

2.1.1 PRESS CURRENT ACTIVITY.

2.1.2 PRESS SELECT.

2.1.3 IF "MENUS" is not highlighted, THEN RETURN to Step 2.1.1.

2.1.4 VERIFY "MENUS" is highlighted 2.1.5 PRESS SELECT.

2.1.6 PRESS DOWN "V" ARROW until "Display/Clear History" is highlighted 2.1.7 PRESS SELECT. "DISPLAY HISTORY" should be highlighted.

2.1.8 PRESS SELECT.

2.1.9 USE DOWN "V" A-ROW to highlight 1 minute, 10 minute, hourly, or daily averages.

2.1.10 PRESS SELECT. Channel ID is located in the upper left hand corner of screen (Channel 1 = R41A, Channel 2 = R41B, Channel 3 = R41C, and Channel 4 = R41D) 2.1.11 USE PREVIOUS or NEXT push buttons to change channel to desired channel. These bottoms are located on right side of panel, under Channel Select. The most current reading is at the top of the left side column.

2.1.12 PRESS CURRENT ACTIVITY push button to return to the main screen.

Salem Page 27 of 35 Rev. 04

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ATTACHMENT 7 Page 1 OF 2 SALEM RADIOLOGICALLY BASED PROTECTIVE ACTION RECOMMENDATION FLOWCHART Initial Conditions: If Rad PAR review criteria is not exceeded, Rad PAR is not required.

Releae in progress that exceeds Federal release rate of:

2.42E+05pCi/sec Noble Gas (Salem) Rad PAR OR Review Critera Field survey dose rate at or beyond the MEA exceeds:

50 mR/hr Noble Gas or 250 mR/hr Thyroid Commitment.

CONTINUE IF ABOVE CRITERA IS EXCEEDED

-y7 Does TEDE DOSE (4 day) YES on the SSCL exceed 1000 mRem at 5 miles Evacuate ALL Sectors 0-5 miles Evacuate Downwind +1 sector 5-10 miles Shelter remaining sectors 5-10 miles NO --A-Does Is THYROID CDE DOSEý YES THYROID CDE DOSE YES on the SSCL exceed 5000 based on a measured value mRem at and not on a default 5 miles value NO NO V

Does TEDE DOSE (4 day) YES on the SSCL exceed 1000 mRem at the MEA or 2 miles "7 J Evacuate All Sectors 0-5 miles NO Does Is THYROID CDE DOSE YES THYROID CDE DOSE-- YES on the SSCL exceed 5000 based on a measured value mRem at the MEA "and not on a default or 2 miles value NO NO NO RADIOLOGICAL PROTECTIVE ACTION RECOMMENDATION REQUIRED!!

Salem Page 28 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 7 Page 2 of 2 Recommended Protective Action Guidelines WIND DIRECTION FROM PAR AFFECTED SECTORS DEGREES COMPASS DOWNWIND +/-1 SECTORS 349-011 N SSE - S - SSW 011 -034 NNE S - SSW - SW 034-056 NE SSW - SW - WSW 056-079 ENE SW -WSW --W 079- 101 E = WSW-W- WNW 101-124 ESE = W-WNW-NW 124- 146 SE = WNW - NW - NNW 146- 169 SSE NW-NNW-N 169-191 S NNW - N - NNE 191-214 SSW N -NNE-NE 214-236 SW NNE-NE-ENE 236- 259 WSW NE- ENE- E 259-281 W = ENE - E- ESE 281 -304 WNW > E - ESE- SE 304-326 NW = ESE- SE- SSE 326-349 NNW = SE - SSE - S NOTE: CONSIDER ADDING A SECTOR TO THE PAR IF THE WIND DIRECTION (FROM) IS WITHIN OF A Y30 SECTOR DIVIDING LINE.

10 2810 0790 1010 259° 1910 1690 Salem Page 29 of 35 Rev. 04

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ATTACHMENT 8 Page 1 of 1 ONSITE PROTECTIVE ACTION GUIDELINES 1.0 RADIATION LEVELS Dose Rate (mR/hr) Location Action

> 100 Onsite Evacuation of all nonessential personnel.

Consider evacuation of other personnel.

Dose Rate (mR/hr) Location Action

> 100 Control Room Consider evacuation OSC within one hour, TSC and/or relocation as Control Point appropriate.

Dose Rate (mR/hr) Location Action

> 1000 Onsite Evacuation of all nonessential personnel Consider immediate evacuation of remaining personnel.

Dose Rate (mR/hr) Location Action

> 1000 Control Room Consider immediate 0SC evacuation, and/or TSC relocation upwind of Control Point the plume.

2.0 RADIOIODINE If the Iodine-1 31 equivalent is calculated or measured in concentrations greater than or equal to 5.OE-7 uCi/cc, consider the use of Potassium Iodide for thyroid blocking. This section is to be applied to areas, in which personnel are working or are planning to work.

Refer to Emergency Procedure NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking, for additional information.

Salem Page 30 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 9 Page 1 of I CONTAMINATION CONTROL GUIDANCE North End Locked Door of Rad Pro Office Area Initial Step Off Pad i

Contamination Monitors Instrument Issue X~CSep Off Pad F-Men's i_ __

Locker Room 0

r-i.

I 0K

- Step Off U i Pad _ --- __

-up Locked Door L Salem Page 31 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 10 Page 1 of 3 STEAM GENERATOR TUBE LEAK/RUPTURE GUIDELINES 1.0 STEAM GENERATOR TUBE LEAK/RUPTURE GUIDELINES 1.1 Refer to the Following Guidelines for Assistance During a Steam Generator Tube Leak/Rupture.

1.1.1 REFER to SC.RP-TI.RM-0607(Q) Primary To Secondary Leak Rate Calculation Based on R15 or R19 Data, to monitor steam generator leak rate. Keep the OS informed of leak rates.

NOTE A Steam Generator Tube Rupture (SGTR) that occurs without a breach of the Main Steam Line(s) (MSL) will be a monitored, but unfiltered release.

The Plant Vent Effluent Radiation Monitors (R41A- C & R45B - C) will detect this release and dose assessment may be performed using the appropriate Plant Vent Effluent Radiation Monitor in accordance with (lAW)

NC.EP-EP.ZZ-0309(Q) Dose Assessment unless or until Operations isolates the pathway from the condenser air removal header to the Plant Vent.

" Dose assessment may be performed using the R46 monitor value during a primary to secondary leak or SGTR lAW NC.EP-EP.ZZ-0309(Q) Dose Assessment.

" Dose assessment may be performed in the case of a breach of the MSL, or the appropriate R46 monitor being out of service, by taking a dose rate on a PRE-EXISTING TELETECTOR RAD MONITORING LOCATION of the affected MSL lAW NC.EP-EP.ZZ-0309(Q) Dose Assessment.

" The PRE-EXISTING TELETECTOR RAD MONITORING LOCATIONS are at the bend of the MSL, prior to the Main Steam Isolation Valves. Refer to NC.EP-EP.ZZ-0309(Q), Dose Assessment (Attachment 1) for a diagram.

1.1.2 IF appropriate, THEN perform dose assessment using a dose rate taken from the MSL and inputting it into MIDAS lAW NC.EP-EP.ZZ 0309(0), Dose Assessment, using the predetermined teletector correction factor of (9.33E-05) or the R46 monitor value, as appropriate.

Salem Page 32 of 35 Rev. 04

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ATTACHMENT 10 Page 2 of 3 1.1.3 CONSIDER setting up contamination controls for the Turbine Building due to pre-existing leaks should be considered contaminated.

(Contamination levels could increase to "Contamination Area" values due to the secondary side being contaminated from the primary side).

1.1.4 IF radiological conditions in the area warrant it, THEN establish the Turbine Building or portions of the Turbine as Radiation Areas or High Radiation Areas (The dose rates could increase to these levels due to the secondary side being contaminated by the primary side).

NOTE

" The possibility exists that the entire Protective Area for Salem and Hope Creek could become a contaminated area where only clean islands exist.

" All areas of water found on Plant surfaces/floors and in the Yard, should be considered contaminated, until proven otherwise.

1.1.5 CONSIDER setting up contamination controls promptly, to ensure that the Control Room/OSC, Control Point, TSC and Main Guard House are maintained as clean islands.

1.1.6 CONSIDER the following items to help maintain these areas as clean islands:

"* DELIVER Shoe covers, gloves, friskers, PC and waste Containers to the Control Room/OSC.

" DRESS Anyone exiting the CR/OSC clean area in shoe covers and gloves.

" FRISK all personnel prior to entering the CR/OSC.

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ATTACHMENT 10 Page 3 of 3

" DECONTAMINATE all contaminated persons, as time and manpower permits.

" PREVENT contaminated persons or items/equipment from entering into clean areas without Supervision's approval.

" SETUP the entrance(s) to the Main Guard House, with step off pads, friskers, PC and waste containers, as time and manpower permits.

"* DELIVER shoe covers and gloves to the Guard House, to be worn by anyone exiting the guard house into the Protected Area, as time and manpower permits.

"* REQUEST the OS for additional support from Hope Creek to assist with appropriate tasks, if thought necessary.

Salem Page 34 of 35 Rev. 04

SC.EP-EP.ZZ-0301 (Q)

FORM 1 Page 1 of 1 HABITABILITY LOG DATE: / I DOSE RATE CONTAMINATION TIME LOCATION (mR/hr) (CPM) INITIALS

+ I 4 I. I 4 1 t 4- 4 1 +/-

.4- 1 T I. p ~ t i 4 +/- r I +/- 1- r 4 1- t t 4 4 + I 4 1 1

___________ .4 ______________

IF other means are used to ensure habitability, THEN list:

Salem Page 35 of 35 Rev. 04

PSEG Internal Use Only PAGE 1 OF 1 PSE&G NUCLEAR LLC HC.EP-EP.ZZ-0301 (Q) - REV. 03 SHIFT RADIATION PROTECTION TECHNICIAN RESPONSE USE CATEGORY: II REVISION

SUMMARY

1. Revised Step 1.1.21 of Attachment 1 to refer to Attachment 6 instead of Attachment 7.

2. Revised the position who approves EP implementing procedures from Vice President Operations to Director - Operations.

IMPLEMENTATION REQUIREMENTS:

PSE&G CONTROL Implementation Date: --13 ,/- ý -- 2 COPY #*,*_, -

APPROVED:,N.

,EP - Manager Date APPROVED: 4fia Date Director' .Oeeraions Dt

HC.EP-EP.ZZ-0301 (Q)

SHIFT RADIATION PROTECTION TECHNICIAN RESPONSE TABLE OF CONTENTS Section Title Page 1.0 P UR P O S E ........................................................................................................ 3 2 .0 P R E R E Q UIS IT E S ....................................................................................... .. 3 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure ... 3 3.0 PRECAUTIONS AND LIMITATIONS .......................... .3 3.1 Precaution and Limitations To Be Followed Prior To Implementing This P ro c e d u re ....................................................................................... . .. 3 4.0 EQUIPMENT REQUIRED ........................................................................... 3 5 .0 P R O C E D UR E ................................................................................................... 4 5 .1 T h e S R P T S h o u ld ................................................................................... 4 5.2 When the TSC is Activated, Perform the Following ................................ 4 6 .0 R E C O R D S ........................................................................................................ 5 7 .0 R E F E R E NC E S ........................................................................................... .. 5 7 .1 R efe re n ce s ....................................................................................... .. 5 7 .2 C ross R eference s ............................................................................. . .5 ATTACHMENTS ATTACHMENT 1 - Shift Radiation Protection Technician Checklist .................................. 6 ATTACHMENT 2 - Hope Creek RMS Status Sheet ........................................................ 11 ATTACHMENT 3 - Radiological Based Protective Action Recommendations Flowchart and Recommended Protective Actions Worksheet ............................... 13 ATTACHMENT 4 - Onsite Protective Action Guidelines ...................................................... 15 ATTACHMENT 5 - DAPA Correction Calculations ............................................................... 16 ATTACHMENT 6 - RMS Quick Reference ........................................................................ 17 FORMS F o rm 1 - Ha b ita b ility Lo g .............................................................................................. . . . 19 Hope Creek Page 1 of 21 Rev. 03

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FIGURES FIG UR E 1 DA PA Correction Figure .......................................................................... 20 FIG UR E 1 DA PA Correction Figure ............................................................................ 21 Hope Creek Page 2 of 21 Rev. 03

HC.EP-EP.ZZ-0301 (Q) 1.0 PURPOSE To outline and describe the Shift Radiation Protection Technician's (SRPT) duties during a declared emergency 2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure Implement this procedure at:

"* The discretion of the Operations Superintendent (OS) or Radiation Protection Supervision.

"* Upon a declaration of an Unusual Event or greater emergency classification.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure 3.1.1 It is recommended that initials be used in the place keeping sign-offs, instead of checkmarks, if more than one person may implement this procedure.

3.1.2 Personnel who implement this procedure shall be trained and qualified lAW the Emergency Plan.

3.1.3 Steps listed in this procedure may be performed in the order deemed appropriate for the emergency situations. Only steps applicable to the specific emergency need be performed.

4.0 EQUIPMENT REQUIRED As provided at the Control Point and Control Room.

Hope Creek Page 3 of 21 Rev. 03

HC.EP-EP.ZZ-0301 (Q) 5.0 PROCEDURE NOTE The OS may change any priority for the SRPT, as deemed necessary.

5.1 The SRPT Should:

5.1.1 START completing Attachment 1, Shift Radiation Protection Technician Checklist.

5.2 When the TSC is Activated Perform the Following:

5.2.1 COMPLETE the turnover of Dose Assessment/Station Status Checklist duties to the Radiation Protection Supervisor - Offsite or the Radiological Assessment Coordinator (RAC).

5.2.2 IF RMS data is not available from the RM-1 1 or the VAX LA1 20, THEN perform the following steps every 15 minutes:

A. DOCUMENT radiation monitors that are in Alarm on Attachment 2, Hope Creek RMS Status Sheet, from the Control Room by referring to the 10C604 Panel.

B. DOCUMENT other radiation monitor values as instructed by the OS or Radiation Protection Supervision on Attachment 2.

C. FAX the completed Attachment 2 to the TSC and EOF using the Group "C" key D. PROVIDE a completed copy of Attachment 2 to the Radiation Protection Supervisor - Exposure Control (RPS-EXP) located in the OSC, every 15 to 20 minutes, or in the opinion of the SRPT, conditions warrant it.

5.2.3 IMPLEMENT NC.EP-EP.ZZ-0303(Q), Control Point Radiation Protection Response.

Hope Creek Page 4 of 21 Rev. 03

HC.EP-EP.ZZ-0301 (Q) 60 RECORDS Return completed procedure and any information or data thought to be pertinent by the SRPT, to the Emergency Preparedness Manager.

7.0 REFERENCES

7.1 References Nuclear Business Unit Emergency Plan 7.2 Cross References 7.2.1 NC.EP-EP.ZZ-0302, Radiological Coordinator Response 7.2.2 NC.EP-EP.ZZ-0303(Q), Control Point Radiation Protection Response Hope Creek Page 5 of 21 Rev. 03

HC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 1 Page 1 of 5 SHIFT RADIATION PROTECTION TECHNICIAN CHECKLIST 1.0 SRPT INITIAL ACTIONS NOTE

"* Refer to NC.EP-EP.ZZ-0303(Q), for Assembly/Accountability directions at the Control Point, if implemented.

"* Refer to NC.EP-EP.ZZ-0309(Q), Dose Assessment, for VAX LA120 operation instructions.

"* Refer to HC.RP-TI.ZZ-0004(Q), Gaseous Effluent Survelliance, for sampling instructions, as needed.

1.1 Perform the Following:

1.1.1 REPORT to the CR when an emergency is declared to receive a briefing from the OS.

1.1.2 REQUEST that the SRPT, or his designee, located at the Control Point, be notified if FRVS is placed in service.

1.1.3 OBTAIN the identity of Communicator 2 (Name) 1.1.4 REQUEST the status of the MET Tower's operability.

IF the MET Tower is not operational, THEN refer to step 1.1.8.

1.1.5 PROVIDE a briefing to the OS, which should include the following Information:

"* Habitability of the Control Point and Control Room.

"* Any unusual dose rates, Plant Conditions, or Alarms observed on the way to the CR.

Hope Creek Page 6 of 21 Rev. 03

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ATTACHMENT I Page 2 of 5 NOTE

"* On a back shift, during a non-outage situation, there should be two Rad Pro Techs and one Chemistry Tech available at all times at Salem.

"* The Salem Control Point may be contacted at extension 2635, 2644, or 2608 (Radiation Protection Supervisor's phone).

The staffing of the Salem Radiation Protection and Chemistry personnel.

NOTE

" The SRPT should be generating page two of the Station Status Checklist (SSCL) for Hope Creek, during Common Site Events. The Salem SRPT will be generating a SSCL for Salem Units 1 and 2 during Common Site Events.

"* A blank SSCL, page 2, may be obtained from Communicator Number 2, if necessary.

1.1.6 IMPLEMENT NC.EP-EP.ZZ-0309(Q), Dose Assessment, to perform dose assessment and generate a completed SSCL pg. 2 every 30 minutes 1.1.7 PERFORM the following steps, if automatic data acquisition MIDAS and/or the MET Computer is not operational:

"* REFER to Attachment 2, Hope Creek RMS Status Sheet.

"* COMPLETE Vent Process Monitors and the MET Data section every 15 minutes.

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ATTACHMENT 1 Page 3 of 5 1.1.8 OBTAIN the MET data from the following sources, if the MET Computer is not operational:

"* Salem Unit One Control Room (NETS X5120, DID X5111)

"* National Weather Service at 609-261-6604 or 609- 261- 6603.

1.1.9 IMPLEMENT NC.EP-EP.ZZ-0309(Q), Dose Assessment, for instructions on performing dose assessment in the manual mode.

1.1.10 INPUT the appropriate effluent monitor and MET values manually into MIDAS to perform dose assessment in the manual mode.

NOTE Contact an Emergency Preparedness representative at x1571 or 1157, concerning any MIDAS problems.

1.1 11 IF the MIDAS computer located at the CP is not operational, THEN use one of the MIDAS computers listed below:

"* Hope Creek TSC

"* Salem Control Room

"* Salem TSC 1.1.12 DETERMINE appropriate PAR, if any, utilizing the most current SSCL and Attachment 3, Radiologically Based Protective Action Recommendation Worksheet Worksheet.

1.1.13 REVIEW the SSCL and the Radiological Based PAR with the OS utilizing Attachment 3 to explain the PAR you are providing, if needed.

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ATTACHMENT 1 Page 4 of 5 1.1.14 PROVIDE the signed SSCL to Communicator Number 2. or leave it with the OS, if he requests to keep it.

1.1.15 ASSIST the OS with completion of Page 2 of the NRC Data Sheet, if asked to.

1.1.16 PERFORM habitability checks at the CP, CR, and the OSC if activated, every thirty minutes and record results on Form - 1, Habitability Log, unless told otherwise by the OS, Radiation protection - Exposure Control (RPS - EXP), or the Radiological Assessment Coordinator (RAC).

1.1.17 MAKE appropriate Onsite PARs to the OS or RAC for Onsite locations using Attachment 4, Onsite Protective Action Guidelines.

1.1.18 ESTABLISH Contamination Controls (no eating, no drinking, no smoking, proper postings, setting up step off pads and friskers) lAW NC.EP-EP.ZZ-0303(Q), Figures 1-1 through 1-4, when any of the following have occurred:

NOTE Noble Gas (NG) Offsite Dose Calculation Manual (ODCM)/Federal Limits are 1.20E+04 uCi/second. for Hope Creek.

" A radiological release > NG technical specification limits is in progress.

" The potential of a radiological release > NG technical specification limits is thought to be high.

"* Normal RCA boundaries have been breached.

"* At the RAC's discretion.

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ATTACHMENT I Page 5 of 5 1.1.19 NOTIFY the RAC and RPS-EXP of changing radiological conditions as determined from step 1.1.18.

NOTE DAPA monitor readings fluctuate due to Drywell temperature. Consult Attachment 5, DAPA Correction Calculations, to perform the required calculations to obtain the correct DAPA monitor readings, if necessary.

1.1.20 TREND RMS data utilizing the RM-1 1 or the VAX LA1 20.

1.1.21 REFER to Attachment 6, RMS Quick Reference, for information concerning some of the RMS monitors.

1.1.22 REFER to HC.RP-AR.SP-0001 (Q), Radiation Monitoring System Alarm Response for more complete information concerning RMS.

1.1.23 IMPLEMENT Section 5.2 of this procedure, and follow appropriate steps, when the TSC is activated.

TURNOVER Given By: _______________

Date/Time:

TURNOVER Received By: Date/Time: --

Hope Creek Page 10 of 21 Rev. 03

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ATTACHMENT 2 Page 1 of 2 HOPE CREEK RMS STATUS SHEET DATE: _/ / TIME:

CURRENT RANGE RANGE TITLE READING UNITS (LOW) (HIGH)

FRVS cfm 2.OOE+02 9.00E+03 NPV cfml O.OOE+00 4.19E+04 SPV cfm 0.OOE+00 4.48E+05 HTV cfln 0.00E+00 2.50E+04 NOTE: CONTACT THE NATIONAL WEATHER SERVICE AT (609) 261-6604 OR (609) 261-6602.

METEOROLOGICAL DATA WND SPD 33 FT. MPH N/A N/A WND SPD 150 FT. MPH N/A N/A WND SPD 300 FT. MPH N/A N/A WND DIR 33 FT DEG FROM N/A N/A WND DIR 150 FT DEG FROM N/A N/A WND DIR 300 FT DEG FROM N/A N/A DELTA T (150-33) DEG C N/A N/A DELTA T (300-33) DEG C N/A N/A STAB. CLASS A-G N/A N/A VENT PROCESS MONITORS FRVS LOW RANGE uCi/cc 1.00E-08 1.00E-01 FRVS MID RANGE uCi/cc 1.00E-03 1.00E+02 FRVS HIGH RANGE uCi/cc 1.OOE-01 1.00E+05 FRVS EFFLUENT uCI/sec 0.00E+00 1.00E+12 NPV PARTICULATE uCi/cc 5.OOE-12 1.00E-06 NPV IODINE uCi/cc 1.LOE- 11 .O1E-05 NPV LOW RANGE uCi/cc 1.00E-08 1.O0E-0 I NPV MID RANGE uCi/cc 1.OOE-03 1.00E+02 NPV HIGH RANGE uCi/cc 1.00E-01 1.00E+05 NP\. EFFLUENT uCi/cc 5.OOE-12 1.OOE-06 SPV PARTICULATE uCi/cc 5.OOE-12 1.OOE-06 SPV IODINE uCi/cc 1.1OE-1 1 1.1OE-05 SPV LOW RANGE uCi/cc 1.OOE-08 1.OOE-01 SPV MID RANGE uCi/cc 1.OOE-03 1.00E+02 SPV HIGH RANGE uCi/cc 1.OOE-01 1.00E+05 SPV EFFLUENT uCi/cc 5.OOE-12 1.00E-06 HTV LOW RANGE uCi/cc 1.00E-04 1.00E+02 HTV MID RANGE uCi/cc 5.OOE+00 5.OOE+05 HTV EFFLUENT uCi/sec 5.OOE-03 2.60E+07 DRYWELL MONITORS DAPA A R/hr 1.00E+00 1.00E+08 DAPA B R/hr 1.00E+00 1.00E+08 DW LEAK DETECT. uCi/cc 1.OOE-06 1.00E-01 MSL A nMR/hr 1.00E+00 1.00E+06 MSL B nRlir 1.00E+00 1.00E+06 MSL C mR/hr 1.00E+00 1.00E+06 NISL D mR/hr 1.00E+00 1.00E+)06 Hope Creek Page 11 of 21 Rev. 03

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ATTACHMENT 2 Page 2 of 2 CURRENT RANGE RANGE TITLE READING UNITS (LOW) (HIGH)

MAIN CR mR/hr 1.00E-01 1.00E+04 TSC VESTIBULE mR/hr 1.00E-01 1.00E+04 CHEM LAB SAM RM mR/hr 1.OOE-0I 1.00E-04 RAD WASTE CR mR/hr 1.OOE-01 1.00E-04 OFFGAS TREAT CR mR/hr 1.00E-01 1.00E+04 OFFGAS VIAL SS mR/hr I.OOE-0 1 1.00E+04 RADWASTE SS mR/hr 1.OOE-0I 1.00E--04 RX BLDG SS mR/hr 1.OOE-0I 1.00E-04 OUTSIDE RX BLDG SS mR/hr 1.OOE-01 1.00E-04 FRVSV SKID mR/hr 1.OOE-01 1.00E+04 FRVSV LRP mR/hr 1.00E-01 1.00E÷04 PERSONNEL AIRLOCK mR/hr 1.00E-01 1.00E+04 EQUIPMENT AIRLOCK mR/hr I.OOE-01 1.00E+04 MOTOR EQUIP AIRLOCK mR/hr 1.00E-01 1.00E+04 OPEN EQUIP HATCH mR/hr I.OOE-01 1.00E+04 SPENT FP DEMIN EQUIP mR/hr I.OOE-01 1.00E+04 AUX HATCHWAY mR/hr I.OOE-01 1.00E+04 REST MACH SHOP A mR/hr 1.00E-01 1.00E+04 REST MACH SHOP B mR/hr I.OOE-0I 1.00E+04 SPENT FUEL POOL mR/hr 1.00E-01 1.00E+04 NEW FUEL A mR/hr I.00E-0I 1.00E+04 NEW FUEL B mR/hr I.OOE-01 1.00E+04 PROCESS MONITORS REFUELING FLR EXH A uCi/cc I.OOE-06 I.OOE-02 REFUELING FLR EXH B uCi/cc I.OOE-06 1.OOE-02 REFUELING FLR EXH C uCi/cc 1.00E-06 I.OOE-02 REACTOR BLDG EXH A uCi/cc I.OOE-06 1.00E-02 REACTOR BLDG EXH B uCi/cc I.OOE-06 1.00E-02 REACTOR BLDG EXH C uCi/cc 1.OOE-06 1.00E-02 CR VENTILATION C uCi/cc 1.OOE-06 1.00E-02 CR VENTILATION CI uCi/cc 1.OOE-06 1.OOE-02 CR VENTILATION D uCi/cc 1.OOE-06 1.OOE-02 CR VENTILATION DI uCi/cc I.OOE-06 I.OOE-02 COOLING TOWER BLDN uCi/cc 1.OOE-06 I.OOE-02 LIQUID RAD WASTE uCi/cc 1.OOE-06 1.OOE-02 OFFGAS A mR/hr 1.00E+00 1.00E+06 OFFGAS B mR/hr 1.00E+00 1.00E+06 OFFGAS TREAT SYS A cpm 1.00E+01 1.00E+06 OFFGAS TREAT SYS B cpm I.OOE+OI 1.00E+06 RX BLDG VENT SYS EXH uCi/cc 1.00E-06 I.OOE-02 TB BLDG EXH uCi/cc 1.OOE-06 1.00E-02 TB BLDG COMPART EXH uCi/cc I.OOE-06 1.00E-02 RADWASTE EXH SYS uCi/cc I.OOE-06 1.OOE-02 RADWASTE AREA EXH uCi/cc 1.OOE-06 1.OOE-02 GAS R W AREA EXH UCi/cc 1.OOE-06 1.00E-02 Hope Creek Page 12 of 21 Rev. 03

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ATTACHMENT 3 Page 1 OF 2 RADIOLOGICAL BASED PROTECTIVE ACTION RECOMMENDATION FLOW CHART AND WORKSHEET Initial Conditions: If Rad PAR review criteria is not exceeded, Rad PAR is not required.

Release in progress that exceeds ODCM/Federal Limits release rate 1.20E+04 uCi/sec Noble Gas (hD Field survey dose rate at or beyond the MEA exceeds: Rad PAR 50 mR/hr Noble Gas Review Criteria OR 250 mR/hr Thyroid Commitment CONTINUE IF ABOVE CRITERIA IS EXCEEDED YES Does TEDE DOSE (4 day) base onea measure valu0 emSl at a n-5 Evacuate ALLSectors miles NOE (e

on000based SSL exeed on a measured value m~em atand not a default 5 milesvalue?

NO NO NO RADIOLOGICAL PROTECTIVE ACTION RECOMMENDATION REQUIRED7!!I Hope Creek Page 13 of 21 Rev. 03

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ATTACHMENT 3 Page 2 of 2 WIND DIRECTION FROM PAR AFFECTED SECTORS DEGREES COMPASS DOWNWIND +/-1 SECTORS 349- 011 N SSE- S- SSW 011 -034 NNE S - SSW - SW 034-056 NE _ SSW - SW - WSW 056-079 ENE SW-WSW-W 079-101 E WSW-W-WNW 101-124 ESE = W - WNW - NW 124- 146 SE = WNW - NW - NNW 146- 169 SSE = NW - NNW - N 169-191 S NNW-N-NNE 191-214 SSW = N - NNE-NE 214- 236 SW NNE-NE-ENE 236- 259 WSW NE - ENE- E 259-281 W ENE - E- ESE 281 -304 WNW E- ESE - SE 304-326 NW ESE- SE- SSE 326 - 349 NNW SE- SSE- S NOTE: CONSIDER ADDING A SECTOR TO THE PAR IF THE WIND DIRECTION (FROM) IS WITHIN +/-30 OF A SECTOR DIVIDING LINE.

10 3490 MILES 0110 2810 0790 1010 2590 1910 1690 Hope Creek Page 14 of 21 Rev. 03

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ATTACHMENT 4 Page 1 of 1 ONSITE PROTECTIVE ACTION GUIDELINES 1.0 RADIATION LEVELS Dose Rate (mR/hr) Location Action

> 100 Onsite Evacuation of all nonessential personnel.

Consider evacuation of other personnel.

Dose Rate (mR/hr) Location Action

> 100 Control Room Consider evacuation OSC within one hour, TSC and/or relocation as Control Point appropriate.

Dose Rate (mR/hr) Location Action

> 1000 Onsite Evacuation of all nonessential personnel Consider immediate evacuation of remaining personnel.

Dose Rate (mR/hr) Location Action

> 1000 Control Room Consider immediate OSC evacuation, and/or TSC relocation upwind of Control Point the plume.

2.0 RADIOIODINE If the Iodine-1 31 equivalent is calculated or measured in concentrations greater than or equal to 5.OE-7 uCi/cc, consider the use of Potassium Iodide for thyroid blocking. This section is to be applied to areas, in which personnel are working or are planning to work.

Refer to Emergency Procedure NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking, for additional information.

Hope Creek Page 15 of 21 Rev. 03

HC.EP-EP.ZZ-0301 (Q)

ATTACHMENT 5 Page 1 of I DAPA CORRECTION CALCULATIONS NOTE DAPA temperature is located on the VAX LA120, Operation Status Board (EOF Menu Selection "2").

1.0 DAPA CORRECTION CALCULATIONS 1.1 To Correct For DAPA High Temperature, Perfrom The Following 1.1.1 REFER to Figure 1-1.

1.1.2 IF the uncorrected DAPA reading lies below the curve, THEN the DAPA Monitor reading is unreliable and should not be used.

1.1.3 PROCEED to step 1.4, if the uncorrected DAPA reading lies above the curve.

1.1.4 REFER to Figure 1-2.

1.1.5 DETERMINE a BIAS value to add to the uncorrected DAPA reading by finding the value on the curve that corresponds to the associated average Drywell Air Temperature.

-I-DAPA Monitor Bias Value Corrected DAPA Reading (R/hr) Reading (R/hr) Reading (R/hr)

Hope Creek Page 16 of 21 Rev. 03

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ATTACHMENT 6 Page 1 of 2 RMS QUICK REFERENCE Hope Creek NOTE All ARM's in the Reactor Building have maximum ranges of 1.OOE+04 mR/hr, except for the Inner Tip Room Monitor (9RX699). The Inner Tip Room Monitor's maximum range is 1.OOE+07 mR/hr.

DAPA A and DAPA B (9RX635 and 9RX636) are high range ARMs in the Drywell.

DAPA A is approximately twice as high as DAPA B under normal operating conditions.

During a LOCA in the Drywell the two monitors should start to trend closer together due to the atmospheric conditions in the Drywell affecting both monitors equally.

Increases on both of these monitors while DAPA A's reading stays about twice of what DAPA B is reading, would be an indication of fuel damage.

Ranges: 1.OOE+00 to 1.OOE+08 R/hr.

Tip Room Inner ARM (9RX699) is located on 102' elevation of the Reactor Building inside the Tip Room. This monitor has the highest range of any ARM in the Reactor Building and could give an idea of what the dose rates in the Reactor Building are after the other ARMs peg out high.

Ranges: 1.OOE+00 to 1.OOE+07 mR/hr Main Steam Line A - D monitors (9RX509-512) are four ARMs located in the ceiling of the Main Steam Tunnel. Increases in these monitors would be an indication of fuel damage. These monitors could increase due to shine from the Reactor Building, after a radiological release.

Ranges: 1.OOE+00 to 1.OOE+06 mR/hr Safeguard Instrument Room Monitor (9RX704) is an ARM located on 77' elevation of the Reactor Building. An increase on this monitor when the reactor SCRAMs with fuel damage could be due to shine from the Torus.

Ranges: 1.O0E-01 to 1.OOE+04 mR/hr Hope Creek Page 17 of 21 Rev. 03

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ATTACHMENT 6 Page 2 of 2 FRVS Effluent monitor (9RX680) monitors what is going out the FRVS Plant Vent.

Under normal operating conditions Reactor Building ventilation would vent through the South Plant Vent. Under accident conditions or when manually initiated, Reactor Building Ventilation isolates and the Reactor Building will vent through the FRVS. FRVS is always a ground release. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.OOE+12 uCi/Sec North Plant Vent Effluent (NPV) monitor (9RX590) monitors Offgas and the chemistry lab fume hoods. NPV could be a ground or elevated release depending on the time of year and wind speed. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+O0 to 1.OOE+12 uCi/Sec South Plant Vent Effluent (SPV) monitor (9RX580) monitors Service Radwaste Building, Turbine Building and the Reactor Building (if FRVS hasn't been initiated).

Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.OOE+1 2 uCi/Sec Hardened Torus Vent Effluent (HTV) monitor (9RX518) would be used to vent the Drywell to relieve pressure. The path it would take would be through the Torus and take advantage of the scrubbing properties of the Torus water. Control Room operators would have to open a valve to use this release path. Sampling from the PASS Torus Gas Space should be performed to provide information as to what is being released.

Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: O.OOE+00 to 2.09E+12 uCi/Sec Hope Creek Page 18 of 21 Rev. 03

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FORM - 1 Page 1 of 1 HABITABILITY LOG (FORM - 1)

DATE:

DOSE RATE CONTAMINATION 1 TIME PERFORMED/LOCATION (mR/hr) (CPM) INITIALS 4 i 4 4 4

.4 4 4

.4 4 4 1- 4 4 i 4 4

+ 4 4 IF other means are used to ensure habitability, THEN list:

Hope Greek Page 19 of 21 Rev. 03

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FIGURE 1 - 1 Page 1 of 2 DAPA MONITOR READING vs AVERAGE DRYWELL AIR TEMPERATURE DAPA MONITOR READING (R/hr) 30-1 25 20 15 10 0-0--

240 266 280 300 ' 320 340 Average Drywell Air Temperature (OF)

Lined area indicates DAPA Monitor value at which alternate method for determining estimate of Drywell airborne radiation levels should be used.

Hope Creek Page 20 of 21 Rev. 03

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FIGURE 1 - 2 Page 2 of 2 DAPA MONITOR READING BIAS vs AVERAGE DRYWELL AIR TEMPERATURE DAPA MONITOR READING BIAS (R/hr) 30 25 20 15 10-0--

240 2601 2801 300 320 340 AVERAGE DRYWELL AIR TEMPERATURE (TF)

Hope Creek Page 21 of 21 Rev. 03

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