ML003698910

Revised Emergency Plan Implementing Procedures for Salem and Hope Creek

ML003698910
Person / Time
Site:	Salem, Hope Creek
Issue date:	03/29/2000
From:	Public Service Electric & Gas Co
To:	NRC/OCIO/IMD/RMB
References
-RFPFR
Download: ML003698910 (159)

Text

Document Transmittal Form To: NRC WASHINGTON ID: EPIP059 DOCUMENT CONTROL DESK WASHINGTON, DC 20555 Date:20000329 Please update your controlled set of documents with the following list of documents:

Document ID Revision Status Quantity Format RecNo PRCIEPIP-TOC-COMMONI000 1 A 1 H 45040 1 A 1 H 44844 PRCIHC.EP-EP.ZZ-0301 1000 1 A 1 H 44795 PRCINC.EP-EP.ZZ-01 021000 1 A 1 H 44893 PRCINC.EP-EP.ZZ-03021000 1 A 1 H 44942 PRCINC.EP-EP.ZZ-031 01000 1 A 1 H 44991 PRCINC.EP-EP.ZZ-03121000 This acknowledgement receipt must be returned within 5 working days to:

Document Management:

PSEG Nuclear BOX 236 Hancocks's Bridge, NJ 08038 MC N04 Your signature below verifies that:

(1) the above documents have been filed and superseded documents have been removed and destroyed or clearly marked as obsolete.

(2) the mailing address and copy holder information are correct or corrections have been identified on this transmittal.

M Place checkmark here to remove from controlled distribution Signature: Date:

1. bO4

NUCLEAR BUSINESS UNIT PSE&G L ONSITE IMPLEMENTING PROCEDURESONTR March 29, 2000 CHANGE PAGES FOR COPY #

REVISION #01 The Table of Contents forms a general guide to the current revision of each section of the Onsite EPIPs. The changes that are made in this TOC Revision #01 are shown below. Please check that your revision packet is complete and remove the outdated material listed below:

ADD REMOVE Pace Descriotion Rev. Pale Description Rev.

Pane Descrintion ALL TOC 01 ALL TOC 00 ALL EPEP 102 01 ALL EPEP 102 00 ALL HC.EP-EP.ZZ-301 01 ALL HC.EP-EP.ZZ-301 00 ALL EPEP 302 01 ALL EPEP 302 00 ALL EPEP 310 01 ALL EPEP 310 00 ALL EPEP 312 01 ALL EPEP 312 00 EPEP-AIJJ 1 of 1

EPIP T.O.C.

Pg. 1 of 2 PSEG NUCLEAR EMERGENCY PLAN PSE&G ONSITE IMPLEMENTING PROCEDURES TABLE OF CONTENTS CONTROL March 29, 2000 COPY #gwoS STATION PROCEDURES Revision Number Effective Number Pages Date NC.EP-EP. ZZ-0101 (Q) ACTIONS REQUIRED AT O0 12 02/29/2000 UNAFFECTED STATION Ol 19 03/29/2000 NC.EP-EP.ZZ-0102 (Q) EMERGENCY COORDINATOR

RESPONSE

NC.EP-EP.ZZ-0201 (Q) TSC - INTEGRATED O0 24 02/29/2000 ENGINEERING RESPONSE NC.EP-EP.ZZ-0202 (Q) OPERATIONS SUPPORT 00 29 02/29/2000 CENTER (OSC) ACTIVATION AND OPERATIONS NC. EP-EP. ZZ-0203 (Q) ADMINISTRATIVE SUPPORT/ 00 14 02/29/2000 COMMUNICATION TEAM RESPONSE - TSC EPIP 204H EMERGENCY RESPONSE 46 31 12/29/1999 CALLOUT/PERSONNEL RECALL EPIP 204S EMERGENCY RESPONSE 46 32 12/29/1999 CALLOUT/PERSONNEL RECALL HC.EP-EP.ZZ-0205 (Q) TSC - POST ACCIDENT 00 39 02/29/2000 CORE DAMAGE ASSESSMENT SC.EP-EP.ZZ-0205 (Q) TSC - POST ACCIDENT 00 80 02/29/2000 CORE DAMAGE ASSESSMENT HC.EP-EP.ZZ-0301 (Q) SHIFT RADIATION 01 21 03/29/2000 PROTECTION TECHNICIAN

RESPONSE

PSEG NUCLEAR-EPIP Rev. 01

EPIP T.O.C.

Pg. 2 of 2 PSEG NUCLEAR EMERGENCY PLAN ONSITE IMPLEMENTING PROCEDURES TABLE OF CONTENTS March 29, 2000 Revision Number Effective Number Pages Date SC.EP-EP.ZZ-0301 (Q) SHIFT RADIATION 00 34 02/29/2000 PROTECTION TECHNICIAN

RESPONSE

NC.EP-EP.ZZ-0302 (Q) RADIOLOGICAL ASSESSMENT 01 19 03/29/2000 COORDINATOR RESPONSE NC.EP-EP.ZZ-0303 (Q) CONTROL POINT - 00 25 02/29/2000 RADIATION PROTECTION RESPONSE NC.EP-EP.ZZ-0304 (Q) OPERATIONS SUPPORT 00 20 02/29/2000 CENTER (OSC) RADIATION PROTECTION RESPONSE NC.EP-EP.ZZ-0305(Q) POTASSIUM IODIDE (KI) 00 10 02/29/2000 ADMINISTRATION NC.EP-EP.ZZ-0306 (Q) EMERGENCY AIR SAMPLING 00 12 02/29/2000 NC.EP-EP.ZZ-0307 (Q) PLANT VENT SAMPLING 00 13 02/29/2000 NC.EP-EP.ZZ-0308 (Q) PERSONNEL/VEHICLE 00 16 02/29/2000 SURVEY AND DECONTAMINATION NC.EP-EP.ZZ-0309 (Q) DOSE ASSESSMENT 00 78 02/29/2000 NC.EP-EP.ZZ-0310 (Q) RADIATION PROTECTION 01 65 03/29/2000 SUPERVISOR - OFFSITE AND FIELD MONITORING TEAM RESPONSE NC.EP-EP.ZZ-0311 (Q) CONTROL POINT 00 18 02/29/2000 CHEMISTRY RESPONSE NC.EP-EP.ZZ-0312 (Q) CHEMISTRY SUPERVISOR 01 26 03/29/2000 CP/TSC RESPONSE PSEG NUCLEAR-EPIP Rev. 01

PSEG Internal Use Only PSEG NUCLEAR Page 1 of 1 NC.EP-EP.ZZ-0102(Q) Rev. 01 EMERGENCY COORDINATOR RESPONSE USE CATEGORY: II REVISION

SUMMARY

EDITORIAL CHANGES ONLY PSE&G 0 Updated EPEP 902 references from section 3 to section 5. CONTROL 0

0 Step 5.2.5 to state 'CM-1 to receive the NRC data sheet".

Added "NOTE:" to Attachment 9, step 2.8. COPY # gpPo5?

IMPLEMENTATION REQUIREMENTS Issued for use.

APPROVED:

Date APPROVED: Ait Vice President - Operations Date

NC.EP-EP.ZZ-0102 (Q)

EMERGENCY COORDINATOR RESPONSE TABLE OF CONTENTS Section Title Page 1.0 P UR P O S E ............... :................................................................................... 2 2.0 PREREQUISITES ........................................................................................ 2 2.1 Prerequisites to be Followed Prior to Implementation: ....................... 2 3.0 PRECAUTIONS AND LIMITATIONS .......................................................... 2 3.1 Precautions and Limitations to be Followed Prior to Implementation: .... 2 4.0 EQUIPMENT REQUIRED ........................................................................... 2 5.0 PR O C ED U R E: ............................................................................................. 3 5.1 Initial Actions: ..................................................................................... 3 5.2 Emergency Conditions: ..................................................................... 3 5.3 Subsequent Actions ......................................................................... 4 5.4 EC Duties Turnover ........................................................................... 4 5.5 Termination/Reduction/Recovery ...................................................... 4 5.6 R eporting ........................................................................................ .. 4 6.0 R E C O R D S .................................................................................................... 5 7.0 R E FER E N C ES ............................................................................................. 5 7.1 R EFER EN C ES .................................................................................. 5 7.2 CROSS REFERENCES ..................................................................... 5 8.0 COMMITMENT DOCUMENTS ..................................................................... 5 ATTACHMENTS ATTACHMENT 1 REPORTING CHECKLIST ............................................................ 6 ATTACHMENT 2 EC EMERGENCY STATUS BRIEFING FORM .............................. 7 ATTACHMENT 3 ACCOUNTABILITY ACTIONS AND RESULTS .............................. 9 ATTACHMENT 4 GENERAL EMERGENCY MESSAGE ......................................... 11 ATTACHMENT 5 SITE AREA EMERGENCY MESSAGE ......................................... 12 ATTACHMENT 6 ALERT MESSAGE ....................................................................... 13 ATTACHMENT 7 UNUSUAL EVENT MESSAGE .................................................... 14 ATTACHMENT 8 ACTIVATION of the TSC .............................................................. 15 ATTACHMENT 9 ACTIVATION of the EOF ............................................................... 17 NUCLEAR COMMON Page 1 of 19 Rev 01

NC.EP-EP.ZZ-0102 (Q) 1.0 PURPOSE This procedure provides emergency response instructions to the Emergency Coordinator (EC) after emergency classification.

2.0 PREREQUISITES 2.1 Prerequisites to be Followed Prior to Implementation:

2.1.1 ECG Attachment 1, 2, 3, 4 or 24 was completed.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations to be Followed Prior to Implementation:

3.1.1 Initials should be used in place of keeping sign-offs, instead of checkmarks.

3.1.2 Activation of the Emergency Response Organization (ERO) during an Unusual Event is implemented at the discretion of the Emergency Coordinator (EC). If additional support personnel are needed during an Unusual Event, then limited or full staffing of the TSC may be initiated at the discretion of the EC. Limited staffing may be initiated by contacting selected support personnel on an individual basis in lieu of activating the full ERO.

4.0 EQUIPMENT REQUIRED As provided in the Control Room, TSC and EOF.

NUCLEAR COMMON Page 2 of 19 Rev 01

NC.EP-EP.ZZ-0102 (Q)

NOTE Should the EDO/ERM be unable to fulfill the duties of Emergency Coordinator (EC) for any reason (e.g., sudden illness, accident, etc.) the Technical Support Supervisor (TSS) or Site Support Manager (SSM) may assume the duties and responsibilities of EC until another qualified EDO/ERM arrives at the facility.

5.0 PROCEDURE

Note: Initial each block as applicable.

AJE:'

• A jSAE )(GE 5.1 Initial Actions:

Optional ATT 8 ATT 8 ATT 8 EDO 5.1.1. ACTIVATE the TSC. Att 8 Optional Optional ATT 9 ATT 9 ERM 5.1.2. ACTIVATE the EOF. Att 9 Att 9 NOTE Since the Rad Alert alarm is located in the Control Room, the OS directs all emergency status announcements. However, when the EDO or ERM has the Emergency Coordinator duties, he/she ensures that the OS is notified to direct the emergency announcements.

Note: Initial each block as applicable.

5.2 Emergency Conditions: UE A. SAE GE EC 5.2.1. DIRECT the OS to generate the ATT7 ATT6 ATT5 ATT4 announcement of the emergency status and Assembly lAW:

Optional OS 5.2.2 IF not performed previously, (Except THEN DIRECT the OSC Coordinator to bomb Activate the OSC lAW EPEP 202, OSC search)

Activation and Operations.

EC 5.2.3. IF desired or WHEN required, Optional Optional ATT 3 ATT 3 Att 3 Att 3 DIRECT implementation of Accountability lAW:

EPEP 101 EPEP 101 EPEP 101 EPEP 101 Unusual ASSEM ASSEM ASSEM OS 5.2.4 IF not performed previously, Event BLY BLY BLY THEN DIRECT the other station OS to Att 5 Att 4 Att 4 Att 4 Implement EPEP-101, Actions Required at Unaffected Station:

EC 5.2.5 ENSURE the NRC Data Sheet is ECG ECG ECG ECG completed and CM-1 notifies NRC as soon ATT5 ATT5 ATT5 ATT5 as possible, but not to exceed one hour from emergency classification lAW:

NUCLEAR COMMON Page 3 of 19 Rev 01

NC.EP-EP.ZZ-0102 (Q) 5.3 Subsequent Actions OS 5.3.1 COORDINATE and PRIORITIZE OSC tasks in conjunction with accident mitigation efforts.

EC 5.3.2 RECOMMEND to the States of New Jersey and Delaware that the ingestion pathway be monitored, should the radionuclide concentrations be in excess of 10CFR20 Appendix B limits or could potentially exist offsite.

OS/ 5.3.3 IF needed, CONTACT unaffected EDO station OS to identify and request available support personnel.

EC 5.3.4 ENSURE the NRC is notified of significant changes in emergency plant status, and implementation of 10CFR50.54x lAW:

5.4 EC Duties Turnover EC optional ATT 2 ATT 2 ATT 2 IF relief is required, ATT 2 THEN PROVIDE turnover to the EDO/ERM:

Note: Initial each block as applicable.

UE A~ SAE GE 5.5 Termination/Reduction/Recovery OS EDO EDO EDO EC /EDO /ERM /ERM /ERM IMPLEMENT NC.EP-EP.ZZ-0405 (Q),

Emergency Termination /

Reduction/Recovery, as appropriate.

Note: Initial each block as applicable.

UE A,A SAE, GEATT 5.6 Reporting ATT I ATTI1 ATTI1 ATTI1 EC WHEN the event is terminated, THEN ENSURE appropriate reports are made and paperwork is forwarded to EP.

NUCLEAR COMMON Page 4 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q) 6.0 RECORDS Forward all completed ECG Attachments / EPEPs / attachments / forms to Manager - CA, EP, & IT.

7.1 REFERENCES

7.1.1. Nuclear Business Unit Emergency Plan 7.1.2. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 7.1.3. PSE&G Nuclear Business Unit, NC.NA-AP.ZZ-0001(Q), Nuclear Procedure System 7.1.4. PSE&G Nuclear Business Unit, NC.NA-WG.ZZ-0001(Z), Procedure Writer's Guide, 7.2 CROSS REFERENCES 7.2.1 NC.EP-EP.ZZ-0405(Q), Emergency Termination/Reduction/Recovery 7.2.2 Hope Creek/Salem Event Classification Guide (ECG) 8.0 COMMITMENT DOCUMENTS Commitment No. EP96-003, (Item #: LR-N96062)

NUCLEAR COMMON Page 5 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT I Page 1 of 1 REPORTING CHECKLIST Initials

1. ENSURE a Notification is created.

OS

2. FORWARD all completed ECG Attachments, EPEPs, attachments, forms, NRC Data Sheet and any supporting documentation to the Manager - CA, EP, & IT.

OS

3. REVIEW this Attachment, the notification and any other relevant information for correct classification of event and corrective actions taken.

EP

4. FORWARD Copies of the documentation to the LER Coordinator (LERC).

EP

5. FORWARD this documentation to the Central Technical Document Room (CTDR) for microfilming.

LERC NUCLEAR COMMON Page 6 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 2 Page 1 of 2 EC EMERGENCY STATUS BRIEFING FORM NOTE Completion of this Attachment is optional. However, the information listed is useful for providing a thorough turnover to the EC.

1. EAL that is the basis for the emergency classification:

Unusual Site Area General Event Alert Emergency Emergency

a. EAL(s)#

b. Time declared

c. PAR based on 10 Yes Wind dir.

points? __ NO (from)

d. Accountability? ____Yes Results: NO Time

2. Status of important safety systems:

3. Status of fuel cladding, reactor coolant system, and containment integrity:

4. Unusual radiological conditions currently existing:

NUCLEAR COMMON Page 7 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 2 (cont.)

Page 2 of 2

5. OSC activated? ( __YES . NO ) Time Activated In-Plant emergency actions underway (OSC priorities):

6. Identification of "out-of-service" equipment that needs repair: (not on priority list)

7. Offsite emergency actions underway (Did a release occur? Have field-monitoring teams been dispatched? State's PADs, etc.)

8. Prognosis for the situation to improve or worsen:

9. Adequacy of current Control Room staffing (Is an additional person needed to assist with communications?)

10. Emergency Operating Procedures (EOPs) being implemented.

11. Other:

NUCLEAR COMMON Page 8 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 3 Page 1 of 2 ACCOUNTABILITY ACTIONS AND RESULTS Initials/Time

+0 Min DIRECT

• SECURITY (X2222) TO IMPLEMENT EPEP 902, SECTIONS 5.2, Automated Accountability and 5.3, Accountability Report Generation. i

/

EDO/OS SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION, ATTENTION, ALL ACCOUNTABILITY STATIONS, IMPLEMENT ACCOUNTABILITY.

DIRECT 0 Other station's OS TO IMPLEMENT ACCOUNTABILITY lAW NC.EP-EP.ZZ-0101.

Hope Creek (NETS X5221) Salem (NETS X5122)

/

Announcer

+20 Min after above announcement was made.

ANNOUNCE TWICE "ATTENTION, ATTENTION. ALL ACCOUNTABILITY STATIONS, COMPLETE ACCOUNTABILITY.

I Announcer NUCLEAR COMMON Page 9 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 3 (cont.)

Page 2 of 2 Initials

+30 min after implement accountability announcement was made:

1. OBTAIN from Security a list of unaccounted personnel. IF Security has not supplied results of the accountability within 30 minutes of the first accountability announcement, then contact the TSC Security Liaison and request accountability results.

EDO/OS Hope Creek Salem NETS X5214 NETS X5117

2. DESIGNATE an individual to attempt to locate unaccounted personnel as follows:

A. Page individuals over the plant page.

B. Obtain feedback from unaccounted person's co-workers/supervisors on last known location/job assignment.

C. Call individual's home to verify work schedule.

D. Request Security's assistance in locating unaccounted personnel.

EDO/OS

3. UPDATE Security as missing personnel are located.

EDO/OS

4. INITIATE search and rescue operations in accordance with EPEP 202, OSC Activation and Operations, as appropriate.

EDO/OS

5. As the situation dictates and/or as radiological conditions permit:

IF all onsite Emergency Response Facilities are completely staffed, THEN release/evacuate extra personnel who reported to the OSC, TSC, CP or Maintenance Shop for accountability.

EDO/OS NUCLEAR COMMON Page 10 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 4 Page 1 of I GENERAL EMERGENCY MESSAGE Initials SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK - SALEM) IS IN A General Emergency Circle one - cross out the others DUE TO:

ALL PSE&G PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA. ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

Announcer RADIO REPEAT EMERGENCY ANNOUCEMENT MESSAGE Announcer IF NOT PERFORMED PREVIOUSLY, DIRECT Security (x2222)

" IMPLEMENT both EPEP 901, Onsite Security Response, and EPEP 903, Opening of Emergency Operations Facility (EOF).

" IMPLEMENT EPEP 0902, section 5.1 Assembly, DUE TO:

(read "Due TO:" from above)_

Announcer NUCLEAR COMMON Page 11 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 5 Page 1 of I SITE AREA EMERGENCY MESSAGE Initials SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK - SALEM) IS IN A Site Area Emergency Circle one - cross out the others DUE TO:

ALL PSE&G PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA. ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

Announcer RADIO REPEAT EMERGENCY ANNOUCEMENT MESSAGE Announcer IF NOT PERFORMED PREVIOUSLY, DIRECT Security (x2222)

"* IMPLEMENT both EPEP 901, Onsite Security Response, and EPEP 903, Opening of Emergency Operations Facility (EOF).

"* IMPLEMENT EPEP 0902, section 5.1 Assembly, DUE TO: I (read "DUE TO:" from above)

Announcer NUCLEAR COMMON Page 12 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 6 Page 1 of I ALERT MESSAGE Initials SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK - SALEM) IS IN AN Alert Circle one - cross out the others DUE TO:

ALL PSE&G PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA. ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

Announcer RADIO REPEAT EMERGENCY ANNOUCEMENT MESSAGE Announcer IF NOT PERFORMED PREVIOUSLY, DIRECT Security (x2222)

"* IMPLEMENT both EPEP 901, Onsite Security Response, and EPEP 903, Opening of Emergency Operations Facility (EOF).

"* IMPLEMENT EPEP 0902, section 5.1 Assembly, DUE TO: I (read "DUE TO:" from above)_

Announcer NUCLEAR COMMON Page 13 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 7 Page 1 of 1 UNUSUAL EVENT MESSAGE Initials SOUND RAD ALERT ALARM AND ANNOUNCE TWICE "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK - SALEM) IS IN AN UNUSUAL EVENT DUE TO:

Circle one - cross out the other ERSONEL LL ATENION PERONNL.

F AL '('ATTNTIO Announcer RADIO REPEAT UNUSUAL EVENT ANNOUCEMENT MESSAGE Announcer NUCLEAR COMMON Page 14 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 8 Page 1 of 2 ACTIVATION of the TSC 1.0 Prior To TSC Activation (i.e., Before Assuming Emergency Coordinator Duties):

1.1 ESTABLISH and MAINTAIN a chronological log of activity and events.

1.2 OBTAIN a briefing on the status of the emergency from the Operations Superintendent (OS). Refer to Attachment 2, EC Emergency Status Briefing Form for turnover points of discussion.

1.3 ENSURE that TSC section leads are making preparations to assume emergency response functions while ensuring adequate staffing:

"* Radiological Assessment Coordinator (RAC)

"* Technical Support Supervisor (TSS)

"* Administrative Support supervisor

"* EPA or CM-1

"* Security 1.4 PERFORM initial briefing to the TSC staff on emergency conditions and the following issues:

"* Plant conditions

"* Introduce section leads

"* Noise control

"* Administrative services

"* Synchronize all TSC clock and personnel watches with SPDS time.

1.5 PREPARE to activate the TSC and ASSUME the duties and responsibilities of the Emergency Coordinator as follows:

" ENSURE each functional group at the TSC has received a detailed briefing from their counterpart in the Control Room and are ready to support TSC activation. (i.e., EDO/OS, TSS/STA, RAC/SRPT).

" ENSURE TSC communicators are ready to assume communications and notification responsibilities from the TSC. This includes coordination of requirement for the "Station Status Checklist", and NRC Updates.

"* VERIFY which EPEP is currently being implemented by the OS, which steps are completed and which steps will be turned over for completion.

NUCLEAR COMMON Page 15 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 8 Page 2 of 2 Activation of TSC (cont.)

1.6 ACTIVATE the TSC by contacting the OS, and with his concurrence, assume the EC's function.

, Ensure TSC Communicators assume communications and notification responsibilities coincident with the EC turnover.

2.0 Upon Assuming Emergency Coordinator Duties, the EDO Should:

2.1 ANNOUNCE to the staff that the TSC is activated, the effective time and that you are the Emergency Coordinator.

2.2 NOTIFY ERM of TSC activation and provide a brief status update.

2.3 REVIEW the ECG for conditions that may require Event Classification escalation.

2.4 ENSURE the Station Status Checklist is reviewed and approved for transmission to the states every 30 minutes.

2.5 IMPLEMENT NC.EP-EP.ZZ-0404(Q), Protective Action Recommendations Upgrades, after an initial PAR for a General Emergency has been made.

2.6 GIVE a status briefing and coordinate the integration of NRC team members within functional areas of the TSC upon arrival of an NRC emergency response team.

2.7 PROVIDE periodic status briefing to the unaffected station's OS and EDO.

NUCLEAR COMMON Page 16 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 9 Page 1 of 3 ACTIVATION of the EOF 1.0 Prior To EOF Activation (i.e,, Before Assuming Emergency Coordinator Duties):

1.1 THEN ESTABLISH and MAINTAIN a chronological log of activity and events.

1.2 IF the EPC is available:

DIRECT Emergency Preparedness Coordinator (EPC) to implement EPEP 401, EPC Response.

1.3 OBTAIN a briefing on the status of the emergency from the Emergency Duty Officer (EDO). Refer to Attachment 2, Emergency Status Briefing Form for turnover points of discussion.

1.4 ENSURE that EOF section leads are making preparations to assume emergency response functions while ensuring adequate staffing:

A. Radiological Support Manager (RSM)

B. Site Support Manager (SSM)

C. Technical Support Manager (TSM)

D. Administrative Support Manager (ASM) 1.5 ENSURE the Public Information Liaison (PIL) is provided with plant and emergency status information.

1.6 PERFORM initial briefing to the EOF staff on emergency conditions and the following issues:

"* Plant conditions

"* Introduce section leads

"* Noise control

"* ASM provides administrative services

"* Synchronize all EOF clock and personnel watches with SPDS time.

1.7 PERFORM periodic EOF leads briefings to exchange information as outlined lAW, "EOF Briefing Checklist."

1.8 PERFORM briefings for the entire EOF staff regarding current emergency events/status changes.

NUCLEAR COMMON Page 17 of 19 Rev 01

NC.EP-EP.ZZ-0102(Q)

ATTACHMENT 9 Page 2 of 3 Activation of EOF (cont.)

1.9 GIVE a status briefing and coordinate the integration of NRC team members within functional areas of the EOF upon arrival of an NRC emergency response team.

1.10 GIVE and OBTAIN status updates from the EDO to include the status of unaffected units/station, Onsite Protective actions implemented, and Corrective Actions in progress and their priorities.

1.11 DIRECT ASM to request assistance from federal, state, local, and private support agencies as required.

1.12 DIRECT ASM to assure continuity of personnel and resources for 24-hour operation of all emergency response facilities.

1.13 PREPARE to activate the EOF and ASSUME the duties and responsibilities of the Emergency Coordinator as follows:

A. ENSURE each functional group at the EOF has received a detailed briefing from their counterpart in the TSC and are ready to support EOF activation. (i.e., ERM/EDO, SSM/TSS, RSM/ RAC, TSM/TSTL, ASM/AS-SUP, EPA EOF/EPA TSC).

B. ENSURE EOF communicators are ready to assume communications and notification responsibilities from the TSC. This includes coordination of requirement for the "Station Status Checklist", NRC Updates, and Offsite Dose Assessment.

1.14 ACTIVATE the EOF by contacting the EDO, and with his concurrence, assume the Emergency Coordinator's function.

• Ensure EOF Communicators assume communications and notification responsibilities coincident with the EC turnover.

NUCLEAR COMMON Page 18 of 19 Rev 01

NC.EP-EP.ZZ-O102(Q)

ATTACHMENT 9 Page 3 of 3 Activation of EOF (cont.)

2.0 Upon Assuming Emergency, Coordinator Duties, the ERM Should:

2.1 ANNOUNCE to the staff that the EOF is activated, the effective time and that you are the Emergency Coordinator.

2.2 NOTIFY State Directors of EOF activation and provide a brief status update. (NJ Director - NETS x541 0; DE Director - NETS x5412) 2.3 REVIEW the ECG for conditions that may require Event Classification escalation.

2.4 ENSURE the Station Status Checklist is reviewed and approved for transmission to the states every 30 minutes.

2.5 IMPLEMENT NC.EP-EP.ZZ-0404(Q), Protective Action Recommendations Upgrades, after an initial PAR for a General Emergency has been made.

2.6 NOTIFY corporate management periodically regarding emergency status.

2.7 NOTIFY both State Directors regularly to provide status updates, ensure data flow is satisfactory, obtain information concerning any Protective Actions implemented by the States. (NJ Director - NETS x541 0; DE Director- NETS x5412)

NOTE:

New Jersey has responsibility for notification and communications with the contiguous (ingestion pathway)

States of Pennsylvania and Maryland.

2.8 OBTAIN Ingestion Pathway Actions implemented by all four States from both State Directors. (NJ Director- NETS x5410; DE Director- NETS x5412)

NUCLEAR COMMON Page 19 of 19 Rev 01

PSEG Internal Use Only PAGE I OF I PSE&G NUCLEAR BUSINESS UNIT HC.EP-EP.ZZ-0301 (Q) - REV. 1 SHIFT RADIATION PROTECTION TECHNICIAN RESPONSE USE CATEGORY: II REVISION

SUMMARY

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

PSE&G

2. Corrected typographical error in Attachment I step 1.1.19.

CONTROL COPY #CaeL*..

IMPLEMENTATION REQUIREMENTS:

This procedure is effective for use upon issue.

APPROVED:

'Manager - EP & IT bate APPROVED: - / 1/

Vice President - Operations Date

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

SHIFT RADIATION PROTECTION TECHNICIAN RESPONSE TABLE OF CONTENTS Section Title Page 1.0 P U R P O S E .................................................................................................... 3 2.0 PREREQUISITES ........................................................................................ 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 rocedure .......................................................................................... 3 4.0 EQUIPMENT REQUIRED ........................................................................... 3 5.0 PROCEDURE ............................................................................................. 4 5.1 The SRPT Should ............................................................................. 4 5.2 When the TSC is Activated, Perform the Following ............................ 4 6 .0 R E C O R D S .................................................................................................... 5

7.0 REFERENCES

............................................................................................. 5 7.1 References ......................................................................................... 5 7.2 Cross References ............................................................................... 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 Form 1 - Habitability Log ................................................................................................. 19 Hope Creek Page 1 of 21 Rev. 1

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

FIGURES FIGURE 1 DAPA Correction Figure .......................................................................... 20 FIGURE 1 DAPA Correction Figure ............................................................................ 21 Hope Creek Page 2 of 21 Rev. 1

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. I

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 LAI 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. 1

HC.EP-EP.ZZ-0301 (Q) 6.0 RECORDS Return completed procedure and any information or data thought to be pertinent by the SRPT, to the Manager - EP & IT.

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. 1

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

ATTACHMENT I 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 HC.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.

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

ATTACHMENT 1 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.

Hope Creek Page 7 of 21 Rev. 1

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

ATTACHMENT I 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 X51 11)

"* 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 x1 571 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.

Hope Creek Page 8 of 21 Rev. I

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

ATTACHMENT I 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 ASSIST the OS with completion of Page 2 of the NRC Data Sheet, if asked to.

1.1.17 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).

1.1.18 MAKE appropriate Onsite PARs to the OS or RAC for Onsite locations using Attachment 4, Onsite Protective Action Guidelines.

1.1.19 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) Technical Specification 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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HC.EP-EP.ZZ-0301 (Q)

ATTACHMENT I Page 5 of 5 1.1.20 NOTIFY the RAC and RPS-EXP of changing radiological conditions as determined from step 1.1.19 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.

1.1.21 TREND RMS data utilizing the RM-11 or the VAX LA120.

1.1.22 REFER to Attachment 7, RMS Quick Reference, for information concerning some of the RMS monitors.

1.1.23 REFER to HC.RP-AR.SP-0001(Q), Radiation Monitoring System Alarm Response for more complete information concerning RMS.

1.1.24 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. 1

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

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.OOE+03 NPV cfm 0.OOE+00 4.19E+04 SPV cfmn 0.OOE+00 4.48E+05 HTV cfm O.0OEE+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 I.OOE-08 1.OOE-01 FRVS MID RANGE uCi/cc 1.001E-03 1.00E+02 FRVS HIGH RANGE uCi/cc 1.OOE-01 1.00E+05 FRVS EFFLUENT uCL/sec 0.OOE+00 1.00E+12 NPV PARTICULATE uCi/cc 5.OOE-12 1.OOE-06 NPV IODINE uCi/cc 1.IOE-11 1.1OE-05 NPV LOW RANGE uCi/cc 1.OOE-08 1.OOE- 1 NPV MID RANGE uCi/cc 1.OOE-03 1.00E+02 NPV HIGH RANGE uCi/cc I.OOE-01 1.00E+05 NPV EFFLUENT uCi/cc 5.OOE-12 1.OOE-06 SPV PARTICULATE uCi/cc 5.OOE-12 1.OOE-06 SPV IODINE uCi/cc 1.IOE-11 1.10E-05 SPV LOW RANGE uCi/cc 1.001E-08 1.00E-01 SPV MID RANGE uCi/cc I.OOE-03 1.00E+02 SPV HIGH RANGE uCi/cc 1.OOE-01 1.00E+05 SPV EFFLUENT uCi/cc 5.OOE- 12 1.OOE-06 HTV LOW RANGE uCi/cc I.OOE-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.OOE-01 MSL A mR/hr 1.00E+00 1.00E+06 MSL B mR/hr 1.001E+00 1.00E+06 MSL C mR/hr 1.00E+00 1.00E+06 MSL D mR/hr 1.00E+00 1.00E+06 Hope Creek Page II of 21 Rev. I

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

ATTACHMENT 2 Page 2 of 2 CURRENT RANGE RANGE TITLE READING UNITS (LOW) (HIGH)

MAIN CR mR/hr I.00E-01 1.003E+04 TSC VESTIBULE mR/hr 1.00E-01 1.00E+04 CHEM LAB SAM RM mR/hr 1.OOE-01 1.00E+04 RAD WASTE CR mR/hr 1.OOE-01 1.00E+04 OFFGAS TREAT CR mRihr 1.OOE-01 1.OOE+04 OFFGAS VIAL SS mR/hr 1.00E-01 1.00E+04 RADWASTE SS mR/hr 1.OOE-01 1.00E+04 RX BLDG SS mR/hr 1.00E-01 1.00E+04 OUTSIDE RX BLDG SS mR/hr L.OOE-01 1.00E+04 FRVSV SKID mR/hr 1.00E-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 1.00E-01 1.00E+04 MOTOR EQUIP AIRLOCK mR/hr 1.OOE-01 1.00E+04 OPEN EQUIP HATCH mR/hr 1.OOE-01 1.00E+04 SPENT FP DEMIN EQUIP mR/hr 1.00E-01 1.00E+04 AUX HATCHWAY mR/hr L.OOE-01 1.00E+04 REST MACH SHOP A mR/hr 1.OOE-01 1.00E+04 REST MACH SHOP B mR/hr 1.00E-01 1.001E+04 SPENT FUEL POOL mR/hr I.00E-01 1.00E+04 NEW FUEL A mR/hr 1.OOE-01 1.00E+04 NEW FUEL B mR/hr 1.OOE-01 1.OOE+04 PROCESS MONITORS REFUELING FLR EXH A uCi/cc 1.OOE-06 1.OOE-02 REFUELING FLR EXH B uCi/cc 1.OOE-06 1.001E-02 REFUELING FLR EXH C uCi/cc I.OOE-06 I.OOE-02 REACTOR BLDG EXH A uCi/cc 1.OOE-06 I.OOE-02 REACTOR BLDG EXH B uCi/cc I.OOE-06 1.00E-02 REACTOR BLDG EXH C uCi/cc 1.OOE-06 1.O0E-02 CR VENTILATION C uCi/cc 1.OOE-06 1.OOE-02 CR VENTILATION C I uCi/cc 1.OOE-06  ! .OOE-02 CR VENTILATION D uCi/cc 1.OOE-06 I.OOE-02 CR VENTILATION D1 uCi/cc I.OOE-06 1.OOE-02 COOLING TOWER BLDN uCi/cc 1.OOE-06 I.OOE-02 LIQUID RAD WASTE uCi/cc 1.00E-06 1.OOE-02 OFFGAS A mR/hr 1.00E+00 1.OOE+06 OFFGAS B mR/hr 1.00E+00 1.00E+06 OFFGAS TREAT SYS A cpm 1.00E+0 1 1.00E+06 OFFGAS TREAT SYS B cpm 1.00E+01 1.00E+06 RX BLDG VENT SYS EXH uCi/cc I.OOE-06 1.00E-02 TB BLDG EXH uCi/cc 1.OOE-06 1.OOE-02 TB BLDG COMPART EXH uCi/cc 1.00E-06 1.OOE-02 RADWASTE EXH SYS uCi/cc 1.OOE-06 1.OOE-02 RADWASTE AREA EXH uCi/cc 1.00E-06 1.OOE-02 GAS R/W AREA EXH uCi/cc I.OOE-06 1.OOE-02 Hope Creek Page 12 of 21 Rev. I

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

ATTACHMENT 3 Page 1 OF 1 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 Tech Spec release rate of:

2.42E+05pCi/sec Noble Gas (Salem) 1.20E+04pCi/sec Noble Gas (Hope Creek) 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.

C NINUE IF ABOVE CRITERA IS EXCEEDED 5 miles Evacuate ALL Sectors 0-5 miles ot C ?eEvacuate Downwind +1 sector 5-10 miles Shelter remaining sectors 5-10 miles on Does THYROID CDE DOSE YES THYROID CDE DOSE YES on the SSCL exceed 5000 based on a measured value "mRem at and not on a default NO NO NO RADIOLOGICAL PROTECTIVE ACTION RECOMMENDATION REQUIRED!!

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

ATTACHMENT 3 Page 2 of 2 PROTECTIVE ACTION RECOMMENDATIONS WORKSHEET 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 +/- 3' OF A SECTOR DIVIDING LINE.

10 2810 0790 1010 2590 1910 1690 Hope Creek Page 14 of 21 Rev. 1

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

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 Emergency Procedure NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking, for additional information.

Hope Creek Page 15 of 21 Rev. I

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)

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

ATTACHMENT 7 Page 1 of 2 RMS QUICK REFERENCE Hope Creek NOTE All ARM's in the Reactor Building have maximum ranges of 1.O0E+04 mRPhr, except for the Inner Tip Room Monitor (9RX699). The Inner Tip Room Monitor's maximum range is 1.O0E+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: 1.0OE-01 to 1.OOE+04 mR/hr Hope Creek Page 17 of 21 Rev. I

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

ATTACHMENT 7 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.OQE+00 to 1.O0E+12 uCi/Sec North Plant Vent Effluent (NPV) monitor (9RX590) monitors Offgas and the chemistry lab fume hoods. SPV 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.O0E+00 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: 1.0OE+00 to 1.OOE+12 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.OQE+00 to 2.09E+12 uCi/Sec Hope Creek Page 18 of 21 Rev. 1

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

FORM - 1 Page 1 of I HABITABILITY LOG (FORM- 1)

DATE:

DOSE RATE CONTAMINATION TIME PERFORMEDILOCATION (mR/hr) (CPM) INITIALS

.1. 4- 4

+

4 4 4-4 I. I.

t T 4 t t 4 4 4 4 4 1 1

+ 1 4- 4- +

.4. i- -r

_____________________________________________ .1.

IF other means are used to ensure habitability, THEN list:

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

FIGURE I-I DAPA CORRECTION FIGURE Page 1 of 2 60 50 Shaded Area Indicates Sy

"(7 DAPA Monitor Value at which Alternate Method of Estimate Drywelt Airborne Rad Levels should

0) 40 be used.

0 30 0

20 0~

0 10 240 260 280 300 320 340 Average Drywell Air Temperature (*F)

NOTE:

No Correction to the DAPA Monitor is Required boelow 245° Hope Creek Page 20 of 21 Rev. I

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

FIGURE 1-2 Page 2 of 2 30 25 0

20----

15-I 0~

-o10 4->

5- -

/-

I I 11 111I 240 260 lI 280 300 320 340 Average Drywell Air Temperature (*°F)

NOTE:

No Correction to the DAPA Monitor is Required below p45° Hope Creek Page 21 of 21 Rev. I

PSEG Internal Use Only PAGE I OF I PSEG NUCLEAR NC.EP-EP.ZZ-0302 (Q) - REV. I RADIOLOGICAL ASSESSMENT COORDINATOR RE31PQI.E USE CATEGORY: II F OUL(XU REVISION

SUMMARY

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

2. Attachment 1; added a note after step 1.1.8 to clarify when the official SSCL page 2 should be generated.

3. Attachment 2; added two additional bullets to the note after step 1.1.9 that were inadvertently deleted during the previous revision.

4. Attachment 5; corrected a typographical error where NPV was called SPV.

IMPLEMENTATION REQUIREMENTS This procedure is effective for use upon issue.

APPROVED: L*, ý. C - 3 . u Manager- EP & IT Date

.APPROVED:

Vice President - Operations Date

NC.EP-EP.ZZ-0302 (Q)

RADIOLOGICAL ASSESSMENT COORDINATOR RESPONSE TABLE OF CONTENTS Section Title Page TA BLE O F C O NTENTS ................................................................................... 1 1.0 P U R PO S E .................................................................................................... 2 2.0 PREREQUISITES ........................................................................................ 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 rocedure .......................................................................................... 2 4.0 EQUIPMENT REQUIRED ........................................................................... 2 5.0 P R O C E D U R E ................................................................................................ 3 5.1 The RAC/RPS - Offsite Should Perform the Following: ....................... 3 6.0 R E C O R D S .................................................................................................... 3 7.0 R EFER EN C ES ............................................................................................. 3 7.1 References ......................................................................................... 3 7.2 C ross References ................................................................................ 3 ATTACHMENTS ATTACHMENT 1 - TSC Pre - Activation Checklist ............................................................ 5 ATTACHMENT 2 - RAC Checklist .................................................................................... 7 ATTACHMENT 3 - Onsite Protective Action Guidelines ................................................. 12 ATTACHMENT 4 - TSC Evacuation Checklist ................................................................. 13 ATTACHMENT 5 - RMS Quick Reference ....................................................................... 16 Nuclear Common Page 1 of 19 Rev.1

NC.EP-EP.ZZ-0302 (Q) 1.0 PURPOSE To outline and describe the Radiological Assessment Coordinator's (RAC) duties.

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

• The discretion of the OS

• The discretion of the EDO.

• Upon the manning of the TSC.

3.0 PRECAUTIONS AND LIMITATIONS 4.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure 4.1.1 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.

4.1.2 Approval of the OS is required prior to the issuance of Potassium Iodide (KI) until a qualified RAC assumes his duties. The authority to designate when and who should receive KI shifts from the OS to the RAC for all Onsite Personnel at this time lAW NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking. The duty of authorizing KI cannot be delegated or assumed by any other position.

4.1.3 The Radiation Protection - Offsite (RPS-Offsite) should assume the RAC's duties until relieved by a qualified RAC. Duties the RPS-Offsite CANNOT PERFORM have asterisks next to them.

4.1.4 Medical care takes priority over any radiological conditions, unless the radiological conditions are life threatening.

4.1.5 It is recommended that initials be used in the step performance check offs/sign-offs, instead of checkmarks, if more than one person may implement this procedure.

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

4.0 EQUIPMENT REQUIRED As provided at the Control Point, Control Room, and TSC.

Nuclear Common Page 2 of 19 Rev.1

NC.EP-EP.ZZ-0302 (Q) 5.0 PROCEDURE 5.1 The RACIRPS-Offsite Should Perform the Following:

5.1.1 IF the TSC is not yet activated, THEN IMPLEMENT Attachment 1, TSC Pre - Activation Checklist.

5.1.2 IF the TSC is activated, THEN IMPLEMENT Attachment 2, RAC Checklist.

5.1.3 IF Onsite Protective Actions are necessary, THEN IMPLEMENT Attachment 3, Onsite Protective Action Guidelines.

5.1.4 IF the TSC needs to be evacuated, THEN IMPLEMENT Attachment 4, TSC Evacuation Checklist.

5.1.5 IF information is needed concerning the Hope Creek or Salem Radiological monitoring System, THEN refer to Attachment 5, RMS Quick Reference.

6.0 RECORDS Return completed procedure and any information or data thought to be pertinent by the dose assessor, to the Manager - EP & IT.

7.0 REFERENCES

7.1 References 7.1.1 Roger E. Linnemann, M.D., President of Radiation Management Consultants, Clinical Associate Professor of Radiation Oncology at the University of Pennsylvania School of Medicine.

7.1.2 Nuclear Business Unit Emergency Plan 7.2 Cross References 7.2.1 Nuclear Business Unit Emergency Plan 7.2.2 NC.EP-EP.ZZ-0404(Q) Protective Action Recommendations (PARS)

Upgrades.

7.2.3 NC.EP-EP.ZZ-0304(Q), OSC - Radiation Protection Response.

7.2.4 NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking.

Nuclear Common Page 3 of 19 Rev.1

NC.EP-EP.ZZ-0302 (Q) 7.2.5 NC.EP-EP.ZZ-0309(Q), Dose Assessment.

7.2.6 NC.EP-EP.ZZ-0310(Q), Radiation Protection Supervisor- Offsite and Field Monitoring Team Response.

Nuclear Common Page 4 of 19 Rev.1

NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT I Page I of 2 TSC PRE - ACTIVATION CHECKLIST DATE: / TIME:

1.0 RAC's INITIAL ACTIONS 1.1 Perform the Following:

1.1.1 PERFORM or ASSIGN a Radiation Protection Technician (RPT) to check the dose rates in the TSC.

1.1.2 COMPARE the dose rates with the habitability criteria found in Attachment 3, Onsite Protective Action Guidelines.

1.1.3 IF the evacuation limits found in Attachment 3 are exceeded, THEN refer to Attachment 4, TSC Evacuation, and suggest an alternate TSC location to the EDO.

1.1.4 OBTAIN a briefing from the SRPT concerning the Plant's radiological conditions.

1.1.5 OBTAIN a briefing from the EDO concerning the Plant's Operational condition.

1.1.6 DIRECT the RPS-Offsite to implement NC.EP-EP.ZZ 0310, RPS-Offsite and Field Monitor Team

Response

1.1.7 IF the RPS-Offsite has NOT arrived at the TSC, THEN IMPLEMENT Attachment 1, TSC Pre-activation Checklist, of NC.EP-EP.ZZ-0310, RPS-Offsite and Field Monitor Team Response, until the RPS - Offsite arrives.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT I Page 2 of 2 1.1.8 ENSURE the following tasks are being performed by the RSP Offsite or Radiation Protection Technicians (RPTs).

NOTE The TSC radiological assessment should not be generating the official Page 2 of the Station Status Checklist (SSCL) until the TSC is activated and the SRPT is informed the TSC is activated and the TSC radiological assessment personnel will be taking over the generation of the SSCL, Page2.

"* Page 2 of the Station Status checklist (SSCL) is being generated.

"* A continuous air monitor sampler (AMS III) is set up outside the TSC entrance.

"* That Radiation Protection Emergency Equipment is available and operational in the TSC.

"* ALL persons in the TSC have a TLD, or issue them one.

"* Habitability checks are performed every 30 minutes.

1.1.9 IMPLEMENT Attachment 2, RAC Checklist, upon completion of this Attachment or when the TSC is activated.

• TSC PRE-ACTIVATION CHECKLIST COMPLETED:

(TIME) e TSC ACTIVATED: /

(TIME)

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 2 Page 1 of 5 RAC CHECKLIST DATE: _ I TIME:

1.0 RAC's DUTIES 1.1 Perform the Following:

1.1.1 ENSURE dose rates in the TSC are being check every 30 minutes.

1.1.2 COMPARE the dose rates with the habitability criteria found in Attachment 3, Onsite Protective Action Guidelines.

1.1.3 IF the evacuation limits found in Attachment 3 are exceeded, THEN REFER to Attachment 4, TSC Evacuation, and suggest an alternate TSC location to the EDO.

1.1.4 ADVISE the EDO on all Station, Onsite, and Offsite radiological conditions, when thought appropriate.

1.1.5 DIRECT the RPS-Offsite to continue to implement NC.EP-EP.ZZ 0310, RPS-Offsite and Field Monitor Team Response NOTE Technical Specification Noble Gas Release Rate Limits are:

Hope Creek: 1.2E+04 uCi/Sec.

Salem: 2.42E+05 uCi/Sec.

1.1.6 IF fuel damage has occurred, or thought to have occurred, THEN request Chemistry to put PASS into recirculation and ask that PASS is taken when the Fuels Engineer and Chemistry Supervisor believe it is appropriate.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 2 Page 2 of 5 1.1.7 IF the potential is thought to be high that a Radiological Release above technical specifications, a Chemical Release, or a Gaseous Release may occur, or an actual Radiological Release above technical specifications, Chemical Release, or Gaseous Release is in progress THEN:

"* NOTIFY the EDO.

"* ONLY IF A RADIOLOGICAL RELEASE ABOVE TECHNICAL SPECIFICATIONS IS IN PROGRESS REQUEST the EDO to ask the Control Room to make a page announcement saying, "A Radiological Release Is in Progress."

"* ONLY IF THE POTENTIAL OF A RADIOLOGICAL RELEASE IS THOUGHT TO BE HIGH A. REQUEST the EDO to NOTIFY the Control Room of this.

B. NOTIFY the Control Point, OSC, and EOF of the potential for a Radiological Release is thought to be high.

" NOTIFY the TSS at HOPE CREEK and SALEM to:

A. Place the TSC Emergency Filter Unit in service in the Pressurization Mode for radiological releases.

B. Place the TSC Emergency Filter Unit in service in the Recirculation Mode for chemical or other gaseous releases.

" COORDINATE with the Radiological Support Manager (RSM) the moving of any equipment thought essential from the Security Center and the Process Center,if thought the equipment could be in the path of the Plume.

NOTE All Personnel or vehicles leaving or entering the Owner Controlled Area (OCA) should be coordinated with the Security Liaison and the Radiological Support Manager (RSM), if the EOF is manned or activated.

0 RECOMMEND travel routes Nuclear Common Page 8 of 19 Rev.t

NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 2 Page 3 of 5 NOTE Any Steps with an asterisk (*) next to them may not be delegated to anyone but another qualified RAC.

1.1.8

• REVIEW the appropriate ECG sections and provide the EDO with Event Classification Recommendations, as necessary.

1.1.9

• IMPLEMENT NC.EP-EP.ZZ-404, Protective Action Recommendations (PARS) Upgrades, and provide the EDO with appropriate Radiological PARs, as thought necessary.

NOTE Contamination controls consist of the following:

• No eating, drinking, or smoking.

• Setting up Step Off Pads (SOP).

• Placing Friskers next to SOPs.

• Establish proper postings.

• Preparing electronic dosimetry and/or SRDs for use in the TSC.

• Preparing SRDs for use by people leaving the TSC.

1.1.10 IMPLEMENT Contamination Controls for all onsite Emergency Response Facilities, including the unaffected Plants, if:

"* A radiological release greater than the Noble Gas technical specifications release rate limits is in progress.

" The potential of a radiological release greater than the Noble Gas technical specifications release rate limits to occur is thought high.

"* Normal RCA boundaries have been breached.

"* At the discretion of the RAC.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 2 Page 4 of 5 1.1.11 IF Contamination Controls are Implemented, THEN:

"* NOTIFY the EDO Contamination Controls have been implemented.

" REQUEST the EDO to ask the Control Room to make a page announcement saying, "Contamination Controls are being implemented."

"* NOTIFY the Control Room, Control Point, OSC, and EOF Contamination Controls should be implemented.

1.1.12

• AUTHORIZE issuing KI lAW NC.EP-EP.ZZ-0305(Q)

Potassium Iodine Administration.

NOTE A RPT may be sent to the hospital "after the fact," if waiting for the RPT will delay the departure of the ambulance.

1.1.13 COORDINATE with the Operational Support Center Coordinator (OSCC) the evacuation of injured person(s).

1.1.14 DIRECT a RPT to accompany an injured person if:

"* The person is contaminated.

"* The person is potentially contaminated.

"* A Radiological Release greater than technical specifications limits are in progress.

"* The potential that a Radiological Release greater than technical specifications limits is thought to be high.

1.1.15 INFORM the RSM that an injured person is leaving the Site.

1.1.16 COORDINATE with the OSCC the evacuation of any person(s) receiving an exposure of 5 rem External Dose Equivalent (EDE) or greater to an appropriate medical facility, as soon as practical.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 2 Page 5 of 5 1.1.17 INTERFACE directly with the NRC on specific radiological issues, as the need arises.

1.1.18 ARRANGE with the Administrative Support Supervisor for relief shifts of RPTs and Chemistry Technicians.

1.1.19 RECOMMEND expenditures for additional radiological support equipment/staff, as necessary.

1.1.20 REFER to Step 1.1 of this Attachment and follow appropriate Steps until relieved from your duties by a qualified RAC.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 3 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 lodine-131 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.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 4 Page 1 of 3 TSC EVACUATION CHECKLIST Date/Time: -

1.0 TSC EVACUATION CHECKLIST 1.1 Evacuate the TSC in the Following Manner:

NOTE Consideration should be given to dose rates in alternate TSC prior to evacuation. Multiple evacuations are to be avoided.

1.1.1 CONSIDER where to relocate the TSC using the locations below:

"* Hope Creek TSC for Salem

"* Salem TSC for Hope Creek

"* EOF (TSC Technical Staff only)

"* Operations Support Center

"* Security Center

"* Administration Building 1.1.2 RECOMMEND the EDO of your selection.

1.1.3 Notify the RPS-EXP and the Shift Radiation Protection Technician of the evacuation of the TSC and the location of the new TSC.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 4 Page 2 of 3 1.1.4 DIRECT the following items be relocated to the new TSC, if thought appropriate:

"* Log books

"* Calculators

"* Maps

"* Portable computer software

"* Portable radios

"* Radiation instruments, dosimetry, stanchions, etc.

"* Emergency Plan Implementing Procedures

• Controlled Copy Books

• Working Copy Files

"* Event Classification Guidelines

• Controlled Copy Books

• Working Copy Files

"* Station Procedures 1.1.5 DIRECT the use of protective clothing, if radiological conditions are unknown enroute to the new location.

1.1.6 DIRECT the use of dose rate instruments during the relocation of the TSC.

1.1.7 DIRECT personnel to be surveyed for contamination prior to admittance to the new TSC, if practical.

1.1.8 INFORM Security, the Control Room, Control Point, OSC, and EOF (if manned or activated) of the new location and phone numbers.

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 4 Page 3 of 3 1.1.9 NOTIFY the Administrative Support Supervisor, if any additional resources or personnel are required due to the evacuation.

1.1.10 IMPLEMENT Attachment 1, TSC Activation Checklist, and ensure the new TSC is ready to assume its responsibilities.

Completed by: /

(PRINT/SIGNATURE)

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 5 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.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.OOE-01 to 1.OOE+04 mR/hr Nuclear Common Page 16 of 19 Rev.1

NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 5 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+12 uCi/Sec (THIS ISA 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+1 2 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.OOE+00 to 2.09E+12 uCi/Sec (THIS IS A 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: 1E-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.

R10A is an ARM located in Containment on the 100' elevation next to the personnel airlock.

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

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 5 Page 3 of 4 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 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 RI OA and R7 ARMs.

Ranges: 1E+00 to 1 E+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).

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NC.EP-EP.ZZ-0302 (Q)

ATTACHMENT 5 Page 4 of 4 R41 B 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(THIS ISA 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 1E+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 1E+01 uCi/cc (THIS IS A 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 1 E+05 uCi/cc (THIS IS A GROUND RELEASE AT ALL TIMES).

Nuclear Common Page 19 of 19 Rev.1

PSEG Internal Use Only PSEG NUCLEAR Page I of 1 NC.EP-EP.ZZ-0310 (Q) Rev. 1 RADIATION PROTECTION SUPERVISOR - OFFSITE AND FIELD MONITORING TEAM RESPONSE USE CATEGORY: I-REVISION

SUMMARY

CONTROL

1. This revision satisfies the requirement for a biennial review. Ury -g IPO

2. Attachment 1; fixed typographical error in step 1.1.3.

3. Attachment 1; added a note after step 1.1.7 to clarify when the official SSCL page 2 should be generated.

4. Attachment 2; added step 1.1.5 that was inadvertently deleted during the previous revision.

5. Attachment 5; fixed typographical error in step 1.1.4.

IMPLEMENTATION REQUIREMENTS Issued for use.

APPROVED:_

MVlanager - EP & IT Dafte APPROVED: I --

Vice President - Operations Date

NC.EP-EP.ZZ-0310 (Q)

RADIATION PROTECTION SUPERVISOR - OFFSITE AND FIELD MONITORING TEAM RESPONSE TABLE OF CONTENTS Section Title Page 1.0 P UR P O S E .................................................................................................... 3 2.0 PREREQUISITES ........................................................................................ 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 rocedure ........................................................................................ . 3 4.0 EQUIPMENT REQUIRED ........................................................................... 3 5.0 PR O C ED UR E ............................................................................................. 4 5.1 The RPS - Offsite Should ................................................................... 4 5.2 The Radiation Protection (RPT - Radio) Should ................................ 4 5.3 The Onsite Field Monitoring Team Should ........................................ 4 6.0 R EC O R D S .................................................................................................... 4 7.0 R E FER E NC ES ............................................................................................. 4 7.1 R eferences ....................................................................................... 4 7.2 Cross References .............................................................................. 5 ATTACHMENTS ATTACHMENT 1 - TSC Pre-activation Checklist ............................................................... 6 ATTACHMENT 2 - RPS-Offsite Checklist .......................................................................... 8 ATTACHMENT 3 - Field Monitoring Team Briefing Guidance ........................................ 12 ATTACHMENT 4 - Onsite Field Monitoring Equipment Checklist .................................... 13 ATTACHMENT 5 - Field Monitoring Team Log ................................................................. 15 ATTACHMENT 6 - Particulate Air Activity vs. Count Rate Table ...................................... 19 ATTACHMENT 7 - Particulate Air Activity vs. Dose Rate Table ...................................... 20 ATTACHMENT 8 - Direct Conversion Table Of Corrected Counts Per Minute To uCI/CC 1-13 1 ............................................................................................... . . 21 ATTACHMENT 9 - Field Monitoring Team Responsibilities and Directions ..................... 22 ATTACHMENT 10 - Onsite Protective Action Guidelines ............................................... 25 ATTACHMENT 11 - Onsite Emergency Monitoring Locations ......................................... 26 ATTACHMENT 12 - Offsite Emergency Monitoring Locations ......................................... 29 Nuclear Common Page 1 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 13 - DAPA Correction Calculations ........................................................ 46 ATTACHMENT 14 - Package Insert For Thyro-Block Tablets ........................................ 47 ATTACHMENT 15 - Operation Of The VAX LA120 Terminal .......................................... 48 ATTACHMENT 16 - Instructions For Salem SPDS Displays ........................................... 51 FORMS Form - 1 Field Sampling Form .................................................................................. 54 Form - 2 D osim etry Log ............................................................................................. 55 Form - 3 KI Side Effects/Administration Sign Off Form ............................................. 56 Form - 4 Field Monitoring Team Briefing Form ....................................................... 58 Form - 5 TLD Issue Log ........................................................................................... 61 Form - 6 Habitability Log ........................................................................................... 62 Form - 7 SPDS RMS Log (Salem Only) ................................................................... 63 FIGURES FIGURE 1 - 1 DAPA Monitor Reading vs Average Drywell Air Temperature ...... 64 FIGURE 1 - 2 DAPA Monitor reading Bias vs Average Drywell Air Temperature ....... 65 Nuclear Common Page 2 of 65 Revl

NC.EP-EP.ZZ-0310 (Q) 1.0 PURPOSE To outline and describe the Radiation Protection Supervisor - Offsite (RPT - Offsite) duties.

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

"* The discretion of the EDO

"* The discretion of the RAC.

"* Upon the manning of the TSC.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure 3.1.1 The order of the steps listed in this procedure may be performed in the order deemed approriate by the Radiation Protection Supervisor Offsite.

3.1.2 Approval of the OS is required prior to the issuance of Potassium Iodide (KI) until a qualified Radiological Assessment Coordinator (RAC) assumes his duties. The authority to designate when and who should receive KI shifts from the OS to the RAC for all Onsite Personnel lAW NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking. The duty of authorizing KI can not be delegated or assumed by any other position.

3.1.3 The RPS-Offsite should assume the RAC's duties until relieved by a qualified RAC by referring to NC.EP-EP.ZZ-0302(Q), Radiological Assessment Coordinator Response.

3.1.4 Medical care takes priority over any radiological conditions, unless the radiological conditions are life threatening.

3.1.5 It is recommended that initials be used in the step performance check offs/sign-offs, instead of checkmarks, if more than one person may implement this procedure.

3.1.6 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.

Nuclear Common Page 3 of 65 Revl

NC.EP-EP.ZZ-0310 (Q) 5.0 PROCEDURE 5.1 The RPS-Offsite Should:

5.1.1 IF the RAC has not arrived at the TSC, THEN ASSUME the RAC's duties until he/she arrives by implementing NC.EP EP.ZZ-0302(Q), Radiological Assessment Coordinator Response.

NOTE The RPS-Offsite reports directly to the RAC.

5.1.2 ASSUME his/her own duties when a qualified RAC assumes his/her own duties by implementing Attachment 1, TSC Pre activation Checklist, of this procedure, unless directed otherwise by the RAC.

5.2 The Radiation Protection - Radio (RPT-Radio) Should:

Assume his/her duties lAW Attachment 5, Field Monitoring Team Log.

5.3 The Onsite Field Monitoring Team(s) Should:

Assume his/her duties lAW Attachment 9, Field Monitoring Team Responsibilities and Directions.

6.0 RECORDS Return completed procedure and any information or data thought to be to the Manager - EP & IT.

7.0 REFERENCES

7.1 References 7.1.1 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

7.1.2 NUREG/CR-0314, An Air Sampling System for Evaluating Thyroid Dose Commitment Due to Fission Products Released for Reactor Containments.

7.1.3 Radiological Health Handbook (Revised Edition January 1970)

Nuclear Common Page 4 of 65 Revl

NC.EP-EP.ZZ-0310 (Q) 7.1.4 Nuclear Business Unit Emergency Plan 7.2 Cross References NC.EP-EP.ZZ-0302(Q), Radiological Assessment Coordinator Response Nuclear Common Page 5 of 65 Rev~l

NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT I Page 1 of 2 TSC PRE -ACTIVATION CHECKLIST DATE: I TIME:

1.0 RPS - OFFSITE INITIAL ACTIONS 1.1 Perform the Followina:

1.1.1 PERFORM or ASSIGN a Radiation Protection Technician (RPT) to check the dose rates in the TSC.

1.1.2 COMPARE the dose rates with the habitability criteria found in Attachment 10, Onsite Protective Action Guidelines.

1.1.3 IF the evacuation limits found in Attachment 10 are exceeded, THEN notify the RAC and refer him to Attachment 4, TSC Evacuation Checklist, found in NC.EP-EP.ZZ-0302(Q).

1.1.4 OBTAIN a briefing from the SRPT concerning the Plant's radiological conditions and when the next SSCL Page 2 is due. (TIME: )

1.1.5 OBTAIN a briefing from the RAC (or the EDO if the RAC is not available) concerning the Plant's Operational condition.

NOTE An inventory of the TSC Emergency Equipment Locker is not necessary if the security seal is intact.

Refer to EP Administration Procedure 1006, Emergency Equipment Inventory Rad Pro Equipment Checklist, if an inventory is necessary.

1.1.6 ENSURE the TSC emergency equipment is available and In operational condition.

Nuclear Common Page 6 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT I Page 2 of 2 1.1.7 ENSURE the following tasks are being performed by Radiation Protection Technicians (RPTs) or perform yourself :

NOTE The TSC radiological assessment should not be generating the official Page 2 of the Station Status Checklist (SSCL) until the TSC is activated and the SRPT is informed the TSC is activated and the TSC radiological assessment personnel will be taking over the generation of the SSCL, Page2.

" Page 2 of the SSCL is being generated in preperartion of taking this function over.

" A continuous air monitor sampler (AMS Ill) is set up outside the TSC entrance.

"* That Radiation Protection Emergency Equipment is available and operational in the TSC.

"* ALL persons in the TSC have a TLD, or issue them one lAW Form - 5, TLD Log.

". Habitability checks are performed every 30 minutes and log the results on Form - 6.

1.1.8 NOTIFY the RAC (or EDO if the RAC is not available) when this attachment is completed.

TSC PRE-ACTIVATION CHECKLIST COMPLETED:

(TIME)

TSC ACTIVATED:

(TIME)

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NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 2 Page 1 of 4 RPS-OFFSITE CHECKLIST "NOTE The order that these steps are to be performed is at the RPS-Offsite's discreti delegated.

Name: / Date/Time: - /

(Print/Sign) 1.0 RPS-OFFSITE 1.1 Should Perform The Following:

1.1.1 INITIATE a RPS-Offsite log book 1.1.2 INFORM the RAC of all changing radiological conditions.

NOTE The keys for the Emergency Preparedness Van are located in the TSC lock box and at the Control Point key box.

1.1.3 CONTACT a Radiation Protection Technician at the Control Point and ask for the location of the Emergency Preparedness Van.

1.1.4 INSTRUCT a RPT to obtain current meteorological data utilizing Attachment 15, Operation of the VAX LA120 Terminal.

1.1.5 INSTRUCT an RPT to obtain the meteorological forecast by calling NOAA at (automative system - 609-261-6600; options 1 & than 2) (to speak to meteorologist at Mount Holly - 609 261-6604) or by using the internet.

1.1.6 INSTRUCT a RPT to obtain current RMS data utilizing (HOPE CREEK ONLY) Attachment 15, Operation of the VAX LA120 Terminal or (SALEM ONLY) Attachment 16 Instructions for SPDS 1.1.7 REQUEST the RAC to assign personnel for Onsite/Offsite Field Monitoring Team members as the need arises.

1.1.8 INSTRUCT the Onsite Field Monitoring Team members to implemented Attachment 4, Onsite Field Monitoring Equipment Checklist.

1.1.9 INSTRUCT the Offsite Field Monitoring Team members to implemented Attachment 3 of NC.EP-EP.ZZ-0603(Q).

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ATTACHMENT 2 Page 2 of 4 1.1.10 DIRECT Onsite Field Team Members to replace missing or out of service items by asking an RPT or SRPT for necessary items to complete the Onsite Field Monitoring Team kit.

1.1.11 DIRECT Offsite Field Team Members to replace missing or out of service items by taking necessary items to complete the Offsite Field Monitoring Team kit from the spare supplies.

NOTE Offsite Field Monitoring Team members may obtain a briefing via radio or telephone for early dispatching from the RPS-Offsite.

1.1.12 PROVIDE a briefing to the Onsite/Offsite Field Monitoring Team members lAW Form - 4, Field Monitoring Team Briefing Form, following the guidance found in Attachment 3, Field Monitoring Team Briefing Guidance.

1.1.13 ASSIGN a color code name for Onsite Field Monitoring Teams, such as Red Team, Blue Team, Green Team, etc.

1.1.14 ASSIGN a phonetic alphabet name for Offsite Teams, such as Alpha Team, Bravo Team, etc.

1.1.15 INSTRUCT the Onsite Field Monitoring Teams to read Attachment 14, Package Insert for Thyro-Block Tablets.

1.1.16 INSTRUCT the Onsite Field Monitoring Teams to signed on the appropriate location of Form - 3, KI Side Effects/Administrative Signoff Form.

1.1.17 INSTRUCT the Offsite Field Monitoring Teams to read Attachment 10, Package Insert for Thyro-Block Tablets. found in NC.EP-EP.ZZ 0603(Q).

1.1.18 INSTRUCT the Offsite Field Monitoring Teams to signed on the appropriate location of Form - 5, Side Effects/Administrative Signoff Form, found in NC.EP-EP.ZZ-0603(Q).

1.1.19 ENSURE the Onsite/Offsite Field Monitoring Teams have received a copy of the briefing forms.

1.1.20 INSTRUCT the Onsite Field Monitoring Teams to implement Attachment 9, Field Monitoring Team Responsibilities and Directions.

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ATTACHMENT 2 Page 3 of 4 1.1.21 INSTRUCT the Offsite Field Monitoring Teams have implemented Attachment 8, Field Monitoring Team Responsibilities and Directions found in NC.EP-EP.ZZ-0603(Q).

1.1.22 ASSIGN a RPT to be the RPT-Radio.

1.1.23 INSTRUCT the RPT-Radio to implement Attachment 5, Field Monitoring Team Log 1.1.24 INSTRUCT the Onsite Field Monitoring Team(s) use frequency 1.

1.1.25 INSTRUCT the Offsite Field Monitoring Team(s) use frequency 4.

1.1.26 INSTRUCT the RPT-Radio to perform a radio check with all appropriate Field Teams 1.1.27 DIRECT Field Monitoring Teams to take direction from the RPT-Radio concerning which monitoring locations to travel to and what samples to obtain.

1.1.28 PROVIDE the RPT - Radio instructions concerning where the Field Monitoring Teams should travel to and what type samples to take.

1.1.29 REVIEW RPT-Radio's paperwork for completeness and correctness of data being recorded.

NOTE

a. The HOPE CREEK Noble Gas (NG) Technical Specification limit is 1.20E+04 uCi/sec.

b. The SALEM Noble Gas (NG) Technical Specification limit is 2.42E+05 uCi/Sec.

c. Alnors or equivalent electronic dosimetry may be used in lieu of SRDs.

1.1.30 ENSURE preparation is ongoing to log and handout Self Reading Dosimeters (SRDs), or electronic equivalent dosimetry, to personnel using Form - 2, Dosimetry Log, if:

Release greater than NG Technical Specification Limits is in progress.

"* Potential of a release greater then NG Technical Specification Limits is thought to be high.

"* Dose rates in the TSC are > 2.5 mR/hr.

"* At the discretion of the RAC.

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ATTACHMENT 2 Page 4 of 4 1.1.31 ENSURE habitability is continuing to be performed every 30 minutes and record on Form - 6, Habitability Log.

1.1.32 PROVIDE guidance to the Onsite/Offsite Field Monitoring Teams concerning how to handle survey equipment that is contaminated with 50k ccpm. (Consideration should be given to changing out or bagging survey equipment).

1.1.33 DETERMINE if issuance of KI is necessary for Field Monitoring Team Members by referring to NC.EP-EP.ZZ-0305(Q), Stable Iodine Thyroid Blocking, and inform the RAC, as appropriate.

1.1.34 RECALL Onsite/Offsite Field Monitoring Teams, as necessary, and debrief.

1.1.35 ENSURE all completed forms are forwarded to the Manager - CA, EP, & IT. Attach any referenced EPEPs or Attachments.

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ATTACHMENT 3 Page 1 of I FIELD MONITORING TEAM BRIEFING GUIDANCE 1.0 BRIEFING GUIDANCE FOR ONSITE AND OFFSITE FIELD TEAMS NOTE This briefing may take place over the radio or cellular phone.

1.1 At A Minimum, The Following Items Should Be Included In The Briefing, and As Appropriate, Recorded On Form - 4, Field Monitoring Team Briefing Form:

1.1.1 ENSURE radio protocol is conducted in the following manner:

"* Repeat backs (Three Way Communications)

"* Use of the proper phonetic alphabet, when appropriate. (A-Alpha, B-Bravo, etc.)

1.1.2 REVIEW Form - 3, KI Side Effects/Administration Sign Off Form, to ensure it is filled out properly and signed.

1.1.3 FOLLOW the provisions for gas, tolls, and meals listed below, as may be appropriate:

" Pay tolls out of the Field Teams own money and submitted for reimbursement through EOF Admin Support Staff.

"* Pay, or Charge on Corporate American Express card, meals and gas and then submitted for reimbursement.

1.1.4 PROVIDE current meteorological conditions and forecast.

1.1.5 PROVIDE phone number to contact the TSC/EOF. This can't be a NETS phone.

1.1.6 USE Frequency 4 to contact the EOF for the Offsite Field Monitoring Team.

1.1.7 USE Frequency 1 to contact the TSC or the Onsite Field Monitoring Team.

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ATTACHMENT 4 Page 1 of 2 ONSITE FIELD MONITORING EQUIPMENT CHECKLIST NOTE

"* An inventory of the Onsite Field Monitoring Team Kits is not necessary, if they are properly sealed.

"* Emergency Preparedness Procedure 1006, Emergency Equipment Inventory (Radiation Protection) should be referred to, to perform an inventory of the Emergency Locker, if necessary.

", The Forms Kit is stored in the RPS-Offsite work area.

"* Lead blankets are stored adjacent to kits.

"* This checklist is to be used to help ensure needed items are not left behind while loading the emergency vehicle. It is not to be used instead of the Emergency Preparedness Procedure 1006.

1. Low Volume Air Samples: Radeco H809C with battery cable and two air sample heads, or a battery operated Radeco with two air sample heads

2. One Count Rate Meter: E140N with a HP210 probe or equivalent meter and probe.

3. One Ion Chamber Dose Rate Meter: RO-2 or RO-2A or equivalent meter.

4. One Teletector or equivalent meter.

5. One GM meter: E520 with a HP177C or 270 probe or equivalent meter and probe.

6. Hi Range Dosimeters (0-5 R or 0-10 R) or electronic equivalent.

7. Low Range Dosimeters (0-200 mR or 0-500mR) or electronic equivalent.

8. One Dosimeter Charger.

9. Absorbent Material.

10. One Ten Mile (EPZ) N.J. and Delaware Map.

NOTE The Forms Kit contains the Onsite Map, NC.EP-EP ZZ-0310(Q), and additional attachments from NC.EP-EP ZZ-0310(Q).

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ATTACHMENT 4 Page 2 of 2

11. One Onsite Map.

12. One Pair of Tweezers.

13. One Button Check Source.

14. Silver Zeolite Cartridges.

15. Box of Air Sample Filters.

16. Box of Smear Papers.

17. Protective Clothing/Paper Coveralls.

18. Shoe Covers.

19. Gloves.

20. Small Envelopes for Particulate Air Sample Filters.

21. Roll of Masking Tape.

22. Small Plastic Bags.

23. Flashlight.

24. Spare Nine Volt Batteries

25. Spare D Cell Batteries.

26. One Bottle of KI Tablets.

27. One First Aid Kit.

28. Respirators.

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ATTACHMENT 5 Page 1 of 4 FIELD MONITORING TEAM LOG 1.0 OPERATING INSTRUCTIONS FOR TSC RAD ASSESSMENT RADIO BASE STATION 1.1 The RPT Radio operator Should Perform The Following:

1.1.1 REQUEST Security Liaison to have Security Force Members to switch over to frequency F2.

1.1.2 TURN on the radio power switch. The power switch is located on the top of the radio.

1.1.3 DEPRESS the F1 button located on the top of the radio to communicate with the Onsite Field Monitoring Teams or F4 to communicate with the Offsite Field Monitoring Teams.

1.1.4 POSITION the toggle switch on the left side of the radio to the forward position (on) to use the speaker or to the back position (off) to use the headset.

1.1.5 DEPRESS the button on the headset cord to transmit, if headset is in use.

1.1.6 DEPRESS the transmit bar on microphone to transmit, if headset is not in use.

NOTE Use this Attachment to assist in performing necessary calculations and document briefing updates.

• Onsite Field Monitoring Team's dose should be tracked on Form - 2, Dosimetry Log.

2.0 ONSITE DATA 2.1 The RPT - Radio Operator OR Designee Should Record The Following, As Applicable:

2.1.1 RPT- Radio: Name: Date:

2.1.2 Team Color Code: Time:

2.1.3 Location :

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ATTACHMENT 5 Page 2 of 4 2.1.4 Instrument Type/Serial Number: J 2.1.5 General Area Open Window Dose Rate: mR/hr 2.1.6 General Area Closed Window Dose Rate: mRlhr 2.1.7 Ground Open Window Dose Rate: _mR/hr 2.1.8 Ground Closed Window Dose Rate:*mR/hr 2.1.9 Time On For A/S : Time Off For A/S_*

2.1.10 Average Flow Rate *_cfm 2.1.11 Particulate Background

• _ cpm 2.1.12 Particulate Sample: _cpm 2.1.13 Iodine Background *_cpm 2.1.14 Iodine Sample:*cpm 2.1.15 Refer to section 3.0 for offsite data that should be obtained.

2.1.16 Refer to section 5.0 for onsite data calculations.

NOTE Offsite Field Monitoring Team's dose should be tracked on Form - 2, Dosimetry Log, as necessary. Turn over tracking of Offsite Field Monitoring Team's dose to Field Team Communicator upon EOF activation.

3.0 OFFSITE DATA 3.1 The RPT - Radio Operator OR Designee Should Record The Following, If Applicable:

3.1.1 Team Phonetic Alphabet Name: Time:

3.1.2 Location":

3.1.3 Instrument Type/Serial Number: / /

3.1.4 General Area Open Window Dose Rate:*mR/hr 3.1.5 General Area Closed Window Dose Rate:*mR/hr 3.1.6 Ground Open Window Dose Rate: _mR/hr 3.1.7 Ground Closed Window Dose Rate:*mR/hr 3.1.8 Time On For A/S : Time Off For A/S

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ATTACHMENT 5 Page 3 of 4 3.1.9 Average Flow Rate: cfm 3.1.10 Particulate

Background:

cpm 3.1.11 Particulate Sample: cpm 3.1.12 Iodine

Background:

.cpm 3.1.13 Iodine Sample: .cpm 3.1.14 Refer to section 6.0 for offsite data calculations.

4.0 BRIEFING UPDATE 4.1 The RPT - Radio Operator OR Designee Should Record The Following:

4.1.1 Time: Event Classification :

4.1.2 Plant Conditions:

4.1.3 Radiological Conditions:

4.1.4 Additional Information Communicated to Offsite Team (Attach additional pages as necessary):

5.0 ONSITE CALCULATIONS 5.1 The RPT - Radio Operator OR Designee Should Record The Following:

5.1.1 Person Performing Calculations: / Date:

(Print/Sign) 5.1.2 Go to Section 2.0 of Attachment 5 for data to perform calculations.

5.1.3 Subtract 2.1.6 _ from 2.1.5 __ and Multiply that value by the beta correction factor of 5 for the mRad/hr: mRad/hr.

(Gen. Area) 5.1.4 Subtract 2.1.8. __ from 2.1.7 __ and multiply that value by the beta correction factor of 5 for the mRad/Hr.

mRad/hr. (Ground)

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ATTACHMENT 5 Page 4 of 4 5.1.5 Subtract 2.1.11 _ from 2.1.12 _ for the corrected counts per minute (ccpm) for particulate samples : ccpm.

5.1.6 Calculate the particulate uCi/cc lAW Attachment 6, Air Activity vs. Count Rate Table, or lAW Attachment 7, Air Activity vs. Dose Rate Table, uCi/cc.

5.1.7 Subtract 2.1.13 from 2.1.14 for the corrected counts per minute (ccpm) for iodine samples: ccpm.

5.1.8 Calculate the iodine uCi/cc IAW Attachment 8, Direct Conversion Per Minute to uCi/cc for 1-131 : uCi/cc.

6.0 OFFSITE CALCULATIONS 6.1 The RPT - Radio Operator OR Designee Should Record The Following:

6.1.1 Person Performing Calculations: Date:

(Print/Sign) 6.1.2 Go to section 3.0 of Attachment 5 for data to perform calculations.

6.1.3 Subtract 3.1.5. _from 3.1.4 __ and Multiply that value by the beta correction factor of 5 for the mRad/hr: mRad/hr.

(Gen. Area) 6.1.4 Subtract 3.1.7 _ from 3.1.6 _ and multiply that value by the beta correction factor of 5 for the mRad/hr. mRad/hr.

(Ground) 6.1.5 Subtract 3.1.10 __ from 3.1.11 _ for the corrected counts per minute (ccpm) for particulate samples : ccpm.

6.1.6 Calculate the particulate uCi/cc lAW Attachment 6, Air Activity vs. Count Rate Table, or lAW Attachment 7, Air Activity vs. Dose Rate Table, uCi/cc.

6.1.7 Subtract 3.1.12 from 3.1.13 __ for the corrected counts per minute (ccpm) for iodine samples: ccpm.

6.1.8 Calculate the iodine uCi/cc lAW Attachment 8, Direct Conversion Per Minute to uCi/cc for 1-131 : uCi/cc.

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ATTACHMENT 6 Page 1 of I PARTICULATE AIR ACTIVITY VS. COUNT RATE TABLE SAMPLE SAMPLE SAMPLE SAMPLE SAMPLE SAMPLE VOLUME VOLUME VOLUME VOLUME VOLUME VOLUME 5 10 15 20 25 30 CORRECTED (CUBIC (CUBIC (CUBIC (CUBIC (CUBIC (CUBIC CPM FT.) FT.) FT.) FT.) FT.) FT.)

(ccpm) (uCi/cc) (uCi/cc) (uCilcc) (uCi/cc) (uCilcc) (uCiicc) 5.OOE+04 1.59E-06 7.95E-07 5.30E-07 3.97E-07 3.18E-07 2.65E-07 4.50E+04 1.43E-06 7.15E-07 4.77E-07 3.57E-07 2.86E-07 2.38E-07 4.OOE+04 1.27E-06 6.35E-07 4.23E-07 3.17E-07 2.54E-07 2.12E-07 3.50E+04 1.11E-06 5.55E-07 3.70E-07 2.77E-07 2.22E-07 1.85E-07 3.O0E+04 9.53E-07 4.76E-07 3.18E-07 2.38E-07 1.91 E-07 1.59E-07 2.50E+04 7.94E-07 3.97E-07 2.65E-07 1.98E-07 1.59E-07 1.32E-07 2.OOE+04 6.35E-07 3.17E-07 2.12E-07 1.59E-07 1.27E-07 1.06E-07 1.50E+04 4.77E-07 2.38E-07 1.59E-07 1.19E-07 9.54E-08 7.95E-08 1.OOE+04 3.18E-07 1.59E-07 1.06E-07 7.95E-08 6.36E-08 5.30E-08 9.OOE+03 2.86E-07 1.43E-07 9.53E-08 7.15E-08 5.72E-08 4.77E-08 8.OOE+03 2.54E-07 1.27E-07 8.47E-08 6.35E-08 5.08E-08 4.23E-08 7.OOE+03 2.22E-07 1.11E-07 7.40E-08 5.55E-08 4.44E-08 3.70E-08 6.OOE+03 1.91E-07 9.55E-08 6.37E-08 4.77E-08 3.82E-08 3.18E-08 5.OOE+03 1.59E-07 7.95E-08 5.30E-08 3.97E-08 3.18E-08 2.65E-08 4.OO E+03 1.27E-07 6.35E-08 4.23E-08 3.17E-08 2.54E-08 2.12E-08 3.OOE+03 9.53E-08 4.76E-08 3.18E-08 2.38E-08 1.91 E-08 1.59E-08 2.OOE+03 6.35E-08 3.17E-08 2.12E-08 1.59E-08 1.27E-08 1.06E-08 1.OOE+03 3.18E-08 1.59E-08 1.06E-08 7.95E-09 6.39E-09 5.30E-09 9.OOE+02 2.86E-08 1.43E-08 9.53E-09 7.15E-09 5.72E-09 4.77E-09 8.OOE+02 2.54E-08 1.27E-08 8.47E-09 6.35E-09 5.08E-09 4.23E-09 7.O0E+02 2.22E-08 1.11E-08 7.40E-09 5.55E-09 4.44E-09 3.70E-09 6.OOE+02 1.91E-08 9.55E-09 6.37E-09 4.77E-09 3.82E-09 3.18E-09 5.OOE+02 1.59E-08 7.95E-09 5.30E-09 3.97E-09 3.18E-09 2.65E-09 4.OOE+02 1.27E-08 6.35E-09 4.23E-09 3.17E-09 2.54E-09 2.12E-09 3.OOE+02 9.53E-09 4.76E-09 3.18E-09 2.38E-09 1.91E-09 1.59E-09 2.OOE+02 6.35E-09 3.17E-09 2.12E-09 1.59E-09 1.27E-09 1.06E-09 1.OOE+02 3.18E-09 1.59E-09 1.06E-09 7.95E-10 6.36E-10 5.30E-10 Calculation Based on: uCi/cc ccpm

• 4.5E-07 uCi/dpM VOL (FT 3)

• 2.832E+4 (CC/FTr)

• EFF (0.10)

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ATTACHMENT 7 Page 1 of I PARTICULATE AIR ACTIVITY VS. DOSE RATE TABLE SAMPLE SAMPLE SAMPLE SAMPLE SAMPLE SAMPLE VOLUME VOLUME VOLUME VOLUME VOLUME VOLUME 5 10 15 20 25 30 (CUBIC (CUBIC (CUBIC (CUBIC (CUBIC (CUBIC FT.) FT.) FT.) FT.) FT.) FT.)

(mRad/hr) (uCilcc) (uCi/cc) (uCilcc) (uCiicc) (uCilcc) (uCiicc) 1.OOE+03 1.59E-06 7.95E-07 5.30E-07 3.97E-07 3.18E-07 2.65E-07 5.OOE+02 1.43E-06 7.15E-07 4.77E-07 3.57E-07 2.86E-07 2.38E-07 1.OOE+02 1.27E-06 6.35E-07 4.23E-07 3.17E-07 2.54E-07 2.12E-07 9.50E+01 1.11E-06 5.55E-07 3.70E-07 2.77E-07 2.22E-07 1.85E-07 9.OOE+01 9.53E-07 4.76E-07 3.18E-07 2.38E-07 1.91 E-07 1.59E-07 8.50E+01 7.94E-07 3.97E-07 2.65E-07 1.98E-07 1.59E-07 1.32E-07 8.OOE+01 6.35E-07 3.17E-07 2.12E-07 1.59E-07 1.27E-07 1.06E-07 7.50E+01 4.77E-07 2.38E-07 1.59E-07 1.19E-07 9.54E-08 7.95E-08 7.OOE+01 3.18E-07 1.59E-07 1.06E-07 7.95E-08 6.36E-08 5.30E-08 6.50E+01 2.86E-07 1.43E-07 9.53E-08 7.15E-08 5.72E-08 4.77E-08 6.00E+01 2.54E-07 1.27E-07 8.47E-08 6.35E-08 5.08E-08 4.23E-08 5.50E+01 2.22E-07 1.11E-07 7.40E-08 5.55E-08 4.44E-08 3.70E-08 5.OOE+01 1.91E-07 9.55E-08 6.37E-08 4.77E-08 3.82E-08 3.18E-08 4.50E+01 1.59E-07 7.95E-08 5.30E-08 3.97E-08 3.18E-08 2.65E-08 4.OOE+01 1.27E-07 6.35E-08 4.23E-08 3.17E-08 2.54E-08 2.12E-08 3.50E+01 9.53E-08 4.76E-08 3.18E-08 2.38E-08 1.91 E-08 1.59E-08 3.OOE+01 6.35E-08 3.17E-08 2.12E-08 1.59E-08 1.27E-08 1.06E-08 2.50E+01 3.18E-08 1.59E-08 1.06E-08 7.95E-09 6.39E-09 5.30E-09 2.00E+01 2.86E-08 1.43E-08 9.53E-09 7.15E-09 5.72E-09 4.77E-09 1.50E+01 2.54E-08 1.27E-08 8.47E-09 6.35E-09 5.08E-09 4.23E-09 1.OOE+01 2.22E-08 1.11E-08 7.40E-09 5.55E-09 4.44E-09 3.70E-09 5.OOE+00 1.91E-08 9.55E-09 6.37E-09 4.77E-09 3.82E-09 3.18E-09 1.O0E+00 1.59E-08 7.95E-09 5.30E-09 3.97E-09 3.18E-09 2.65E-09 Calculation Based on:

(1 mRad/hr. = 5000 ccpm) uCi/cc = ccpm

• 4.5E-07 uCi/dpm VOL (FT 3)

• 2.832E+4 (CC/FT*)

• EFF (0.10)

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ATTACHMENT 8 Page 1 of 1 DIRECT CONVERSION TABLE OF CORRECTED COUNTS PER MIN. TO uCIICC 1-131 THYROID COMMITTED DOSE EQUIVALENT ccpm uCilcc (mRemlINHALATION hr) 1.13E+01 1.0OE-08 1.30E+01 2.26E+01 2.OOE-08 2.60E+01 5.65E+01 5.OOE-08 6.50E+01 7.92E+01 7.O0E-08 9.10E+01 1.13E+02 1.O0E-07 1.30E+02 2.26E+02 2.O0E-07 2.60E+02 5.65E+02 5.OOE-07 6.50E+02 7.92E+02 7.00E-07 9.1OE+02 1.13E+03 1.OOE-06 1.30E+03 2.26E+03 2.0OE-06 2.60E+03 5.65E+03 5.00E-06 6.50E+03 7.92E+03 7.OOE-06 9.1OE+03 1.13E+04 1.OOE-05 1.30E+04 2.26E+04 2.O0E-05 2.60E+04 3.40E+04 3.00E-05 3.90E+04 4.53+E04 4.00E-05 5.20E+04 EQUATIONS:

corrected counts per minute (ccpm)

(detector efficiency)(collection efficiency)(conversion factor - dpm to uci)(volume - cubic ft.)(conversion factor - cc to cubic ft.)

WHERE:

2.00E-03 ccpm/dpm = DETECTOR EFFICIENCY 90% (0.90) = COLLECTION EFFICIENCY 2.22E+06 dpm/uCi = CONVERSION FACTOR 10 Cubic Feet = VOLUME 2.832E+04 cc to Cubic Feet = CONVERSION FACTOR uCi/cc

• Dose Rate Conversion Factor (DRCF) = mRem/Inhalation hr.

WHERE:

1.30E+09 mRem/uCi/cc/hr = Dose Rate Conversion Factor (DRCF) from EPA 400 Nuclear Common Page 21 of 65 Revl

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ATTACHMENT 9 Page 1 of 3 FIELD MONITORING TEAM RESPONSIBILITIES AND DIRECTIONS 1.0 RESPONSIBILITIES 1.1 The Field Monitoring Team Should Perform The Following:

1.1.1 RECEIVE a briefing from the RPS-Offsite 1.1.2 OBTAIN a copy of the completed Form - 4, Field Monitoring Team Briefing Form.

1.1.3 OBTAIN a Dimension (DID) or Centrex telephone number for the RPS-Offsite and a hand held radio located next to the Radio base station.

Phone #:

1.1.4 READ Attachment 14, Package Insert for Thryo-Block Tablets, and SIGN Form - 3, KI Side Effects/Administration Sign Off Form.

1.1.5 OBTAIN the Forms Kit briefcase from RPS-Offsite.

1.1.6 CHECK seals on Field Monitoring Kits. Perform an inventory of kits in accordance with Emergency Preparedness Procedure 1006, if seal is broken.

NOTE A satisfactory response check would be an upscale response on the Count Rate or Dose Rate instrument, when the instrument is on the lowest scale.

1.1.7 PERFORM response checks on instruments and replace batteries or instrument, if necessary.

1.1.8 SIGN on to appropriate Radiation Work Permit and ensure SRDs, are zeroed, if used, and ALNOR is set at 80% of 4500 mRem minus current year to date dose.

1.1.9 LOAD the Onsite Field Monitoring Team Kits into the Emergency Van using Attachment 4, Onsite Field Monitoring Equipment Checklist, to help ensure needed items are not left behind 1.1.10 PERFORM a radio and a telephone check from the emergency van:

SET the radio on frequency

• 1 to contact the Onsite Field Monitoring Team(s)

• 4 to contact the Offsite Field Monitoring Team(s).

1.1.12 INFORM the RPS-Offsite if the Emergency Van's gas gauge indicates less than 1/2 full, prior to going into the field or at any time while in the field.

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ATTACHMENT 9 PAGE 2 OF 3 1.1.13 REPLENISH Onsite Field Monitoring Team Kits to ensure kits are kept in a ready mode lAW Emergency Preparedness Procedure 1006 at the end of a:

"* Drill

"* Exercise

"* Declared Emergency 1.1.14 PERFORM response checks on instruments used. Inform RPS Offsite if instrument(s) fails response check.

2.0 DIRECTIONS 2.1 The Field Monitorinq Team Should Perform The Following:

NOTE The Onsite Field Monitoring Team should provide input to the RPS-Offsite as they think is necessary concerning plant conditions, sampling, moving to other then assigned locations due to radiological or meteorological conditions. The Onsite Field Monitoring Team members should report conflicting radiological or meteorological conditions to the RPS-Offsite, ASAP.

2.1.1 ENSURE air samples taken using a low volume air sampler should be a total of 10 cubic feet taken at a flow rate not to exceed 2 cfm unless otherwise directed by the RPS-Offsite.

2.1.2 PURGE iodine cartridges in low background area outside the plume after collecting the sample.

NOTE Air samples may be taken in accordance with NC.EP-EP ZZ 0306 Emergency Grab Air Sampling and Analysis, if approved by RPS-Offsite.

2.1.3 ENSURE open and closed window readings are be taken at every sampling location.

2.1.4 CONTACT with the RPT-Radio should be maintained at least every 30 minutes.

2.1.5 MAINTAIN contamination controls whenever handling air samples.

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ATTACHMENT 9 PAGE 3 OF 3 2.1.6_STORE all samples in back area of emergency van, unless otherwise directed by the RPS-Offsite.

2.1.7 COVER all samples reading 100 mR/hr. or greater on contact with a lead blanket and contact the RPS - Offsite immediately.

2.1.8 MONITOR dose rates and check dosimetry upon exiting the plume.

2.1.9 FRISK and SURVEY appropriate equipment, as time allows, after exiting the plume to ensure contamination levels are below 50k ccpm smearable contamination.

2.1.10 CONTACT RPS-Offsite for further directions on what to do with equipment if contamination levels are 50k ccpm or greater smearable contamination.

2.1.11 REFER to Attachment 11, Onsite Emergency Monitoring Locations, for the Onsite Monitoring Locations.

2.1.12 REFER to Attachment 12, Offsite Field Monitor Locations, for the Offsite Monitoring Locations. -

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ATTACHMENT 10 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 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.

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ATTACHMENT 11 Page 1 of 3 ONSITE EMERGENCY MONITORING LOCATIONS DESIGNATION LOCATION DESCRIPTION A-7 Northeast corner of circulating water intake structure.

A-1 End of pier by heli-pad.

B-6 Halfway between north end of circulating water intake and service water intake structure.

C-7 West Corner of "B" Building B-10 By heli-pad.

B-12 Adjacent to Jet Fuel Storage Tank on wooded fence.

D-5 North of service water structure on security fence.

C-5 Northeast corner of service water structure.

C-6 Chemistry trailer.

C-8 Along sidewalk, 150' north of Unit #1 Guardhouse (at Hose Station).

D-11 Southeast corner of SNGS switchyard, on security fence.

D-4 Security access road, due west of midway between the two Containment Buildings, west of south end of "A" Building.

D-6 On wall of Salem Unit #1 Fuel Handling Building, opposite R-45 shed.

D-7 Closest outside entrance to the Control Point (next to Unit

1. 1 steam mixing bottle).

D-8 Southeast corner of SNGS Cafeteria.

E-4 Northwest corner of security road at right angle (inside fence).

E-6 On wall of Salem Unit #2 Fuel Handling Building, opposite R-45 shed.

E-7 Between Salem Unit #2 Containment Building and Unit #2 Turbine Building.

F-7 Northwest corner of SNGS Unit #2 Turbine Building.

E-8 Northeast corner of SNGS Administration Building Nuclear Common Page 26 of 65 Revi

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ATTACHMENT 11 Page 2 of 3 F-1 1 Inside site security fence at northeast corner of SNGS switchyard.

F-5 Adjacent to First Aid Trailer.

F-8 Inner Access Road, northeast intersection.

G-7 Adjacent to SE Corner of USNRC Trailer.

G-8 SNGS South Fence Vehicle Access Gate.

G-9 Southwest corner SNGS #2 Warehouse.

H-3 Near the fence between Salem and Hope Creek south of Radwaste Storage Facility.

H-4 Chemical Waste Holding Basin. Near the fence between Salem and Hope Creek 500' northwest of Salem Chemical Waste Holding Basin.

H-5 Near the fence between Salem and Hope Creek near the 907 Building H-6 Near the fence between Salem and Hope Creek northeast of 906 Building.

H-7 200' West of Security Center.

H-8 Behind Security Center.

1-2 West of Radwaste Storage Facility on lamp post.

1-4 Southwest corner of Hope Creek Reactor Building.

1-6 Hope Creek Unit #1 Turbine Building (Southeast corner of Turbine Building).

1-7 On Hope Creek security fence, 100' east of Southeast corner of Turbine Building.

J-1 Hope Creek Intake Structure.

K-4 Northwest corner of Hope U/2 Reactor Building (Abandoned).

K-6 Northeast corner of Hope Creek Turbine Building.

K-7 On security fence, east of northeast corner of Turbine Building.

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ATTACHMENT 11 Page 3 of 3 K-1 West of Material .Center inside security Fence on lamppost.

L-6 100' southeast of Hope Creek Auxiliary Boiler Building.

M-1 Northwest corner of Hope Creek Security fence.

M-2 Adjacent to Hope Creek Sewerage Treatment facility (Outside Protected Area).

M-3 Inside Hope Creek security fence, 500' east of corner of fence.

M-4 Inside Hope Creek security fence, 100' northwest of fire water tank.

M-5 Inside Hope Creek security fence, North of Aux Boiler House.

N-6 Southwest of Hope Creek Cooling Tower. (Outside Protected Area).

0-1 Along Hope Creek security fence near fuel oil storage tank (Outside Protected Area).

N-5 Along Hope Creek security fence near Circ. Water Building (Outside Protected Area).

0-0 Northwest corner of Hope Creek site, near Cooling Tower Blowdown Outfall Instrument Shelter (Outside Protected Area).

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ATTACHMENT 12 Page 1 of 17 OFFSITE EMERGENCY MONITORING LOCATIONS NOTE The following pages of this Attachment include Offsite Emergency Monitoring Stations for New Jersey and Delaware. The descriptions and directions to each of the locations are contained in this attachment. Most monitoring points are situated at intersections, end of roads or landmarks. In addition, many points are identified by symbols painted on utility poles. These symbols consist of 2 to 5 letters or numerals (ENE4, etc.) painted in green above 3 orange circles arranged in a triangle. All distances are approximate.

LOCATION MILE AZIMUTH DESCRIPTION N7 5.8 6.50 Drive 1.6 miles North on Hancocks Bridge Road from the Hancocks Bridge intersection.

Turn left onto Ft. Elfsborg Road proceed 3.5 miles to curve at the intersection of Road 625. The marked pole at the intersection is the monitoring location.

NIO 9.6 355.5o Drive 3.5 miles North on Route 49 from the town of Salem until you reach Lighthouse Road. Turn left onto Lighthouse Road and proceed 2 miles to Fort Mott Road. Turn left onto Fort Mott Road. Proceed 1.5 miles to the end of the road. The marked pole at the end of the road is the monitoring location.

N20 10.5 100 Drive 3.8 miles North on Route 49 from the town of Salem you reach Richmans Dairy.

The monitoring location is located in front of the restaurant.

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ATTACHMENT 12 Page 2 of 17 LOCATION MILE AZIMUTH DESCRIPTION NE7 5.8 210 Drive 1.6 miles North on Hancocks Bridge Road from the Hancocks Bridge Intersection.

Turn left onto Ft. Elfsborg Road and proceed 2.2 miles to Amwellbury Road. The marked pole at this intersection is the monitoring location.

NNE8 6.4 110 Drive 1.6 miles North on Hancocks Bridge Road from the Hancocks Bridge intersection.

Turn left onto Ft. Elfsborg Road and proceed 4.2 miles to Country Club Road. The marked pole at the intersection is the monitoring location.

NNE10 8.7 250 Drive North on Market Street 0.3 miles from the town of Salem. Turn left onto Hancock Avenue and proceed to the end of the Avenue. The marked pole located 50 feet around the corner is the monitoring location.

NNE10a 7.4 26.50 Drive 0.8 miles South on Walnut Street from East Broadway, to the New Salem High School. The marked pole across the street from the school is the monitoring location.

NNE10b 7.3 100 Drive 1.6 miles North from the Hancocks Bridge intersection, towards the town of Salem on Hancocks Bridge Road. Turn left onto Ft. Elfsborg Road and proceed 4.3 miles to Sinnickson Landing Road. Turn left and proceed 1.5 miles. After crossing a bridge, the monitoring locations on the left prior to the first house.

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ATTACHMENT 12 Page 3 of 17 LOCATION MILE AZIMUTH DESCRIPTION NNE20 10.3 280 Drive North 2.6 miles on Market Street to the Memorial Hospital of Salem County. The marked pole located in front of the hospital is the monitoring location.

NE4 3.8 50.50 Drive 0.5 miles North from Hancocks Bridge intersection toward the town of Salem. Turn left onto Front Street, which will become Poplar Street. Front Street is the last street before the bridge. Proceed to the gate located at the end of the road. The marked concrete pole located at the gate is the monitoring location.

NE5 4.1 520 -Drive 0.5 miles North from the Hancocks Bridge intersection toward the town of Salem.

Turn left onto Front Street, which will become Poplar Street. Front Street is the last street before the bridge. Proceed 0.9 miles to a farm with a large white and green barn. The marked pole across the street from the farm is the monitoring location.

NE7 5.1 550 Drive 0.2 miles North from the Hancocks Bridge intersection to the Lower Alloways Creek Municipal Building. The monitoring location is across the street from the Municipal Building on a pole south of the post office.

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ATTACHMENT 12 Page 4 of 17 LOCATION MILE AZIMUTH DESCRIPTION NE7a 5.8 40.5 0 Drive 1.7 miles North from the Hancocks Bridge intersection toward the town of Salem to the intersection of Hancocks Bridge and Quinton Road and Salem/Hancock Bridge Road. The marked pole is the monitoring location.

NE10 8.8 48.50 Drive 3.5 miles east from the town of Salem on Route 49 to the intersection of Routes 49 and 581. This is a stoplight located in Quinton. Turn left onto Route 581 and proceed 0.2 miles to the Waterworks Road intersection. The marked pole at this intersection is the monitoring location.

10.8 450 Drive East 3.8 miles on Grant Street in the NE20 town of Salem to Clancy Road. (Grant Street turns into Quaker Neck Road). The marked pole located at the Clancy Road intersection is the monitoring location.

750 Drive 3.5 miles on the access road from the ENE4 3.7 Salem and Hope Creek Generating Stations.

Located on the west side of the road is an air sampler. The monitoring location is located at the air sampler.

ENE5 4.1 62.50 Drive 4.8 miles from the Salem and Hope Creek Generating Stations, to the intersection of Grosscup Road. The marked pole located at the Grosscup Road intersection is the monitoring point location.

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ATTACHMENT 12 Page 5 of 17 LOCATION MILE AZIMUTH DESCRIPTION ENE7 5.9 650 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store ENE10 8.6 680 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Proceed straight through the stop light and bear to the left.

This should be Harmersville/Peck Corner Cohansey Road. Proceed 2.6 miles to the intersection of Jericho Road. The marked pole at this intersection is the monitoring location.

ENE20 10.5 730 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Proceed straight through the stop light and bear to the left.

This should be Harmersville/Peck Corner Cohansey Road. Proceed 4.5 miles to the intersection of Route 49. The monitoring location is at this intersection.

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ATTACHMENT 12 Page 6 of 17 LOCATION MILE AZIMUTH DESCRIPTION El 0.9 1060 The fork in the Access Road between the Salem and Hope Creek Generating Stations.

Located on pole to the right of air sampler.

E4 3.5 880 Drive 3.1 miles from the Salem and Hope Creek Generating Stations, down the Access Road to the sharp bend. The monitoring location is at the sharp bend on the gantry pole.

E7 6.5 85.50 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Proceed straight through the stop light and bear to the left.

This should be Harmersville/Pecks Corner Cohansey Road. Turn right onto Canton Road and proceed 3 miles to Frogg Ocean Road. The marked pole located at this intersection is the monitoring location.

E20 12.6 910 Drive 12.5 miles East, from the town of Salem, on Route 49 to the intersection of East/West Roadstown Road. The marked pole at this intersection is the monitoring location.

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ATTACHMENT 12 Page 7 of 17 LOCATION MILE AZIMUTH DESCRIPTION ESE7 6.4 1040 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Turn right onto Canton Road and proceed 3.7 miles to Long Bridge Road. Turn right and proceed 1.6 miles to the end of the road. Turn left onto Stow Neck Road and proceed 0.3 miles. The marked pole on is the monitoring location.

ESE10 8.1 103 0 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Turn right onto Canton Road and proceed 5.2 miles to the intersection of Gum Tree Corner. The monitoring location is at this intersection.

ESE20 11.3 1180 Drive 6.8 miles from the Salem and Hope Creek Generating Stations, to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Turn right onto Canton Road and proceed 3.4 miles to the end of the road. Turn left onto Bacon's Neck Road and proceed 0.3 miles to Market Road.

The marked pole located at this intersection is the monitoring location.

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ATTACHMENT 12 Page 8 of 17 LOCATION MILE AZIMUTH DESCRIPTION SE10 8.8 1290 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Turn right onto Canton Road and proceed 5.2 miles to Gum Tree Corner and bear right onto Gum Tree Corner. Proceed 3.4 miles to the end of the road. Turn right onto Bacon's Neck Road and proceed 0.6 miles until you reach Tindull Island Road. Turn left and proceed 0.2 miles until you reach Bayside Road. Turn left and proceed 2.0 miles to the fork in the road.

Take the right fork and proceed to the end of the road. The marked pole located at the end of the road is the monitoring location.

SE20 11.4 1250 Drive 6.8 miles from the Salem and Hope Creek Generating Stations to the Harmersville intersection. The stoplight located at the LAC General Store is the Harmersville intersection. Turn right onto Canton Road and proceed 5.2 miles to Gum Tree Corner and bear right onto Gum Tree Corner. Proceed 3.4 miles to the end of the road. Turn right onto Bacon's Neck Road and proceed 0.6 miles until you reach Tindull Island Road. Turn left and proceed 1.5 miles to Ragged Island Road. Turn left and proceed to the end of the Road. The pole marked at the end of the road is the monitoring location.

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ATTACHMENT 12 Page 9 of 17 LOCATION MILE AZIMUTH DESCRIPTION SSE1 0 9.6 1590 Drive to the Delaware Memorial Bridge and proceed 28 miles on Rte 13 South to Rte 6.

Turn left onto Rte 6 and proceed 7.0 miles to the end of the road. The monitoring location is at the end of the road at Wood-land Beach on a telephone pole on the beach.

S5 4.2 1870 Drive to the Delaware Memorial Bridge and proceed 18 miles on Rte 13 South to Odessa. Turn left onto Main StIRte 299 and proceed 6 miles South to Rd 453.(Rte 299 turns into Rte 9 and Rd 453 is also known as Cedar Swamp Rd).Turn left onto Rd 453 and proceed 2.7 miles to the end of the road.

The monitoring location is at the end of the road on a concrete barrier.

S7 6.3 179.50 Drive to the Delaware Memorial Bridge and proceed 18 miles on Rte 13 South to Odessa. Turn left onto Main StIRte 299 and proceed South 9 miles to Rd 491.(Rte 299 turns into Rte 9). Proceed 1.4 miles on Rd 491 to the intersection. Monitoring location is at this intersection.

S10 9.1 1770 Drive to the Delaware Memorial Bridge and proceed 28 miles on Rte 13 South to Rte 6.

Turn left onto Rte 6 and proceed 4.2 miles to Rte 9. Turn left on Rte 9 and proceed 1.8 miles to Rd 321. The monitoring location is at this intersection.

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ATTACHMENT 12 Page 10 of 17 LOCATION MILE AZIMUTH DESCRIPTION SSW4 3.9 2030 Drive to the Delaware Memorial Bridge and proceed 18 miles on Route 13 South to Odessa. Turn left onto Main Street/Route 299 and proceed South 6 miles to Road 453.

(Route 299 turns into Route 9 and Road 453 is also known as Cedar Swamp Road). Turn left onto Road 453 and proceed 1.6 miles, the monitoring locations is on the left side of the road.

SSW7 5.6 198.50 Drive to the Delaware Memorial Bridge and proceed 18 miles on Route 13 South to Odessa. Turn left onto Main Street/Route 299 and proceed 9 miles to Road 454.

(Route 299 turns into Route 9 and Road 454 is also known as Saw Mill Road). The monitoring location is at this intersection.

SSW10 9.1 203.50 Drive to the Delaware Memorial Bridge and proceed 24 miles on Route 13 South to Road 469. (Road 469 is also known as Black Diamond Road). Turn left onto Road 469 and proceed 2 miles to Road 30 and 45. The monitoring location is at this intersection.

SSW20 11.6 1990 Drive to the Delaware Memorial Bridge and proceed 28 miles on Route 13 south to Route 6 in Symra. The monitor location is at this intersection in the back of "Wendy's" parking lot.

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ATTACHMENT 12 Page 11 of 17 LOCATION MILE AZIMUTH DESCRIPTION SW5 4.9 2160 Drive to the Delaware Memorial Bridge and proceed 18 miles on Route 13 South to Odessa. Turn left onto Main Street/Route 299 and proceed 6 miles to Road 453.

(Route 299 turns into Route 9 and Road 453 is also known as Cedar Swamp Road). The monitoring location is in the front of light house.

SW7 6.0 2350 Drive to the Delaware Memorial Bridge and proceed 18 miles on Route 13 South to Odessa. Turn left onto Main Street/Route 299 and proceed 3.5 miles to Road 452.

(Route 299 turns into Route 9 and Road 452 is also known as Taylor's Bridge Road). The monitoring location is at this intersection in the island.

SW10 9.0 2300 Drive to the Delaware Memorial Bridge and proceed 22 miles on Route 13 South to the intersection of 896. The monitoring location is at this intersection on the south side of Route 13 at the 2nd right of triangle.

SW20 12.3 2250 Drive to the Delaware Memorial Bridge and proceed 22.5 miles on Route 13 south to Road 471. Turn right onto Road 471 proceed 2.5 miles to Road 47. (Road 471 is also known as Salem Church Road and Road 47 is also known as Greenspring/

Vandyke Road). Turn right and drive 1.0 miles to Dexter Corner. The monitoring location is at this intersection on pole with adjacent junction box on the North East corner.

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ATTACHMENT 12 Page 12 of 17 LOCATION MILE AZIMUTH DESCRIPTION.

WSW5 4.4 2550 Drive to the Delaware Memorial Bridge and proceed 18 miles on Route 13 South to Odessa. Turn left onto Main Street/Route 299 and proceed 2.6 miles to road 440.

(Route 299 turns into Route 9. Road 440 is also known as Thomas Landing Road). Turn right onto Road 440 and drive 0.8 miles to the end of the paved road. Monitoring location is at the end of the paved road.

WSW5a 4.2 2630 Drive to the Delaware Memorial Bridge and proceed 9 miles on Rte 13 South to Rte 72.

Turn left onto Rte 72 and proceed 11.5 miles to the bridge over the Appoquinimink River.

(Rte 72 turns into 9). You will pass W5 monitoring location on the North side of the bridge. Drive 0.5 miles to the monitoring location.

WSW10A 7.7 2400 Drive to the Delaware Memorial Bridge and proceed 20 miles on Route 13 South to Road

25. (Road 25 is also known as Townsend Pine Tree Corner Road). The monitoring location is in the North end of the parking lot at this point.

WSW10 9.4 2410 Drive to the Delaware Memorial Bridge and proceed 20 miles on Route 13 South to Road

25. (Road 25 is also known as Townsend Pine Tree Corner Road). Turn right onto Road 25 and proceed 1.8 miles to the Townsend Elementary School. The monitoring location is at the school.

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ATTACHMENT 12 Page 13 of 17 LOCATION MILE AZIMUTH DESCRIPTION WSW20 11.0 2420 Drive to the Delaware Memorial Bridge and proceed 20 miles on Rte 13 South to Rd 25.

(Rd 25 is also known as Townsend Pine Tree Corner Rd). Turn right and proceed 3.0 miles to Rd 459. (Rd 459 is also known as Grears Corner Rd). The monitoring location is at this intersection.

W5 4.2 271.50 Drive to the Delaware Memorial Bridge and proceed 9 miles on Rte 13 South to Rte 72.

Turn left onto Rte 72 and proceed 11.5 miles to the bridge over the Appoquinimink River.

(Rte 72 turns into 9). The monitoring location is on the North side of the bridge.

W7 6.6 264.50 Drive to the Delaware Memorial Bridge and proceed 18 miles on Rte 13 South to Odessa. Turn left onto Main St/Rte 299.

The Monitoring location is at this intersection at the Delaware State Police Station.

W10 9.9 263.50 Drive to the Delaware Memorial Bridge and proceed 18 miles on Rte 13 South to Odessa. Turn right onto Main St/Rte 299 and proceed 3 miles to Middletown. (Main St/ Rte 299 turns into Rte 9). Turn left onto S. Broad St/Rte 896. The monitoring location is at this intersection at the Fire Station.

W20 11.2 261.50 Drive to the Del. Memorial Bridge and proceed 18 miles on Rte 13 South to Odessa. Turn right onto Main St/Rte 299 and proceed through the town to the traffic light. At Route 30, turn left and go 0.5 miles to Greers Corner Road.

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ATTACHMENT 12 Page 14 of 17 LOCATION MILE AZIMUTH DESCRIPTION WNW4 3.4 2940 Drive to the Delaware Memorial Bridge and proceed 9 miles on Rte 13 South to Rte 72.

Turn left onto Rte 72 and proceed to Belts Rd.(Rte 72 turns into Rte 9).Turn left onto Belts Rd and proceed to the lighthouse gate.

The monitoring location is at the gate.

WNW5 4.0 2950 Drive to the Delaware Memorial Bridge and proceed 9 miles on Rte 13 South to Rte 72.

Turn left onto Rte 72 and proceed 10 miles to a sharp 90 curve to the left.(Rte 72 turns into Rte 9). The monitoring location is before the curve across from a 90 curve caution sign on the North side of the road.

WNW7 6.7 291.50 Drive to the Delaware Memorial Bridge and proceed 14.5 miles on Rte 13 South to Rd 15.(Rd 15 is also known as Boyds Corner Rd). Turn left at light. The monitoring location is in the Wawa parking lot.

WNW10 8.5 288.50 Drive to the Delaware Memorial Bridge and proceed 14.5 miles on Rte 13 South to Rd

15. Turn right onto Rd 15 and proceed 1.8 miles to Rd 413. (Rd 15 is also known as Boyds Corner Rd and Rd 413 is also known as Jamison Corner Rd). The monitoring location is at the intersection.

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ATTACHMENT 12 Page 15 of 17 LOCATION MILE AZIMUTH .DESCRIPTION WNW20 10.4 292.50 Drive to the Delaware Memorial Bridge and proceed 14.5 miles on Rte 13 South to Rd

15. Turn right onto Rd 15 and proceed 3.5 miles to Rte 896 /301.(Rd 15 is also known as Boyds Corner Rd).Turn right onto Rte 896

/301 and proceed 1 mile to the Summit Airport. The monitoring location is at the Summit Airport next to a ditch full of large rocks.

NW4 3.8 315.50 Drive to the Del. Memorial Bridge & proceed 9 miles on Rte 13 South to Rte 72. Turn left onto Rte 72 & proceed 8.5 miles to Augustine Bch. (Rte 72 turns into Rte 9). The

-monitoring location is at Augustine Bch adjacent to sign.

NW7 5.5 3120 Drive to the Del. Memorial Bridge & proceed 14.5 miles on Rte 13 South to Rd 15. Turn left onto Rd 15 & proceed 2.5 miles to the Port Penn intersection. The monitoring location is at this intersection.

NW10 8.4 3120 Drive to the Del. Memorial Bridge & proceed 11 miles on Rte 13 South to St. Georges Bridge. Cross over the bridge & turn right at the first road. The monitoring location is at this intersection.

NW20 11.5 3100 Drive to the Del. Memorial Bridge & proceed 6 miles on Rte 13 South to Rte 301. Bear right onto Rte 301 & proceed 4.5 miles to the intersection of Rd 409. (Rd 409 is also known as St. Georges Rd). The monitoring location is on the south side of RR tracks next to RR signal.

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ATTACHMENT 12 Page 16 of 17 LOCATION MILE AZIMUTH DESCRIPTION NNW5 4.2 3280 Drive to the Del. Memorial Bridge & proceed 9 miles on Rte 13 South to Rte 72. Turn left onto Rte 72 and proceed 7.5 miles to the small bridge just south of Port Penn.(Rte 72 turns into Rte 9.) Turn left just prior to the bridge & proceed 0.2 miles to the end of the road. The monitoring location is at the end of the road in front of the sewage plant where an air sampler is located. (NOTE: Map location is wrong. Correction location is about one inch south on map on Rte. 9).

NNW7 5.9 332.50 Drive to the Delaware Memorial Bridge and proceed 9 miles on Route 13 South to Route

72. Turn left onto Route 72 and proceed 6.5 miles to Torntown Road intersection.(Route 72 turns into Route 9. The monitoring location is on the river side at this intersection.

NNW10 7.8 3420 Drive to the Delaware Memorial Bridge and proceed 9 miles on Route 13 South to Route

72. Turn left onto Route 72 and proceed 4 miles to Delaware City.(Route 72 turns into Route 9). Cross over the small bridge and turn right at the first road.(Follow the signs to the Emergency Plan Center/Governor Bacon Health Center). Turn left at the first road and proceed 0.3 miles to the end of the road.

The monitoring location is in the front of the EPC, East of blue garage.

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ATTACHMENT 12 Page 17 of 17 LOCATION MILE AZIMUTH DESCRIPTION NNW20 12.3 3310 From Delaware Memorial Bridge take Route 13 South (Delaware) 7.6 miles to Bear Tybouts Road and make a left. The monitoring point is at the North East Corner of Park & Ride at the light.

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ATTACHMENT 13 Page 1 of I DAPA CORRECTION CALCULATIONS NOTE "THIS ATTACHMENT IS FOR USE FOR HOPE CREEK ONLY!"

DAPA temperature is located on the VAX LA120, Operation Status Board (EOF Menu Selection "2").

1.1 Refer to figure 1 - 1.

1.2 The DAPA Monitor is unreliable and should not be used, if the uncorrected DAPA reading lies below the curve (shaded region).

1.3 Proceed to step 1.4, if the uncorrected DAPA reading lies above the curve.

1.4 Refer to figure 1 - 2.

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.

+-

DAPA Monitor Bias Value Corrected DAPA Reading (R/hr) Reading (R/hr) Reading (R/hr)

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-ATTACHMENT 14 Page 1 of 1 PACKAGE INSERT FOR THYRO-BLOCK TABLETS 1.0 HOW POTASSIUM IODIDE-WORKS

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

"* In a radiation emergency, radioactive iodine may be released in the air. This material may be breathed or swallowed. It may enter the thyroid gland and damage it. The damage would probably not show itself for years. Children are most likely to have thyroid damage.

" If you take potassium iodide, it will fill your thyroid gland. This reduces the chance that harmful radioactive iodine will enter the thyroid gland.

2.0 WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicine for a thyroid problem (for example, a thyroid hormone or anti-thyroid drug). Pregnant and nursing women and babies and children may also take this drug.

3.0 HOW AND WHEN TO TAKE POTASSIUM IODIDE Potassium Iodide should be taken as soon as possible after public health officials tell you. You should take one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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.

4.0 SIDE EFFECTS

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

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

"* A few people have an allergic reaction with more serious symptoms. These could be 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 iodine may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland or enlargement of the thyroid gland (goiter).

5.0 WHAT TO DO IF SIDE EFFECTS OCCUR If the side effects are severe or if you have an allergic reaction, stop taking potassium iodide and call a doctor.

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NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 15 Page 1 of 3 OPERATION OF THE VAX LAI20 TERMINAL 1.0 METEOROLOGICAL DATA 1.1 Perform The Followina to Obtain Current 15 Minute Average Meteoroloaical Data:

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

1.1.2 ENTER 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 3 (Disable Automatic Display of MET Data Every 15 minutes) and depress the RETURN key to stop the VAX LA120 from printing out meteorological data every 15 minutes.

1.1.4 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 Followina SteDs to Obtain Archived Meteoroloqical Data:

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

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NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 15 Page 2 of 3 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 1989 "depress the space bar once" and enter 01:30).

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

1.2.8 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).

1.2.9 ENTER "Y"ifthe 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 ENTER EOF and depress the RETURN key. (A prompt should be displayed asking for PASSWORD).

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NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 15 Page 3 of 3 2.1.3 ENTER the letters EOFUSER and depress the RETURN key.

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

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

2.2.4 SELECT option 1 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 number 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-0310 (Q)

ATTACHMENT 16 Page 1 of 3 INSTRUCTIONS FOR SALEM SPDS DISPLAYS 1.0 SALEM I & 2 SPDS RADIOLOGICAL SCREEN INSTRUCTIONS 1.1 Follow The Steps Below In The Listed Order, To Display SPDS Radiological Screens.

NOTE Values in Red with "HH" displayed are in HIGH HIGH ALARM.

Values in YELLOW with "H"displayed are in HIGH ALARM.

Form - 7, SPDS RMS Log, may be used to record SPDS RMS values.

1.1.1 DEPRESS the UNIT MASTER MENU Key 1.1.2 DEPRESS and hold the "SHIFT" key, while depressing the number 5 key. (Radiation Monitor Screen 1 will be displayed.

This screen (Radiation Monitor Screen 1 will be displayed. This screen consists of instantaneous values for the RMS monitors listed below).

0 R46A-E Main Steam Line Mon 0 R44A/B Containment Post LOCA Rad Mon

• R11A Containment Particulate 0 R12A Containment Noble Gas

• R12B Containment Iodine

• R44A/B Integ Dose Containment Post LOCA Rad Mon 1.1.3 DEPRESS and hold the "SHIFT" key, while depressing the number 2 key. (Radiation Monitor Screen 2 will be displayed.

This screen consists of RMS instantaneous monitor values listed below).

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NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 16 Page 2 of 3

• R45B Plant Vent Accident Mon (Medium Range Noble Gas)

• R45C Plant Vent Accident Mon (High Range Noble Gas)

• R16 Plant Vent Gas Eff

• R41A Low Range Noble Gas

• R41B Mid Range Noble Gas

• R41C High Range Noble Gas

• R43 Aux Building Roof Mon

• Unit 1 or 2 Noble Gas Release Rate

• Combined Noble Gas Release Rate 1.1.4 DEPRESS and hold the "SHIFT" key, while depressing the number 3 key. (Radiation Monitor Screen 3 will be displayed.

This screen consists of RMS 15 minute average monitor values listed below).

• _ R46A-E Main Steam Line Mon R44A/B Containment Post LOCA Rad Mon R11A Containment Particulate R12A Containment Noble Gas R12B Containment Iodine 1.1.5 DEPRESS and hold the "SHIFT" key, while depressing the number 4 key. (Radiation Monitor Screen 4 will be displayed.

This screen consists of RMS 15 minute average monitor values listed below).

• Plant Vent Airflow to Atmosphere (Plant Vent Flow Rate)

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NC.EP-EP.ZZ-0310 (Q)

ATTACHMENT 16 Page 3 of 3

• R45B Plant Vent Accident Mon (Medium "RangeNoble Gas)

• R45C Plant Vent Accident Mon (High Range Noble Gas)

• R16 Plant Vent Gas Eff

• R41A Low Range Noble Gas

• R41 B Mid Range Noble Gas

• R41C High Range Noble Gas

• R43 Aux Building Roof Mon 1.1.6 RECORD RMS values on Log 4, SPDS RMS Log.

2.0 SALEM I & 2 SPDS RADIOLOGICAL SCREEN TRENDING INSTRUCTIONS 2.1 Perform The Steps Listed Below In The Listed Order, To Trend SPDS Radiological Monitors.

2.1.1 DISPLAY the screen that lists the monitor you want to trend.

2.1.2 DEPRESS the "DATA ENTRY FORWARD" key to move the cursor to the radiation monitor that is to be trended.

2.1.3 DEPRESS the "TREND" key.

2.1.4 DEPRESS the "Page Down" key to display the trending of the monitor.

2.1.5 DEPRESS the "Page Up" key to return to Radiation Monitor Screen 1.

3.0 RML SCREEN INSTRUCTIONS DEPRESS The RML Key To Display The Dome Screen.

4.0 RML SCREEN INSTRUCTIONS DEPRESS The RM Key To Display Any Abnormal Releases In Progress.

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NC.EP-EP.ZZ-0310 (Q)

FORM - 1 Page 1 of I FIELD SAMPLING FORM OPEN CLOSED WINDOW WINDOW OPEN WINDOW CLOSED READING CART. READING PART.

DATE/ TEAM WINDOW TIME 4 NAME LOCATION GRD (mRlhr) GRD (mR/hr) GA (mR/hr) GA (mR/hr) (ccpm) (ccpm) 4 & 4 4 4 4 4 4 4 4 4 4 I 4

4

_____ .1 .1 4 +

4 4-4-

__ 1 4.

4 4 t + 4 + +/- 4.---

4 4 4 + 4 + +

4 4- 4 4 4- -4 4 4 4 1- 4 4 + -4 4 4 Nuclear Common Page 54 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

FORM - 2 Page 1 of I DOSIMETRY LOG INTIAL END TOTAL DOSIMETER ISSUE[ RTN VALUE VALUE DOSE NAME NUMBER DATE DATE (mRem) (mRem) (mRem) 1- 1 r 4- .4. 4- .1- + 4 4 + + + -t t 4 4- - 4- t

& I. 4 I. 4 4 4 4 4 4 1 4 4 4 4 4 +

4 4 4 4 i -4.

4 4 4 4 4- 4 4- 4 4 4 + I.

+ I 1 1 -4.

4. .4 4- 4- 4 4- 4- 4- + 4 4 4 + + 4 1 Nuclear Common Page 55 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

FORM - 3 Page 1 of 2 KI SIDE EFFECTSIADMINISTRATION SIGN OFF FORM AUTHORIZED BY:

ADMINISTERED BY:

My signature indicates that I have read and understand Attachment 14 Package Insert For Thyroid Blocking Tablets.

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NC.EP-EP.ZZ-0310 (Q)

FORM - 3 Page 2 of 2 Nuclear Common Page 57 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

FORM - 4 Page 1 of 3 FIELD MONITORING TEAM BRIEFING FORM 1.0 TEAM BRIEFING 1.1 The RPS - Offsite Should Ensure The Following Information Is Completed:

1.1.1 RPS-Offsite

/ /

(PRINT/SIGN) (DATE) 1.1.2 Event Classification/Time: /

1.1.3 Plant Conditions :

1.1.4 Wind Direction : (Expected Plume Direction)

"* From: (Degrees) To: (Degrees)

"*From: To:

1.1.5 Specific Monitoring Location(s) If Applicable

"*From : To:

"* Landmarks (If Applicable) 1.1.6 Initial areas or locations to be surveyed: (Refer to Onsite Emergency Monitoring Locations Map or 10 Mile EPZ Map located in the Field Monitoring Kit, as appropriate).

1.1.7 Wind Speed: (MPH) 1.1.8 Protective Clothing Requirements _

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FORM - 4 Page 2 of 3 NOTE Field Monitoring Team members must be respirator qualified prior to instruction them to wear respirators.

1.1.9 Respiratory Protection Requirements:

1.1.10 Additional Specific Radiological Concerns:

1.1.11 Color Name for Onsite Team and Members of Team:

"*Red Team: Name of Team Leader:

Name of Team Member:

"*Blue Team: Name of Team Leader:

Name of Team Member:

"*Green Team: Name of Team Leader:

Name of Team Member:

1.1.12 Phonetic Alphabet Name for Offsite Team and Members of Team:

" Alpha Team: Name of Team Leader:

Name of Team Member:

"*Bravo Team: Name of Team Leader:

Name of Team Member:

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NC.EP-EP.ZZ-0310 (Q)

FORM - 4 Page 3 of 3 Personnel Attending Briefing:

REMAINING DOSE NAME NAME SOCIAL SECURITY FOR FIELD TEAM (PRINT) (SIGNATURE) NUMBER MEMBER (REM)

+/- t

.4. 4 4 Nuclear Common Page 60 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

FORM - 5 Page 1 of I TLD ISSUE LOG Name Date TLD Number Badge Number To the best of my knowledge, my current annual exposure is omrem.

Signature Date Name Date TLD Number Badge Number To the best of my knowledge, my current annual exposure is mrem.

Signature Date Name Date TLD Number Badge Number To the best of my knowledge, my current annual exposure is mrem.

Signature Date Nuclear Common Page 61 of 65 Revl

NC.EP-EP.ZZ-0310 (Q)

FORM - 6 Page 1 of I HABITABILITY LOG DATE:

DOSE RATE CONTAMINATION LOCATION TIME (mR/hr) (CPM) INITIALS

________ I __ I __ I ______ I___

4 4

+/- I 4

.1 .1 I IF other means are used to ensure habitability, THEN list:

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NC.EP-EP.ZZ-0310 (Q)

FORM - 7 Page 1 of I SPDS RMS LOG (SALEM ONLY)

Date/Time: _______ _______I- Salem Unit Location on Monitor Value of SPDS Number Description of Monitor Monitor Units Screen 1/3 R46A Main Steam Line Mon mR/hr Screen 1/3 R46B Main Steam Line Mon mR/hr Screen 1/3 R46C Main Steam Line Mon mR/hr Screen 1/3 R46D Main Steam Line Mon mR/hr Screen 1/3 R46E Main Steam Line Mon mR/hr Screen 1/3 R44A CNTMT Post LCOA Mon R/hr Screen 1/3 R44B CNTMT Post LOCA Mon R./hr Screen 1/3 R11A CNTMT Particulate Mon cpm Screen 1/3 R12A CNTMT Noble Gas Mon cpm Screen 1/3 R12B CNTMT Iodine Mon cpm Screen 4 R16 Plant Vent Gas Mon cpm Screen 2/4 R41A Low Range Noble Gas Mon uCi/cc Screen 2/4 R41 B Mid Range Noble Gas Mon uCi/cc Screen 2/4 R41C High Range Noble Gas Mon uCi/cc Screen 2/4 R45B Plant Vent Accident Mon (Min Range Noble Gas Back-up) uCi/cc Screen 2/4 R45C Plant Vent Accident Mon (High Range Noble Gas Back-up) uCi/cc Nuclear Common Page 63 of 65 Revl

FIGURE 1-1 NC.EP-EP.ZZ-0310 (Q'j DAPA CORRECTION FIGURE Page I of 2 60 50 Shaded Area Indicates DAPA Monitor Value at which Alternate Method of Estimate Dryweut Airborne Rad Levels should 40 be used.

d 0) 30 0

0 n*

10 oo W I 240 260 280 300 320 340 Average Dryweti Air Temperature (°F)

NOTE:

No Correction to the DAPA Monitor is Required below 245° Nuclear Common Page 64 of 65 Rev. I

NC.EP-EP.ZZ-0310 (Q)

FIGURE 1-2 Page 2 of 2 30 L

dV 25 a)20 ry15 L

0 10 0

7-5 240 260 280 300 320 340 Average Drywe(I. Air Temperature (°F)

NOTE:

No Correction to the DAPA Monitor is Required below 245° Nuclear Common Page 65 of 65 Rev. 1

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

SUMMARY

PSE&G

1. This procedure deleted an incorrect reference in step 5.1.19. CONTROL

2. This revision satisfies the requirement for a biennial review. COPY #g~'IF'o69 IMPLEMENTATION REQUIREMENTS:

This procedure is effective for use upon issue.

APPROVED: - - ----- /

Manager - EP & IT Date

-- 77 APPROVED:VPd O Vice President - Operations Date

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

CHEMISTRY SUPERVISOR - CP/TSC RESPONSE 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 LIMITATIONS ................................................. 2 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure .................................................. 2 4.0 EQUIPMENT REQUIRED ................................................................. 2 5.0 PROCEDURE .................................................................................... 2 5.1 The Chemistry Supervisor - CPITSC Should Perform The Following .................................................................................. 2 6.0 RECORDS ........................................................................................ 7

7.0 REFERENCES

................................................................................... 7 7.1 References .............................................................................. 7 7.2 Cross References ................................................................... 7 7.3 Commitments ......................................................................... 7 ATTACHMENTS ATTACHMENT 1 - Salem and Hope Creek Chemistry Systems .............................. 9 ATTACHMENT 2 - Chemistry Guidelines - Power Operation ................................. 10 ATTACHMENT 3 - Chemistry Guidelines - Power Reduction ............................... 11 ATTACHMENT 4 - Chemistry Guidelines - Salem Reactor Trip ............................. 13 ATTACHMENT 5 - Chemistry Guidelines - PASS ................................................. 14 ATTACHMENT 6 - Chemistry Guidelines - Outside Systems .................................. 17 ATTACHMENT 7 - Chemistry Guidelines - Primary to Secondary Leak (SA LEM O NLY ) ..................................................................... 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 PASS Storage Location .................................................... 24 FIGURE 2 - Hope Creek PASS Storage Location .......................................... 26 Nuclear Common PagelI of 26 Rev. I

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

- CP/TSC 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 EQUIPMENTIMATERIAL REQUIRED As provided in the Emergency Response Facility.

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

5.1 The Chemistry Supervisor - CPITSC Should Perform The Following:

NOTE The Chemistry Supervisor - CP/TSC may locate at the CP or the TSC as thought necessary.

5.1.1 REPORT initially to the Control Point.

Nuclear Common Page 2 of 26 Rev. I

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 REFER to Attachment 6 IF:

• Status of outside systems is required during power operation.

Nuclear Common Page 3 of 26 Rev. 1

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

"* 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 the PASS system.

(Guidance and information are provided in Attachment 5, Chemistry Guidelines - PASS).

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

NOTE An individual, in lieu of a team, may be dispatched by the Chemistry Supervisor

- CP after OSC Coordinator notification and approval. 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.).

Nuclear Common Page 4 of 26 Rev. I

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

• 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of recirculation actuation, 5.1.27 NOTIFY the RAC and Nuclear Fuels Engineer - TSC of PASS 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.

Nuclear Common Page 5 of 26 Rev. I

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

5.1.34 PERFORM the following steps to ship a PASS sample to Babcock and Wilcox 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 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 prepared to be given to Babcock and Wilcox:

• 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 Babcock and Wilcox that a PASS sample is going to be shipped to them for chloride analysis at 804-522-5833.

Nuclear Common Page 6 of 26 Rev. I

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

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

NOTE Assembly shall be implemented after the declaration of an Alert Emergency Condition.

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 with the Shift Radiation Protection Technician (SRPT), or the Onshift Radiation Protection Technician ORPT), accountability utilizing the guidance provided in 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 can not 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 can not be used.

6.0 RECORDS Return completed procedure and any information or data thought to be pertinent to the Manager - EP & IT.

7.0 REFERENCES

7.1 References 7.1.1 Nuclear Business Unit Emergency Plan 7.2 Cross References 7.2.1 NC.NA-AP.ZZ-0311(Q), Control Point - Chemistry Response Nuclear Common Page 7 of 26 Rev. 1

NC.EP-EP.ZZ-0312(Q) 7.2.2 Nuclear Administrative Procedure NC.NA-AP.ZZ -0005 7.2.3 Sampling the Primary Condensate Pumps HC.CH-SA.AD-0001(Q) 7.2.4 Operation of the Demineralized Water Make-Up Plant HC.CH-SO.

AN-0001(Q) 7.2.5 Environmental Monitoring and Compliance Sampling HC.CH-TI.ZZ 0003(Q) 7.2.6 Operation of the Zinc Injection System HC.CH-SO.BQ-0001 (Z) 7.2.7 Operation of the Reactor Water Cleanup System HC.CH-SO.BG 0001(Q) 7.2.8 Condensate Demineralizer System Service Vessel Operation HC.CH-SO.AK-0001(Q) 7.2.9 Hydrogen/Oxygen Injection System Operation HC.CH-SO.AX 0001(Q) 7.2.10 Condensate Oxygen Injection System Operation HC.CH-SO.AX 0005(Q) 7.2.11 Post Accident Sample Panel Operation HC.CH-EO.SH-0001 (Q) 7.2.12 Post Accident Sample Analysis HC.CH-EO.SH-0004(Q) 7.2.13 Post Accident Sample Dilution HC.CH-EO.SH-0005(Q) 7.2.14 Transporting Post Accident Sampling System Sampler HC.CH EO.SH-0007(Q) 7.2.15 Sampling From the Turbine Building Sample Station (BOP Panel)

HC.CH-SA.RC-0001(Q) 7.3 Commitments Emergency Preparedness Commitment EP96-005 Nuclear Common Page 8 of 26 Rev. 1

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ATTACHMENT I Page 1 of I 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

• (PAS) PASS Sampling 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. I

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ATTACHMENT 2 Page 1 of I 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.

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.

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 00C118 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.

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.ZZ-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.

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 0OC1 18 and make up to the demin tanks as required.

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ATTACHMENT 4 Page 1 of I 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.

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.

1.5 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 I of 3 CHEMISTRY GUIDELINES - PASS 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

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

"* RCS/RHR-Gas

"* 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 PASS AT SALEM STATION NOTE Figure - 1, Salem PASS Storage Location, illustrates the PASS storage locations outlined in step 2.1.

2.1 REFER to Figure - 1 to ensure the transportation and storage of post accident 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 - CP/TSC informed of transportation and storage activities.

NOTE The plant's current operational condition will determine the appropriate PASS 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 15 of 26 Rev. I

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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.

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

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

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

5.4 KEEP the Chemistry Supervisor - Control Point informed of transportation and storage activities.

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ATTACHMENT 6 Page 1 of I CHEMISTRY GUIDELINES - OUTSIDE SYSTEMS 1.0 Dosimetry ENSURE that all personnel dispatched to the outside systems keep there dosimetry upon exiting the Building.

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.

3.3 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.

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ATTACHMENT 7 Page 1 of I 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.

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ATTACHMENT 8 Page 1 of 2 ASSEMBLYIACCOUNTABILITY INSTRUCTIONS - CONTROL POINT 1.0 IMPLEMENTATION OF ASSEMBLY AT THE CONTROL POINT 1.1 The Chemistry Supervisor-CP/TSC Or Designee SHALL:

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-CPITSC Or Designee SHALL:

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

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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-CP/TSC Or Designee SHALL:

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.

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

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 RAG of the new telephone numbers.

1.1.5 NOTIFY the RAG 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.

1.1.9 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.

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

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

(circle)

LAST NAME/FIRST NAME BADGE NUMBER

+

+

Attach additional pages with appropriate information as needed.

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FIGURE-i Page I of 2 SALEM PASS STORAGE LOCATION ELEVATIOJN 100 NUCLEAR COMMON Page 24 of 26 Rev. I

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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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FIGURE-2 Page 1 of I HOPE CREEK PASS STORAGE LOCATION SAMPLE STORAGE CAVE SERVICE AND RADWASTE AREA 124' 0" ELEVATION NUCLEAR COMMON Page 26 of 26 Rev. I