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Enclosure 2 to LR-N18-0074, Emergency Plan Document Revisions Implemented June 25, 2018
	ML18199A166
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Site:	Salem, Hope Creek
Issue date:	07/18/2018
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
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ML18199A162	List: LR-N18-0074, Enclosure 2 to LR-N18-0074, Emergency Plan Document Revisions Implemented June 25, 2018;
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	LR-N18-0074
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LR-N18-0074 ENCLOSURE 2 EMERGENCY PLAN DOCUMENT REVISIONS IMPLEMENTED JUNE 25, 2018

PSEG Internal Use Only PSEG NUCLEAR L.L.C. Page 1 of 1 EMERGENCY PREPAREDNESS NC.EP-EP.ZZ-0102(Q) Rev. 23 EMERGENCY COORDINATOR RESPONSE USE CATEGORY: II A. Biennial review performed: Yes _ _ No__ ..:...;N:;..;../A_,___

B. Packages and Affected Document Numbers incorporated into this revision: None C. The following OTSCs were incorporated into this revision: None REVISION

SUMMARY

70196577 - Revised to add communications systems available to EC during ELAP/Biackout event:

Added Step 3.1 .6 under Precautions and Limitations concerning communications systems availability during a SBO/ELAP. (70196577)

Added new Attachments 8, Hope Creek Communications Availability Guidance (70196577)

Added new Attachments 9, Salem Communications Availability Guidance (70196577)

Revised Step 5.2.a 1st and 2nd to assess capability of the TSC to staff and activate and activate at an Alert or higher Eplan Section 9.0, Subsection 1.3 (TSC)

Revised Step 5.3.a 151 and 2nd to assess capability of the EOF to staff and activate and activate at an Alert or higher Eplan Section 9.0, Subsection 4.0 (EOF)

Revised Attachments 6 & 7 Note to add information regarding capability to staff and activate at Alert of higher.

80120807/0010- Page 9 step 5.2.a, 3rd step revised from "EDO" to "EC" to be consistent with ERM and to ensure EC notifies SM

70198198/0030- Section 5.2.b & Section 5.3.b- added PAG values for PAR upgrade and scientific notation

70195488 0020 & 80120807/0030- Revised Attachment 4 to provide instructions for optional activation of the ERO at a UE classification

Revised Step 2.7 of Attachment 10 to provide continuing direction during a security event

NC.EP-EP .ZZ-01 02(Q)

EMERGENCY COORDINATOR RESPONSE TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ........................................................................................................ 2 2.0 PREREQUISITES ............................................................................................ 2 3.0 PRECAUTIONS AND LIMITATIONS ................................................................ 2 4.0 EQUIPMENT REQUIRED ................................................................................ 3 5.0 PROCEDURE ................................................................................................... 4 5.1 Shift Manager (SM) Actions ................................................................... 4 5.2 Emergency Duty Officer (EDO) Actions ................................................. 9 5.3 Emergency Response Manager (ERM) Actions .................................. 14 6.0 RECORDS ...................................................................................................... 18

7.0 REFERENCES

............................................................................................... 18 8.0 COMMITMENT DOCUMENTS ....................................................................... 18 ATTACHMENTS:

ATTACHMENT 1 DOCUMENTATION CHECKLIST ..................................................... 19 ATTACHMENT 2 EC EMERGENCY STATUS BRIEFING FORM ................................. 20 ATTACHMENT 3 ACCOUNTABILITY ACTIONS AND RESULTS ................................ 22 ATTACHMENT 4 UNUSUAL EVENT ANNOUNCEMENT ............................................ 24 ATTACHMENT SA ALERT ANNOUNCEMENT ............................................................... 26 ATTACHMENT 58 SITE AREA EMERGENCY ANNOUNCEMENT ................................ 27 ATTACHMENT 5C GENERAL EMERGENCY ANNOUNCEMENT ................................. 28 ATTACHMENT 6 ACTIVATION of the TSC .................................................................. 29 ATTACHMENT 7 ACTIVATION of the EOF .................................................................. 32 ATTACHMENT 8 Communications Availability Guidance - Hope Creek ...................... 36 ATTACHMENT 9 Communication Availability Guidance -Salem ................................. 38 ATTACHMENT 10 SECURITY EMERGENCY GUIDELINE (SEG) ........................... .40 ATTACHMENT 11 Allowable Deviations from Normal Work Practices In Emergencies .. 45 ATTACHMENT 12 Organization of All-Call Extra Responders ........................................ 4 7 Nuclear Common Page 1 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

EMERGENCY COORDINATOR RESPONSE 1.0 PURPOSE This procedure provides:

Emergency response instructions to the Emergency Coordinator (EC) after emergency classification.

Security Emergency Guidelines (SEG is Attachment 10) to the Shift Manager (SM) for use prior to or after emergency classification based on security events.

SM Instructions while filling the role of EC and after being relieved as the EC and reverting back to the role of SM.

Instructions to the EDO and ERM on how to activate the TSC and EOF and actions both prior to and after facility activation.

2.0 PREREQUISITES Initials 2.1 Prerequisites to be Followed Prior to Implementation 2.1.1 ECG Attachment 1, 2, 3, 4 or 24 was completed.

OR 2.1.2 The Security Emergency Guideline, Attachment 10 of this procedure should be implemented immediately if the Shift Manager (SM) judges that security events warrant the implementation of the Operation's Abnormal Procedure for Security Threat or Airborne Threat.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions and Limitations to be Followed Prior to Implementation 3.1.1 Initials should be used for place keeping sign-offs.

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.

3.1 .3 A Loss of Command and Control is defined as either one of the following:

any event resulting in a situation where a qualified SRO is unable to establish direct control of the reactor from either the Control Room or the Remote Shutdown Panel(s).

any event resulting in a situation where a qualified SRO is unable to implement the Emergency Plan.

Nuclear Common Page 2 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Initials 3.1.4 IF circumstances prevent staffing and activation of the TSC, the SM may turnover EC responsibilities directly to the ERM at the EOF, bypassing the TSC.

3.1.5 IF the "Two-Person Line of Sight Rule" is in effect, the deployment of all teams within the vital area will be done lAW SY-AA-101-108, Attachment 2.

3.1.6 If the emergency involves a Station Blackout or Extended Loss of AC Power (ELAP) normal communications systems could be significantly degraded. Refer to Attachment 8 (Hope Creek) or Attachment 9 (Salem) for Communications Availability Guidance.

4.0 EQUIPMENT REQUIRED As provided in the Control Rooms, TSCs and EOF.

Nuclear Common Page 3 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q) 5.0 PROCEDURE Initials/Time

Shift Manager (SM) shall IMPLEMENT section 5.1 of this procedure.

Emergency Duty Officer (EDO) shall IMPLEMENT section 5.2 of this procedure.

Emergency Response Manager (ERM) shall IMPLEMENT section 5.3 of this procedure.

5.1 Shift Manager (SM) Actions:

NOTES

1. Should the Emergency Classification Level change, the SM shall implement actions based on the new Emergency Classification Level.

2. After EC turnover to the EDO, the SM shall continue to implement the SM designated steps in Section 5.1.

3. Since the Rad Alert alarm is located in the Control Room, the SM directs all emergency status change announcements.

!E EITHER one of the following has or is occurring:

Security Based Emergency Att10 Att 10 Att10 Att 10

Catastrophic Event- large explosion, airliner impact, etc. resulting in a loss of command and SM control at the other station Init:

- Init:

THEN Time: Time: - Time: - Time:

IMPLEMENT Attachment 10 - Security Emergency Guideline (SEG), of this procedure For each change in Emergency Classification Level, Att 4 Att 5A Att58 Att5C DIRECT I MAKE emergency status announcements AND Security notifications as follows:

Init: Init: Init: Init:

SM

IMPLEMENT Attachment 4 for Unusual Event

IMPLEMENT Attachment 5 for ALERT or Higher Time:

- Time: - Time: - Time:

(will be requested by EDO if TSC is activated)

For Security based emergency, SEG may require modifications of associated actions/announcements.

Nuclear Common Page 4 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Note: Initials/time each block as applicable DIRECT the other station's SM to: EPEP 101 EPEP 101 EPEP 101 EPEP 101

If not done previously, IMPLEMENT NC.EP- UE ASSEMBLY ASSEMBLY ASSEMBLY EP .ZZ-01 01 , Actions Required at Unaffected Att5 Att4 Att4 Att4 Station.

SM

DIRECT I MAKE a Plant Page announcement per Init: Init: Init: Init:

the applicable referenced attachment based on the - - - -

current emergency level. Time: - Time:- Time: - Time:

For Security based emergency, SEG may require modifications of associated

!E not performed previously, THEN DIRECT the OSC Optional Init:

- Init:

SM Coordinator to Activate the OSC lAW NC.EP-EP.ZZ- (Mandatory 0202, OSC Activation and Operations. for security Time: - Time:- Time: -

COMPLETE or DIRECT completion of the NRC Data Sheet lAW ECG Att. 5 and PROVIDE to the Primary Init:

and Secondary Communicators (CM1/CM2) to inform Init:

Init:

- - Init:

EC the NRC as soon as possible.

Time: - Time: Time: - Time: -

NOTE: The 60 minute notification requirement is -

met when the ICMF is read to the NRC lAW EP-SA/HC-111-F6.

Prior to TSC activation, !E desired or WHEN required, THEN DIRECT IMPLEMENTATION I IMPLEMENT Init: Init:

Optional Optional - -

SM Accountability lAW Attachment 3 of this procedure.

Time: - Time: -

For Security based emergency, SEG may require modifications of associated actions/announcements.

If ERO callout was activated, PREPARE for EC turnover to the EDO OR ERM using the WebEOC EC Init: Init: Init: Init:

Status Briefing Board (or Attachment 2- EC - - - -

EC Emergency Status Briefing Form, of this procedure. Time:- Time: Time: - Time: -

As time allows, FAX completed Form to TSC.) -

(Salem fax is NETS 5114 and Hope Creek fax is at NETS 5216)

If needed, CONTACT unaffected station SM to Init: Init: Init: Init:

identify and REQUEST available support EC personnel. Time:- Time:- Time: - Time: -

Nuclear Common Page 5 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Until relieved by the EDO, lE Remote Response Center (RRC) Guideline, SH.OP-AM.TSC-0002, REMOTE RESPONSE CENTER (RRC)

OPERATIONS was implemented per directions in Attachment 10, THEN: [CM-HC.2007 -42]

PROVIDE overall direction (command & control) Init:

- Init:

SM and support to the RRC Leader (NETS X5135 or DID X2801). Time:

- Time:

- Time:-

PROVIDE periodic briefings to the RRC Leader .

TURNOVER command & control of the affected station's emergency response to a qualified SM or EDO from the affected station when the affected station has adequate resources.

Until relieved by the EDO, as needed/requested for accident mitigation (25R) or life saving (75R),

AUTHORIZE Emergency Dose.

(per OSC RP Response, NC.EP-EP.ZZ-0304)

ENSURE RAC works with the OSC and considers Init: Init: Init: Init:

dose savings to the public to expedite OSC team - - - -

SM dispatch.

Time: - Time: Time: Time: -

ENSURE backup actions are being planned; (OSC or TSC engineering staff).

ENSURE OSC Coordinator considers pre-staging teams at the control point while plans are being finalized.

lAW ECG Attachment 5, NRC Data Sheet and Completion Reference, ENSURE the NRC is notified of:

Significant changes in emergency or plant status Init:

- Init:

EC including equivalent or lower EALs exceeded.

Time:- Time: - Time: Time: -

Implementation of 10CFR50.54x (Refer to OP-M-101-111-1003, Section 4.7.2 as needed)

Non-emergency reportable conditions per RALs SM Continuous Actions on next page COORDINATE and PRIORITIZE OSC tasks in Init:_ lnit:_ lnit:_ lnit:_

SM conjunction with accident mitigation efforts. Time:_ Time:_

Time:_ Time:_

Nuclear Common Page 6 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ENSURE the Station Status Checklist (SSCL) is Init: Init: Init:

reviewed and approved for transmission to the states - - - Init:

EC every 30 minutes. Time:

- Time:

- Time: - Time:

Init: Init: Init:

If needed, CONTACT the NRC for Federal assistance - - - Init:

EC or Federal resources. Time: Time: Time: Time:

If needed to address plant conditions during a severe accident not specifically addressed in approved procedures or in the Severe Accident Guidelines, Init: Init: Init: Init:

IMPLEMENT/DIRECT implementation of the - - - -

SM Supplemental Severe Accident Management Time: - Time: - Time: Time: -

Guideline, SH.OP-AM.TSC-0001 and associated -

Technical Support Center Assist Guidelines, SC/HC.OP-AM. TSC-XXXX.

NOTE When classifying an emergency using the Fission Product Barrier Table, it is possible for conditions to degrade but for the point total to remain in the same classification. For example, a six (6) point SAE degrades to a ten (10) point SAE or a twelve (12) point GE degrades to a thirteen (13) point GE. In these cases, the proper method of informing the states and NRC of the classification update is through the use of an updated Station Status Checklist (SSCL). Init:

REVIEW the ECG for conditions that may require Classification Escalation or PAR Upgrade:

IF in the position of EC, and classification level is escalated, THEN, EXIT this procedure and IMPLEMENT the appropriate ECG attachment until directed back to this procedure.

Init: Init: Init: Init:

lE in the position of EC, and a General Emergency - - - -

SM was previously declared and conditions change Time: - Time: - Time: - Time: -

such that a PAR Upgrade is needed, THEN, IMPLEMENT a new ECG Attachment 4 and UPGRADE the PAR on the ICMF.

lE EDO/ERM is the EC, THEN, PERFORM classification verification check and FEEDBACK results to EC.

Nuclear Common Page 7 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

When SM relief is required, USE WebEOC or SM Attachment 2 of this procedure and PROVIDE Init:

- Init:

turnover to oncoming SM. Time:

- Time:- Time:- Time:-

Init: Init: Init: Init:

PROVIDE a control room crew update when the SM - - - -

SM has completed EC turnover to the EDO in the TSC. Time:- Time:- Time: - Time: -

When relieved as the EC:

ENSURE all SM steps of this procedure are Init:

- Init:

SM completed

If emergency is upgraded, PERFORM all SM Time:

- Time: - Time: - Time: -

ste s for the new u raded classification level.

IMPLEMENT NC.EP-EP.ZZ-0405 (Q), Emergency Init:

Termination/Reduction/Recovery for UE termination SM N/A N/A N/A as appropriate. Time:

WHEN the event is terminated, THEN ENSURE Init: Init: Init: Init:

appropriate steps in Attachment 1 - Documentation SM Checklist are completed. Time: Time: - Time: - Time: -

lE needed, AUTHORIZE deviations from Normal Work Practices In Emergencies. See Attachment 11 , Init: Init: Init: Init:

Allowable Deviations from Normal Work Practices In - - - -

EC Emergencies. Time: Time:- Time: Time:-

END - SM Actions Nuclear Common Page 8 of 46 Rev.23

NC.EP-EP.ZZ-01 02(Q) 5.2 Emergency Duty Officer (EDO) Actions: Initials NOTES

1. Should the Emergency Classification Level change, the EDO shall implement actions based on the new Emergency Classification Level.

2. After EC turnover to the ERM, the EDO shall continue to implement the EDO designated steps in Section 5.2.

3. Since the Rad Alert alarm is located in the Control Room, the SM directs all emergency status change announcements.

4. DID X5930 can be used to monitor Shift Manager/Security hostile action event communications.

ASSESS capability of the TSC to staff and be ready Capable of Capable of Capable of to activate within 90 minutes of an Alert or higher Activation? Activation? Activation?

emergency classification - (NOTE: staffing and Yes I No Yes I No Yes I No EDO Optional activation time could vary if severe weather conditions Init:- - Init:- - Init:- -

or acts of nature/terrorism were experienced at the Time:- Time: - Time: -

same time as the ERO callout)

Init: Init: Init:

EDO IMPLEMENT Attachment 6 and ACTIVATE the TSC Optional (required at SAE or higher classification) Time:-

At the discretion of the EDO, DESIGNATE an ERO Init: Init: Init:

member to implement Attachment 12, Organization Of

- - - Init:

EDO All-Call Extra Responders. Time:

- Time: - Time: - Time: -

INFORM affected station SM of all changes in AttSA AttSB AttSC EC emergency level and REQUEST page announcement N/A Init:

- Init:- Init:-

per appropriate attachment of this procedure. Time: - Time: - Time:-

COMPLETE or DIRECT completion of the NRC Data Sheet lAW ECG Att. 5 and PROVIDE to the Primary and Secondary Communicators (TSC1/TSC2) to Init: Init: Init: Init:

notify the NRC as soon as possible.

EC Time:- Time:- Time:_ Time:-

NOTE: The 60 minute notification requirement is met when the ICMF is read to the NRC lAW EP-SAIHC-111-F6.

Nuclear Common Page 9 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q) lE not previously completed and, IF desired or WHEN required,

THEN DIRECT the SM to implement Accountability lAW Attachment 3, Steps 1 thru 4 of this procedure.

Init: Init:

EDO

At 30 minutes after Accountability was Optional Optional - -

implemented, EDO shall COMPLETE Time: Time:

Accountability follow-up actions lAW Attachment 3, - -

Steps 5 of this procedure.

For Security based emergency, SEG may require modifications of associated actions/announcements.

Nuclear Common Page 10 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

If needed, CONTACT unaffected station SM to Init:

- Init:

EDO identify and REQUEST available support personnel.

Time: Time: Time: Time: -

lE Remote Response Center (RRC) Guideline, SH.OP-AM.TSC-0002, REMOTE RESPONSE CENTER (RRC) OPERATIONS was implemented per directions in Attachment 10, THEN,

PROVIDE overall direction (command & control) Init:

- Init:

EDO and support to the RRC Leader (NETS X5135 or DID X2801). Time: - Time:

- Time:

- Time: -

PROVIDE periodic briefings to the RRC Leader .

TURNOVER command & control of the affected station's emergency response to a qualified SM or EDO from the affected station when the affected station has uate resources.

As needed/requested for accident mitigation (25R) or life saving (75R), AUTHORIZE Emergency Dose.

(per OSC RP Response, NC.EP~EP.ZZ~0304)

ENSURE RAC works with the OSC and considers dose savings to the public to expedite OSC team Init: Init: Init: Init:

dispatch. - - - -

EDO

ENSURE backup actions are being planned; (OSC Time: - Time:

- Time:

- Time: -

or TSC engineering staff).

ENSURE OSC Coordinator considers pre-staging teams at the control point while plans are being finalized.

lAW ECG Attachment 5, NRC Data Sheet and Completion Reference, ENSURE the NRC is notified of:

Significant changes in emergency or plant status Init:

- Init:

EC including equivalent or lower EALs exceeded.

Time:

Implementation of 10CFR50.54x - Time:

- Time:

- Time: -

(Refer to OP-M-101-111-1003, Section 4.7.2 as needed)

Non-emergency reportable conditions per RALs After an initial PAR for a General Emergency has been made, IMPLEMENT NC.EP-EP.ZZ-0404(0), Init:

Protective Action Recommendations (PAR) Upgrades. -

PAGS that require a PAR Upgrade: Time: -

EC N/A N/A N/A

Projected TEDE Dose >1 ,000 (1.0E+3) mRem at 5 miles or 10 miles on a MIDAS SSCL page 2

Projected Thyroid Dose >5,000 (5.0E+3) mRem at 5 miles or 10 miles on a MIDAS SSCL e2 Nuclear Common Page 11 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

If needed, CONTACT the NRC for Federal assistance Init:- Init:- Init:- Init:-

EC or Federal resources. Time: - Time:

- Time: - Time: -

NOTE When classifying an emergency using the Fission Product Barrier Table, it is possible for conditions to degrade but for the point total to remain in the same classification. For example, a six (6) point SAE degrades to a ten (10) point SAE or a twelve (12) point GE degrades to a thirteen (13) point GE. In these cases, the proper method of informing the states and NRC of the classification update is through the use of an updated Station Status Checklist (SSCL). Init:

REVIEW plant status, radiological release conditions, and the EGG for conditions that may require Init: Init: Init: Init:

Classification escalation or PAR upgrade. !E - - - -

EC escalation/upgrade is being considered, THEN Time: Time: - Time: - Time: -

DIRECT SM and/or ERM to perform a -

classification/upgrade verification.

!E classification level is escalated, THEN, EXIT this Init:

- Init:

EC procedure and IMPLEMENT the appropriate EGG attachment until directed back to this procedure. Time: Time:- Time: - Time:-

ENSURE SM and unaffected station's SM or EDO are kept informed of emergency status changes such as:

Classification level Init:

- Init:

EDO

Onsite protective actions Time: - Time: - Time: - Time: -

Radiological releases

Emergency response facility activations ENSURE the Station Status Checklist (SSCL) is Init: Init: Init: Init:

reviewed and approved for transmission to the states - - - -

EC approximately every 30 minutes. May be delegated to Time: Time: - Time: - Time: -

TSS (page 1) and RAG (page 2) if desired. -

If ERMis the EC, USE procedure NC.EP-EP.ZZ- Init:

0404(0), Protective Action Recommendations (PAR) N/A N/A N/A -

EDO Upgrades, for peer checking PAR upgrades. Time:-

Upon arrival of an NRC emergency response team, Init: Init: Init: Init:

PROVIDE a status briefing and COORDINATE the - - - -

EDO integration of NRC team members within functional Time: - Time: - Time: - Time: -

areas of the TSC.

Nuclear Common Page 12 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Init: lnt: Init: Init:

Periodically (approximately every 30-60 minutes) , - - - -

EDO CONDUCT TSC facility leads briefings. Time: - Time: - Time: - Time: -

Periodically (approximately every 60- 90 minutes),

CONDUCT an "ALL FACILITY BRIEFING" by Init: Init: Init: Init:

providing the TSC Admin Support Supervisor with a EDO briefing time and DIRECT him/her to setup the "ALL Time: - Time: - Time: - Time:-

FACILITY BRIEFING" conference call.

When EDO relief is required, USE WebEOC or Init: lnit: Init:

Attachment 2 of this procedure and PROVIDE

- - - Init:

EDO turnover to oncoming EDO. Time: - Time: - Time: - Time:

Init: Init: Init: Init:

When relieved as the EC, ENSURE all EDO steps of - - - -

EDO the EDO Section of this procedure are completed.

Time: - Time:

- Time: - Time: -

Init: Init: Init: Init:

PROVIDE a TSC Staff update when the EDO has - - - -

EDO completed EC turnover to the ERMin the EOF.

Time:- Time: - Time:- Time: -

If emergency is upgraded, and the ERMis the EC, Init: Init: Init: Init:

PERFORM all EDO steps for the new upgraded EDO classification level. Time: - Time: - Time:- Time:-

If needed to address plant conditions during a severe accident not specifically addressed in approved procedures or in the Severe Accident Guidelines, Init: Init: Init: Init:

IMPLEMENT/DIRECT implementation of the - - - -

EDO Supplemental Severe Accident Management Time:- Time: - Time:- Time:-

Guideline, SH.OP-AM.TSC-0001 and associated Technical Support Center Assist Guidelines, SC/HC.OP-AM.TSC-XXXX.

Init: Init: Init: Init:

IMPLEMENT NC.EP-EP.ZZ-0405 (Q), Emergency - - - -

EC Termination/Reduction/Recovery, as appropriate.

WHEN the event is terminated, THEN ENSURE Init: Init: Init: Init:

appropriate steps in Attachment 1 - Documentation EDO Checklist are feted. Time:

- Time: - Time: - Time:

lE needed, AUTHORIZE deviations from Normal Init:_ Init: Init: Init:

Work Practices In Emergencies. See Attachment 11, - -

EC Allowable Deviations from Normal Work Practices In Emergencies. Time: - Time:

- Time: - Time:-

END - EDO Actions Nuclear Common Page 13 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q) 5.3 Emergency Response Manager (ERM) Actions: Initials NOTES 1 . Should the Emergency Classification Level change, the ERM shall implement actions based on the new Emergency Classification Level.

2. Since the Rad Alert alarm is located in the Control Room, the SM directs all emergency status change announcements.

3. DID X5930 or can be used to monitor Shift Manager/Security hostile action event communications.

ASSESS capability of the EOF to staff and be ready Capable of Capable of Capable of to activate within 90 minutes of an Alert or higher Activation? Activation? Activation?

Yes I No Yes I No Yes I No emergency classification - (NOTE: staffing and ERM Optional activation time could vary if severe weather conditions or acts of nature/terrorism were experienced at the Init:

- Init:

Time: Time: Time:

same time as the ERO callout) - - -

Init: Init:

ERM IMPLEMENT Attachment 7 and ACTIVATE the EOF Optional Optional (required at SAE or higher classification)

At the discretion of the ERM, DESIGNATE an ERO ERM member to implement Attachment 12, Organization Of Init:

- Init:

All-Call Extra Responders. Time:

- Time:

INFORM affected station SM of all changes in Att5A Att5B Att5C emergency level and REQUEST page announcement EC per appropriate attachment of this procedure. N/A Init:

- Init:- Init:-

Time: - Time: Time:-

INFORM EDO of all changes in emergency level -

COMPLETE or DIRECT completion of the NRC Data Sheet lAW EGG Att. 5 and PROVIDE to the Primary and Secondary Communicators (EOF1/EOF2) to Init: Init: Init:_ Init:_

EC notify the NRC as soon as possible.

NOTE: The 60 minute notification requirement is Time:

- Time:

met when the ICMF is read to the NRC lAW EP-SA/HC-111-F6.

If the event involves the activation of the Unified Command Center (UCC), DIRECT PSEG ERO personnel to fill the following positions within the UCC Init: Init: Init:

ERM lAW EP Aids 60 & 61:

Optional

Salem- Ops Liaison (off-duty SSM or TSS) Time: - Time:

- Time:

Hope Creek- Ops Liaison (off-duty SSM or TSS)

Security Liaison (Sec. Dir. or off-duty SSG)

RadPro Liaison RSM or Nuclear Common Page 14 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q) lAW ECG Attachment 5, NRC Data Sheet and Completion Reference, ENSURE the NRC is notified of:

EC

Significant changes in emergency or plant status Init:

- Init:

including equivalent or lower EALs exceeded.

Time: Time: Time: Time:

Implementation of 10CFR50.54x (Refer to OP-AA-1 01-111-1003, Section 4.7.2 as needed)

Non-emergency reportable conditions per RALs EC If needed, CONTACT the NRC for needed Federal Init:

- Init:

assistance or Federal resources.

After an initial PAR for a General Emergency has been made, IMPLEMENT NC.EP-EP.ZZ-0404(0),

Protective Action Recommendations (PAR)

Upgrades. Init:_

N/A N/A N/A EC PAGS that require a PAR Upgrade:

Time:_

Projected TEDE Dose >1 ,000 (1.0E+3) mRem at 5 miles or 10 miles on a MIDAS SSCL page 2

Projected Thyroid Dose >5,000 (5.0E+3) mRem at 5 miles or 10 miles on a MIDAS SSCL e2 ERM Continuous Actions on next page Nuclear Common Page 15 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

NOTE When classifying an emergency using the Fission Product Barrier Table, it is possible for conditions to degrade but for the point total to remain in the same classification. For example, a six (6) point SAE degrades to a ten (10) point SAE or a twelve (12) point GE degrades to a thirteen (13) point GE. In these cases, the proper method of informing the states and NRC of the classification update is through the use of an updated Station Status Checklist (SSCL). Init:

REVIEW plant status, radiological release conditions, and the ECG for conditions that may require Init: Init: Init: Init:

EC Classification escalation or PAR upgrade. IF - - -

escalation/upgrade is being considered, THEN Time: - Time: - Time: - Time:

DIRECT EDO and/or SM to perform a -

classification/upgrade verification.

IF classification level is escalated, THEN EXIT this Init: Init: Init: Init:

EC procedure and IMPLEMENT the appropriate ECG attachment until directed back to this procedure. Time:

- Time: - Time:

- Time:

ENSURE EDO is kept informed of emergency status changes such as:

Classification level Init:

- Init:

EC

Offsite protective actions Time: - Time: - Time: - Time:

Radiological releases

Emergency response facility activations ENSURE the Station Status Checklist (SSCL) is Init: Init: Init: Init:

reviewed and approved for transmission to the states - - - -

EC every 30 minutes. This may be delegated to SSM Time: - Time:- Time: - Time:

(page 1) and RSM (page 2) if desired. -

Upon arrival of an NRC emergency response team, Init: Init: Init: Init:

PROVIDE a status briefing and COORDINATE the - - - -

ERM integration of NRC team members within functional Time:- Time:- Time: - Time:

areas of the EOF. -

UPDATE both State Directors regularly and ENSURE data flow is satisfactory. OBTAIN information concerning any Protective Actions implemented by the States.

Init: Init: Init: Init:

ERM

New Jersey EOC Director- NETS x541 0 Time:- Time: - Time: - Time:

Delaware EOC Director- NETS x5412 -

As a minimum, update State Directors of any changes in Emergency Classification, PARs or Radiological Release Status.

Nuclear Common Page 16 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Init: Init: !nit: Init:

Time: - Time: - Time: - Time:

Init: Init: Init: Init:

Periodically (approximately every 30-60 minutes), - - - -

ERM CONDUCT EOF facility leads briefing.

Time: - Time: - Time: -

lE offsite radionuclide concentrations exist OR could potentially exist in excess of 10CFR20 Appendix B Init: Init: Init: Init:

limits, THEN RECOMMEND to the States of New ERM Jersey and Delaware that the ingestion pathway be Time:

- Time:- Time:- Time:

monitored.

When ERM relief is required, USE WebEOC or Init: Init: Init:

Attachment 2 of this procedure and PROVIDE

- - - Init:

ERM turnover to oncoming ERM. Time:

- Time:

- Time:- Time:

Init: Init: Init: Init:

IMPLEMENT NC.EP-EP.ZZ-0405 (Q), Emergency - - - -

EC Termination/Reduction/Recovery, as appropriate.

Time:-

WHEN the event is terminated, THEN ENSURE Init: !nit: Init: Init:

appropriate steps in Attachment 1 - Documentation ERM Checklist are completed. Time:

- Time:

- Time: - Time:

lE needed, AUTHORIZE deviations from Normal Work Practices In Emergencies. See Attachment 11, Init:

- Init:- Init: - Init:-

EC Allowable Deviations from Normal Work Practices In Time: Time: - Time: - Time: -

Emergencies. -

END - ERM Actions Nuclear Common Page 17 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q) 6.0 RECORDS Refer to Attachment 1, Documentation Checklist.

7.0 REFERENCES

7.1 References

PSEG Nuclear Emergency Plan

NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency

Response Plans and Preparedness in Support of Nuclear Power Plants.

NRC Security Advisory Basis Document, Notification- 20080626

Safeguards Advisory (SA-04-07) dated 6/18/04

Safeguards Advisory (SA-05-02) dated 1/26/05

NRC Bulletin 2005-02, EP and Response Actions for Security-Based Events

CM-HC.2007 B.5.b Commitment (70067198)

IN PO IER L 1-13-10, Nuclear Accident at the Fukushima Daiichi Nuclear Power Plant 7.2 Cross References

NC.EP-EP.ZZ-0405(0), Emergency Termination/Reduction/Recovery

Hope Creek/Salem Event Classification Guide (ECG)

HC.OP-AB.SEC-0001 (0) & SC.OP-AB.CR-0004(0), Security Event

HC.OP-AB.SEC-0002(0) & SC.OP-AB.CR-0005(0), Airborne Threat

SH.OP-AM.TSC-0002, Remote Response Center (RRC) Operations

SH.OP-AM.TSC-0001 ,Supplemental Severe Accident Management Guidelines (SSAMG)

SY-AA-1 01-1 08, Response to Suspicious Activity and Events Maliciously Directed at Plant Safety or Security

NC.EP-EP.ZZ-01 01 (0), Actions Required at Unaffected Station

NC.EP-EP.ZZ-0202(0), Operations Support Center (OSC) Activation and Operaitons

NC.EP-EP.ZZ-0901 (0), Onsite Security Response

NC.EP-EP.ZZ-0902(0), Assembly/Accountability/Evacuation

NC.EP-EP.ZZ-0903(0), Opening of Emergency Operations Facility (EOF)

EP Aid #060, Unified Command Center (UCC) Activation Checklist

EP Aid #061, Unified Command Center (UCC) Responsibilities 8.0 COMMITMENT DOCUMENTS CM-HC.2007 B.5.b Commitment (70067198)

Nuclear Common Page 18 of 46 Rev.23

NC.EP~EP .ZZ~01 02(Q)

ATTACHMENT 1 DOCUMENTAT ION CHECKLIST Page 1 of 1 Initials

1. ENSURE a Notification is created and the basis for the Termination/Recovery is included in the notification.

Notification #:

SM

2. COORDINATE with the station EP Manager (or designee) and COMPLETE the Event Review Checklist per EP-AA-120-F2 SM

3. COLLECT, REVIEW and FORWARD all completed ECG Attachments, Procedures, T&RMs, Forms, Logbooks, etc. and any supporting documentation to the Manager EP (MEP).

SM/EDO/ERM

4. REVIEW forwarded emergency documentation and any other relevant information for correct classification of event and corrective actions taken.

Station EPM/MEP

5. FORWARD the following documents to Record Retention:

Final Report lAW EP-AA-120- Emergency Plan Administration

EP-AA-120-F2- Event Review Checklist

EP-AA-125-1002-F01-DEP Observation Checklist,

Copies of ECG Emergency Attachments implemented by the ECs and communicators in all Emergency Response Facilities.

NC.EP-EP.ZZ-01 02- EC Response procedure completed by all ECs.

NC.EP-EP.ZZ-0405- Emergency Termination procedure

Log books maintained by the SM, EDO and ERM (If used instead of WebEOC).

AIIICMFs, NRC Data Sheets, and SSCLs transmitted during the emergency.

Other documents as per MEP discretion.

MEP Nuclear Common Page 19 of 46 Rev.23

NC. EP-EP .ZZ-01 02(Q)

ATTACHMENT 2 EC EMERGENCY STATUS BRIEFING FORM Page 1 of 2 NOTE Completion of this Attachment is optional. However, the information listed is useful for providing a thorough turnover to the oncoming EC. WebEOC EC Status Briefing Board is the preferred format for this information, but use of this form is acceptable. If conditions/time allows, fax this briefing form to the oncoming EC prior to starting a turnover briefing.

Plant: HC S1 S2

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 Yes _RPSA- EVAC All, 0-5 miles, downwind 5-10 +I- one sector and shelter remaining 5-1 0 Wind direction (from): No miles.

_HAB - SHELTER All, 0-5 miles, and MONITOR and PREPARE All 5-10 miles

_Default- EVAC All, 0-5 miles and MONITOR and PREPARE All 5-10 miles

d. Accountability called? Yes Time completed:

Results: No

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 20 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 2 EC EMERGENCY STATUS BRIEFING FORM Page 2 of 2

5. OSC activated? (_YES _NO ) Time Activated OSC Coord. _ _ _ _ __

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. Security Event details, were SEG Attachment 10 actions completed and what onsite protective actions have been implemented?

12. Status of NRC Data Sheet and Station Status Checklist (SSCL) update times:

13. Other:

Nuclear Common Page 21 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 3 ACCOUNTABILITY ACTIONS AND RESULTS Page 1 of 2 The SM should PERFORM steps 1 through 4 to Implement Accountability: Initials/Time

1. For an UNUSUAL EVENT, DIRECT Security Shift Manager (X2223) at the Security Center to implement procedure NC.EP-EP.ZZ-0902, Sections:

4.2, Automated Accountability

4.3, Accountability Report Generation --- I -

SM OR For an ALERT or higher, DIRECT Security Shift Manager (X2223) at the Security Center to implement procedure NC.EP-EP.ZZ-0902, Sections:

4.2, Automated Accountability

4.3, Accountability Report Generation

4.5, Evacuation --- I -

SM

2. DIRECT the other station's SM to implement NC.EP-EP.ZZ-01 01, ACCOUNTABILITY, Attachment 3.

Hope Creek (NETS X5234 or DID X3027) I Salem (NETS X5142 or DID X5200) --- I -

SM NOTE Accountability Implementation Time (AIT) is defined as the time that the below page announcement to "implement accountabilit " is made. I SM

3. DIRECT the following: (AIT +0 Min)

SOUND the Radiation Alert Alarm --- I -

SM AND ANNOUNCE TWICE --- I -

SM "ATTENTION ALL PERSONNEL, ATTENTION, ALL PERSONNEL, ALL ACCOUNTABILITY STATIONS IMPLEMENT ACCOUNTABILITY"

4. 20 minutes later, DIRECT the following: (AIT +20 Min after above announcement was made)

SOUND the Radiation Alert Alarm --- I -

SM AND ANNOUNCE TWICE --- I -

SM "ATTENTION ALL PERSONNEL, ATTENTION, ALL PERSONNEL, ALL ACCOUNTABILITY STATIONS COMPLETE ACCOUNTABILITY" Nuclear Common Page 22 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 3 ACCOUNTABILITY ACTIONS AND RESULTS Page 2 of 2 The EDO (SM if TSC not yet activated) should PERFORM step 5 to Complete Accountability:

Initials/Time NOTE IF the TSC has not yet been manned by the TSC security liaison, THEN Security will report the results of the accountability immediately to the Shift Manager (SM) at both stations.

EDO/SM

5. After 30 minutes has passed from the initial "Implement Accountability" announcement, COMPLETE the following Accountability followup actions:(AIT+30 min)

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 affected station's TSC Security Liaison and REQUEST accountability results. - I-EDO/SM Hope Creek- NETS X5214 or DID X3252 Salem - NETS X5117 or DID X2707

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

... Page individuals over the plant page.

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

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

... Request Security's assistance in locating unaccounted personnel. - I-EDO/SM

UPDATE Security as missing personnel are located. - I-EDO/SM

INITIATE search and rescue operations in accordance with NC.EP-EP.ZZ-0202, OSC Activation and Operations, as appropriate. - I-EDO/SM

!E Accountability was directed while in an Unusual Event (no OCA evacuation was directed) and the emergency is later upgraded to an ALERT or higher, THEN, DIRECT Security Shift Manager (X2223) at the Security Center to implement NC.EP-EP.ZZ-0902, Section 4.5, Evacuation. - I-EDO/SM

As the situation dictates and/or as radiological conditions permit and 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. - I-EDO/SM Nuclear Common Page 23 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 4 UNUSUAL EVENT ANNOUNCEMENT Page 1 of 2 Initials/Time A. ERO NOT ACTIVATED -IF the ERO is NOT activated, THEN Perform steps A, 1 -I- -

1. SOUND the Radiation Alert Alarm - -I- -

AND

2. ANNOUNCE Twice - -I- -

"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK- SALEM Unit 1 -SALEM Unit 2) IS (ARE) IN AN ciRClE cdRREC r ONi f(s)

UNUSUAL EVENT DUE TO: _______________________________________________________

3. REPEAT the Above Emergency Announcement over the Radio I

4. NOTIFY Security Shift Manager (X2223) at the Security Center of the UNUSUAL EVENT B. ERO ACTIVATED -If the ERO is ACTIVATED, THEN perform steps B, 1-4 I

1. SOUND the Radiation Alert Alarm I AND

2. ANNOUNCE Twice _ _I__

"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK- SALEM Unit 1- SALEM Unit 2) IS (ARE) IN AN ciRClE CORREC r ONil (s)

UNUSUAL EVENT DUE TO: _______________________________________________________

ALL PSEG PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA.

ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

3. REPEAT the Above Emergency Announcement over the Radio _ _.1 (Continued Next Page)

ATTACHMENT 4 Nuclear Common Page 24 of 46 Rev.23

NC.EP-EP.ZZ-01 02(Q)

UNUSUALEVENTANNOUNCEMENT Page 2 of 2

4. If NOT performed previously, DIRECT Security Shift Manager (X2223) at the Security Center to Implement the following procedures:

NC.EP-EP.ZZ-0901, Onsite Security Response

NC.EP-EP.ZZ-0902, Section 4.1 Assembly, DUE TO:

(read "DUE TO:" from above message)

NC.EP-EP.ZZ-0903, Opening of Emergency Operations Facility (EOF). __./

Nuclear Common Page 25 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT SA ALERT ANNOUNCEMENT Page 1 of 1 Initials/Time

1. SOUND the Radiation Alert Alarm __I

2. ANNOUNCE Twice _ _I "ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK- SALEM Unit 1 -SALEM Unit 2) IS (ARE) IN AN CIRCLE CORRECT UNIT(S)

ALERT DUE TO:

ALL PSEG PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA.

ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

3. REPEAT the Above Emergency Announcement over the Radio __ I

4. If NOT performed previously, DIRECT Security Shift Manager (X2223) at the Security Center to Implement the following procedures:

NC.EP-EP.ZZ-0901, Onsite Security Response

NC.EP-EP.ZZ-0902, Section 4.1 Assembly, DUE TO:

(read "DUE TO:" from above message) _ _ _ _ _ _ _ _ _ _ __

NC.EP-EP.ZZ-0903, Opening of Emergency Operations Facility (EOF). I Nuclear Common Page 26 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 58 SITE AREA EMERGENCY ANNOUNCEMENT Page 1 of 1 Initials/Time

1. SOUND the Radiation Alert Alarm

2. ANNOUNCE Twice __ ./

"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK- SALEM Unit 1 -SALEM Unit 2) IS (ARE) IN A CIRCLE CORRECT UNIT(S)

SITE AREA EMERGENCY DUE TO:

ALL PSEG PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA. ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

3. REPEAT the Above Emergency Announcement over the Radio __/

4. If NOT performed previously, DIRECT Security Shift Manager (X2223) at the Security Center to Implement the following procedures:

NC.EP-EP.ZZ-0901, Onsite Security Response

NC.EP-EP.ZZ-0902, Section 4.1 Assembly, DUE TO:

(read "DUE TO:" from above message) - - - - - - - - - - - -

NC.EP-EP.ZZ-0903, Opening of Emergency Operations Facility (EOF). ----'/

Nuclear Common Page 27 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 5C GENERAL EMERGENCY ANNOUNCEMENT Page 1 of 1 Initials/Time

1. SOUND the Radiation Alert Alarm __I

2. ANNOUNCE Twice _ _!

"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL.

(HOPE CREEK- SALEM Unit 1 -SALEM Unit 2) IS (ARE) IN A CIRCLE CORRECT UNIT(S)

GENERAL EMERGENCY DUE TO:

ALL PSEG PERSONNEL REPORT TO YOUR ASSIGNED ASSEMBLY AREA. ALL CONTRACTORS LEAVE THE SITE IMMEDIATELY.

3. REPEAT the Above Emergency Announcement over the Radio I

4. If NOT performed previously, DIRECT Security Shift Manager (X2223) at the Security Center to Implement the following procedures:

NC.EP-EP.ZZ-0901, Onsite Security Response

NC.EP-EP.ZZ-0902, Section 4.1 Assembly, DUE TO:

(read "DUE TO:" from above message) - - - - - - - - - - - -

NC.EP-EP.ZZ-0903, Opening of Emergency Operations Facility (EOF). __ / _

Nuclear Common Page 28 of 46 Rev.23

NC.EP-EP.ZZ-01 02(Q)

ATTACHMENT 6 ACTIVATION of the TSC Page 1 of 2 Initials/Time NOTE The TSC must be capable of staffing and activating within 90 minutes of an Alert or higher emergency classification . Staffing and activation time could vary if severe weather conditions or acts of nature/terrorism were experienced at the same time as the ERO callout.

ACTIVATION of the TSC is REQUIRED at a SAE or higher classification.

1.0 Prior To TSC Activation (i.e., Before Assuming Emergency Coordinator Duties):

1. ESTABLISH and MAINTAIN a chronological log of activity and events using WebEOC or a logbook. (If needed, OBTAIN TSC Administrative staff member to maintain the log.) - I-

2. If not already done, OBTAIN a briefing on the status of the emergency from the Shift Manager (SM). REFER to WebEOC EC Status Briefing Board or Attachment 2, EC Emergency Status Briefing Form for turnover points of discussion. _I_

3. DIRECT/ENSURE 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 _I_

4. PERFORM initial briefing of the TSC staff on emergency conditions and the following issues: (Full TSC staff briefing should be done after TSC has activated)

Plant/emergency conditions- Why are we here?

ESTABLISH TSC Activation target time - Should be within 90 minutes of Alert or higher classification. I

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

ENSURE key roles/funtions for TSC activation are covered:

TSC has either an EDO or TSS to provide command & control

TSC has at least one qualified communicator

TSC can support Radiological and Engineering assessment _I_

ATTACHMENT 6 Nuclear Common Page 29 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ACTIVATION of the TSC Page 2 of 2 Initials/Time

6. ACTIVATE the TSC as follows: (Communicator, RP and EC turnovers should be done coincident with each other)

DIRECT TSC communicators to "take turnover from the Control Room Communicators. Communications turnover does not have to be completed prior to TSC activation but should be in progress. - I-

DIRECT RAC to "take turnover" of dose assessment from the SRPT

CONTACT the Shift Manager and COMPLETE EC turnover:

~ VERIFY current plant/emergency status. - I-

~ DETERMINE which EDO/EC steps in Section 5.2.a and 5.2.b, of this procedure are completed and which steps will be turned over for completion. _I_

~ ENSURE timing and responsibility for next SSCL and/or NRC data sheet are coordinated. - I-

~ With SM concurrence, ASSUME the EC function and DECLARE TSC activated. - I-2.0 Upon Assuming Emergency Coordinator Duties. the EDO Should:

1. ANNOUNCE to the TSC staff that the TSC is activated, the effective time and that you are the emergency coordinator. - I-

2. ANNOUNCE (over the plant page) "THE TSC IS ACTIVATED AND IS THE EMERGENCY COORDINATOR" _I_

3. NOTIFY ERM of TSC activation and PROVIDE a brief status update. - I-

4. IMPLEMENT Sections 5.2, EDO Actions, of this procedure. - I-Nuclear Common Page 30 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 7 ACTIVATION of the EOF Page 1 of 3 Initials/Time NOTE The EOF must be capable of staffing and activating within 90 minutes of an Alert or higher emergency classification. Staffing and activation time could vary if severe weather conditions or acts of nature/terrorism were experienced at the same time as the ERO callout.

ACTIVATION of the EOF is REQUIRED at a SAE or higher classification. I 1.0 Prior To EOF Activation (i.e., Before Assuming Emergency Coordinator Duties):

1. ESTABLISH and MAINTAIN a chronological log of activity and events using WebEOC or a logbook. - I-

2. DIRECT Emergency Preparedness Coordinator (EPC) to implement NC.EP-EP.ZZ-0401, EPC Response. - I-

3. OBTAIN a briefing on the status of the emergency from the Emergency Duty Officer (EDO). REFER to WebEOC EC Status Briefing Board or Attachment 2, Emergency Status Briefing Form for points of discussion. - I-

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

Radiological Support Manager (RSM)

Site Support Manager (SSM)

Technical Support Manager (TSM)

Administrative Support Manager (ASM) - I-

5. ENSURE the Public Information Liaison (PIL) is provided with plant and emergency status information both prior to and after EOF activation. - I-

6. PROVIDE initial briefing to the EOF staff on emergency conditions and the following issues:

Plant conditions

Introduce section leads (SSM, RSM, TSM, ASM, NJ & DE Leads)

Noise control

ASM provides administrative and IT services

REQUEST staff to synchronize all EOF clock and personnel watches with SPDS data time - I-Nuclear Common Page 31 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 7 ACTIVATION of the EOF Page 2 of 3 Initials/Time

7. PERFORM periodic EOF leads briefings to exchange information lAW, "EOF Briefing Checklist." _I_

8. PERFORM periodic summary briefings for the entire EOF staff regarding current emergency events/status changes following a leads briefing. - I-

9. PROVIDE an emergency status briefing and COORDINATE the integration of NRC team members within functional areas of the EOF upon arrival of an NRC emergency response team. - I-

10. PROVIDE 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. - I-

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

12. DIRECT ASM to assure continuity of personnel and resources for 24-hour operation of all (onsite and offsite) emergency response facilities. - I-

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

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, EPC EOF/EPA TSC). - I-

ENSURE EOF Communicators and Radiological Assessment Staff are ready to assume communications and notification responsibilities from the TSC. This includes coordination of requirements for the "Station Status Checklist", NRC Updates, and Offsite Dose Assessment. - I-

14. ACTIVATE the EOF as follows: (Communicator, RP and EC turnovers should be done coincident with each other)

DIRECT EOF communicators to "take turnover" from the TSC Communicators. Communications turnover does not have to be completed prior to EOF activation but should be in progress. - I-

DIRECT RSM to "take turnover" of dose assessment from the RAC. - I-(Continued on next page)

Nuclear Common Page 32 of46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 7 ACTIVATION of the EOF Page 3 of 3 Initials/Time

CONTACT the EDO and TAKE EC turnover. - I-

VERIFY current plant/emergency status. I

DETERMINE which EC steps in Section 5.3.a and Section 5.3.b, of this procedure are completed and which steps will be turned over for completion. - I-

ENSURE timing and responsibility for next SSCL and/or NRC data sheet are coordinated - I-

With EDO concurrence, ASSUME the EC function and DECLARE the EOF activated. I

DIRECT the EDO to announce (over the plant page):

"THE EOF IS ACTIVATED AND

____________________ IS THE EMERGENCY COORDINATOR" I 2.0 Upon Assuming Emergency Coordinator Duties. the ERM Should:

1. ANNOUNCE to the EOF staff that the EOF is activated, the effective time and that you are the EC. - I-NOTE New Jersey has responsibility for notification and communications with the contiguous (ingestion pathway) States of Pennsylvania and Maryland.

I

2. NOTIFY state directors of EOF activation and PROVIDE a brief status update.

(NJ Director- NETS X5410; DE Director- NETS X5412) _ /_

3. IMPLEMENT Sections 5.3, ERM Actions, of this procedure. - I-Nuclear Common Page 33 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 8 COMMUNICATIONS AVAILABILITY GUIDANCE- HOPE CREEK Page 1 of 2

Background:

A Beyond Design Basis External Event (BDBEE) such as a Flood, Hurricane, Tornado, or Earthquake resulting in a Station Blackout (SBO) or Extended Loss of AC Power (ELAP) will result in significant communication systems challenges. The below guidance provides a summary of potential communication systems availability and usage guidance.

NOTE Many/most of the PSEG Nuclear communication systems have multiple power supplies to increase reliability. Continued system availability after a BDBEE resulting in an ELAP will depend on the type of damage inflicted by the BDBEE. Do not assume the loss of a communications system without first checking system operation.

COMMO SYSTEM PRI POWER B/U POWER FLEXPWR? PRIMARY USAGE NOTES HC UHF Radio Non 1E (1 BJ484) fed by Battery backed - Non 1E 125 Yes-FLEX Onsite communciations The portions of the UHF Radio System outside 10B313 MCC- Class 1E VDC Switchgear 1OD486 Power from between CR and in- the HC power block will be disabled per Alt. 1OB 1OB222 after plant/OSC personnel. of HC.OP-AB.ZZ-0135 when the UHF Control Section 5.3 of HC- Room radio console is transferred to DC Remote OP-EO.ZZ-0401 mode.

is complete.

HC Public Address 1E panel 1OJ496 fed by Battery backed - Class 1E 125 Yes-FLEX Onsite communciations Portions of this system may be OOS based on 10B411 MCC -Class 1E VDC Switchgear 1OD41 0 Power from between CR and in- damage from the BDBEE.

(Gaitronics) 10B411 feeds plant/OSC personnel and 1OJ496 per HC- Security Personnel OP-EO.ZZ-0401, Section 5.2

1. Communications with 4. In an ELAP, Satellite phones may be the only HC Satellite Phones in CR, 1E Instrument Panel 1BJ481 11E Instrument Panei1BJ481 Yes-FLEX Offiste Response methods for the Salem and Hope Creek SMs OSC, TSC, EOF backed by inverter 1BD481 Power from Organization (OROs) at to communicate to ensure actions are EOF Sat phones powered by EEOF Sat phones powered by 10B421 feeds 2. Between Salem & coordinated.

non-vital EERC power non-vital EERC power that is 1BD481 inverter Hope Creek Stations 5. All ERF Satellite phone #s are on NETS UPS backed and has per HC-OP- 3. Between Emergency Quick Reference Directory - EP Aid - 004 Emergency Diesel if EO.ZZ-0401, Response Facilities (This includes NJ and DE) available.based on BDBEE Section 5.2 (ERFs) 6. Each ERF has at least one portable satellite afffects. phone No FLEX power for EOF Sat phones 900MHz Radio system Non-1E 120VAC panel SC230- Panel SC230-1DISCMMAIN1Y No Used for onsite and offsite Major components in MET Tower building in 1DISCMMAIN1Y is UPS and diesel backed field monitoring teams to OCA (SCCM-1 GENCME70) talk with TSC and EOF Nuclear Common Page 34 of46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 8 COMMUNICATIONS AVAILABILITY GUIDANCE- HOPE CREEK p age 2 0 f2 COMMO SYSTEM PRIPOWER B/U POWER FLEXPWR? PRIMARY USAGE NOTES NETS - Nuclear Emergency Commercial 120V EERC UPS and EERC Diesel No Emergency 1. Most onsite NETS circuits run through Telephone System- Privately House Power Generator Communications with telephone building next to sallyport ..

controlled PSEG telephone OROs and between ERFs 2. System used diverse pathways such as fiber, exchange microwave, & buried cable,

3. Main system components housed in EERC

4. All NETS #s can be found on NETS Quick Reference Directory - EP Aid - 004 (This includes NJ and DE)

CENTREX - (also refered to as Non-1E Telephone Bldg AC Telephone Bldg UPS Power No Backup to NETS 1. Verizon controlled PSEG exchange - draws ESSX) -- Dist Panel S1230- Panel SCCM-1DIS1F6XLHAYB dial tone (973)from Newark, NJ area.

DIS1 F6XL20Y fed from has manual X fer switch to 2. Major onsite components in Telephone Bldg Telephone Bldg UPS Power select an alternate power next to Sallyport.

Panel SCCM-1DIS1F6XLHAYB source and is also Diesel Gen 3.. All CENTREX #s can be found on NETS backed (SCCM-1CME53) Quick Reference Directory - EP Aid - 004 DID (Direct Inward Dial) Same as CENTREX Same as CENTREX No Backup to NETS and 1. Verizon controlled local exchange - draws dial CENTREX tone (856) from Salem Area.

2. Major components in Telephone Bldg next to Sallyport 3 .. DID emergency response position #s can be found on NETS Quick Reference Directory- EP Aid- 004 NAWAS (National Attack Same as CENTREX Same as CENTREX No Backup method for Owned and maintained by DEMA - Delaware Warning & Alert System contacting State of Emergency Management Agency Delaware EMRAD (Emergency Radio) Non-1E 120VAC None No Backup method for Owned and maintained by NJSP - New Jersey contacting State of New State Police, Office of Emergency Management.

Jersey FTS - Federal DC Power Diesel Generator and battery No PSEG uses to 1. Major components in Telephone Bldg next to Telecommuincations System- backed 0 non-1 E communicate emergency Sallyport Dedicated NRC phone system info to NRC. NRC uses to 2. NRC contact #sin ECG Attachment 6, communicate between Communicators Log.

different functional areas. 3. Uses Verizon microwave Sound Powered Phones None (Voice Powered) None (Voice Powered) N/A Backup system only in Portions of this system may be OOS based on select areas of power block damage from the BDBEE Nuclear Common Page 35 of46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 9 COMMUNICATIONS AVAILABILITY GUIDANCE - SALEM Page 1 of 2

Background:

A Beyond Design Basis External Event (BDBEE) such as a Flood, Hurricane, Tornado, or Earthquake resulting in a Station Blackout (SBO) or Extended Loss of AC Power (ELAP) will result in significant communication systems challenges. The below guidance provides a summary of potential communication systems availability and usage guidance.

NOTE Many/most of the PSEG Nuclear communication systems have multiple power supplies to increase reliability. Continued system availability after a BDBEE resulting in an ELAP will depend on the type of damage inflicted by the BDBEE. Do not assume the loss of a communications s stem without first checkin s stem o eration.

COMMO SYSTEM PRIPOWER B/U POWER FLEXPWR? PRIMARY USAGE NOTES Salem UHF Radio Manual X fer Switch: 1A/2A 125V battery bus power Yes- FLEX Power from Onsite For a predicted Hurricane Storm Surge > 3 feet Normal - Class 1E UPS is supplied to the 1A/2A Vital FLEX 230V MCC to the communciations above site grade, the portions of the UHF Radio 115V supplied power from Instrument Bus Inverter, 1A/2A 125V battery bus between CR and in- System outside the Units power block will be 1A/2A Vitallnst Bus 11NV1A5YB /21NV2A5YB which then supplies power to plant/OSC personnel. disabled per SC.OP-AM.FLX-0050 when the Class 1E UPS and coverted UHF Control Room radio is transferred to DC Emergency - Class 1E to 115V AC power for the Remote.

115V 1/2 ASDS distribution 1A/2A Vital Instrument Bus panel supplied from ASDS per S1.0P-FS.FLX-0005 Inverter Salem Public Address Class 1E UPS 115V 1C/2C 125V battery bus power Yes- FLEX Power from Onsite Portions of this system may be ODS based on supplied power to 12/22 is supplied to the Unit 1 I Unit 2 FLEX 230V MCC to the communciations damage from the BDBEE.

(Gaitronics) MAC panels. Essential Controls Inverters 1C/2C 125V battery bus between CR and in-11NV1 C6YC /21NV2C6YC which then supplies power plant/OSC personnel to the Essential Controls and Security Inverters and coverted to Personnel 115V AC for 12/22 MAC panels per S1.0P-FS.FLX-0005 Yes- For Control Room and 7. In an ELAP. Satellite phones may be the only Salem Satellite Phones in CR, For Control Room and OSC For Control Room and OSC OSC phones. FLEX Power 1.Communications methods for the Salem and Hope Creek SMs OSC, TSC, EOF phones - 1A 115V Vital Ins! phones - 1A 115V Vital Ins! Bus from FLEX 230V MCC to the with Offiste Response to communicate to ensure actions are Bus backed by inverter 11NV1A5YB 1A/2A 125V battery bus Organization (OROs) coordinated.

which then supplies power to 2. Between Salem & B. All ERF Satellite phone #s are on NETS Quick For TSC Sat phones - Non- TSC Sat phones - TSC Emerg Class 1E UPS and is Hope Creek Stations Reference Directory - EP Aid - 004 (This Vitai120VAC power from Diesel will feed Panel CFBB6 if coverted to 115V AC power 3. Between includes NJ and DE) panel CFBB6 in "B" available for the 1A/2A Vital Instrument Emergency 9. Each ERF has at least one portable satellite Building. Bus per S1.0P-FS.FLX- Response Facilities phone EOF Sat phones powered by 0005 (ERFs)

EOFSat phones powered UPS backed EERC power. Has No FLEX power for TSC or by non-vital EERC power Emerg Diesel if available.based EOF Sat phones on BDBEE afffects.

Nuclear Common Page 36 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 9 COMMUNICATIONS AVAILABILITY GUIDANCE - SALEM p age 2 0 f2 COMMO SYSTEM PRI POWER B/U POWER FLEXPWR? PRIMARY USAGE OTES 900MHz Radio system Non-1E 120VAC panel SC230- Panel SC230-1DISCMMAIN1Y No Used for onsite and offsite Major components in MET Tower building in 1DISCMMAIN1Y is UPS and diesel backed field monitoring teams to OCA.at base of MET Tower.

(SCCM-1GENCME70) talk with TSC and EOF NETS - Nuclear Emergency Commercial 120V EERC UPS and EERC Diesel No Emergency 1. Most onsite NETS circuits run through Telephone System- Privately House Power Generator Communications with telephone building next to sallyport..

controlled PSEG telephone OROs and between ERFs 2. System used diverse pathways such as fiber, exchange microwave, & buried cable,

3. Main system components housed in EERC, non-1 E structure.

4. All NETS #s can be found on NETS Quick Reference Directory - EP Aid - 004 (This includes NJ and DE)

CENTREX - (also refered to as Non-1E Telephone Bldg AC Telephone Bldg UPS Power No Backup to NETS 1.Tele Building power fed from #1 or #2 Mise 2.

ESSX) -- Dist Panel S1230- Panel SCCM-1DIS1F6XLHAYB Yard Equip Control Center. Verizon controlled DIS 1F6XL20Y fed from has manual X fer switch to 2. PSEG exchange - draws dial tone (973)from Telephone Bldg UPS Power select an alternate power Newark, NJ area.

Panel SCCM-1DIS1F6XLHAYB source and is also Diesel Gen 2. Major onsite components in Telephone Bldg backed (SCCM-1CME53) next to Sallyport.

3.. All CENTREX #scan be found on NETS Quick Reference Directory - EP Aid - 004 DID (Direct Inward Dial) Same as CENTREX Same as CENTREX No Backup to NETS and 1. Verizon controlled local exchange - draws dial CENTREX tone (856) from Salem Area.

2. Major components in Telephone Bldg

3. DID ERO position #s can be found on NETS Quick Reference Directory - EP Aid - 004 NAWAS (National Attack Same as CENTREX Same as CENTREX No Backup method for 1 , Owned and maintained by DEMA - Delaware Warning & Alert System contacting State of DE. Emergency Management Agency EMRAD (Emergency Radio) Non-1E 120VAC None No Backup method for 1, Owned and maintained by NJSP - New Jersey contacting State of NJ State Police, Office of Emergency Management.

FTS - Federal DC Power Diesel Generator and battery No PSEG uses to 1. Major components in Telephone Bldg next to Telecommuincations System- backed 0 non-1 E communicate emergency Sallyport Dedicated NRC phone system info to NRC. NRC uses to 2. NRC contact #s in ECG Attachment 6, communicate between Communicators Log.

different functional areas. 3. Uses Verison microwave Sound Powered Phones None (Voice Powered) None (Voice Powered) N/A Backup system only in Portions of this system may be OOS based on select areas of power block damage from the BDBEE Nuclear Common Page 37 of46 Rev.23

NC.EP-EP.ZZ-01 02(Q)

ATTACHMENT 10 SECURITY EMERGENCY GUIDELINE (SEG)

Page 1 of 5 Initials/Time CAUTION The Shift Manager (SM) should ensure actions specified in this attachment are immediately implemented for any actual or imminent attack (Hostile Action). For any actual or imminent attack, prompt actions specified below should not be delayed but should be performed immediately even if an emergency has not yet been classified or declared. 1 NOTE During an actual or imminent hostile action, a security posture will be implemented which includes a "Take Cover and Shelter-in-Place" action by all ONSITE personnel. This will inhibit many individuals from reporting to ERO positions/locations and Acountability Stations until safe passage(s) can be established. I NOTE (Important Security Contact Phone #s)

Security Center- Security Shift Manager: NETS 5136 DID 2223 SAS- Secondary Alarm Station: NETS 513815177 DID 2255 CAS- Central Alarm Station: NETS 506315033 DID 2648 Unified Command Center(@ EERC): NETS 5090 DID 3737 SASICAS open conference line NETS 4-5930 DID 5930 I

1. ENTRY CONDITIONS Security based emergency is occurring or imminent. (CONTINUE these actions until the security threat is averted or other specific direction is provided in response to the event).

--- I -

NOTE As practical and as time allows, both Salem and Hope Creek SMs should concur on protective actions and emergency classification levels for security events. I

2. PROMPT ACTIONS 2.1. IF not previously done; CALL Communicators to the Control Room AND (Salem Only), CALL SRPT to the Control Room. _ _I _

2.2. If response is not possible, IDENTIFY personnel presently in the Control Room to be used as Communicators. _ _I _

(Prompt Actions are continued on next page)

Nuclear Common Page 38 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 10 SECURITY EMERGENCY GUIDELINE (SEG)

PAGE20F5 Initials/Time 2.3. ENSURE radio in the Control Room is monitoring security radio channel(s).

- -I -

2.4. ENSURE CRS is implementing appropriate abnormal procedure "SECURITY EVENT or AIRBORNE THREAT" which will provide specific directions on when to Trip/Scram the units (if needed) as well as page announcements associated with specific onsite protective actions. I 2.5. Owner Controlled Area (OCA) Evacuation OR Shelter-In-Place:

2.5.1. lE OCA Evacuation is needed or desired, THEN, in coordination with other station's SM, DIRECT Security in SAS to implement OCA Evacuation per NC.EP-EP.ZZ-0902, Section 5.5, Evacuation. I 2.5.2. IF personnel in the OCA have not been evacuated and IF needed for their protection, THEN, in coordination with other station's SM, DIRECT Security in SAS to make the following page announcement using the OCA siren system page announcement capability:

"Attention all personnel, Attention all personnel. A credible security threat exists at the station. All personnel take immediate cover and shelter in place until further notice" (Repeat)

- -I -

2.6. lE notified by security or by fire protection of a loss of the command and control function (defined in PRECAUTIONS AND LIMITATIONS section) at the other (affected) station due to a catastrophic security event, THEN DECLARE a General Emergency lAW EAL HG4.1 and ENSURE ICMF specifies that a "Hostile Action has resulted in a Loss of Facility Control at the other station". - I-2.7. EXIT this procedure and CLASSIFY the security event in coordination with other station's SM. WHEN Security event CLASSIFICATION is complete, PROCEED to the next section - 3. SUBSEQUENT ACTIONS. - I-Nuclear Common Page 39 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 10 SECURITY EMERGENCY GUIDELINE (SEG)

Page 3 of 5

3. SUBSEQUENT ACTIONS 3.1. lE events at the other station have resulted in a loss of command and control at that station, as defined in PRECAUTIONS AND LIMITATIONS section, THEN DIRECT an SRO (work control SRO or STA) to report to the Fire Department Office in the NOSF and ACTIVATE the RRC per Guideline titled, Remote Response Center (RRC) Operations, SH.OP-AM.TSC-0002. - I-3.2. CONSULT with the security supervisor and as the security events change and in coordination with the other Stations SM:

MODIFY onsite protective action page announcements made from the Security Threat or Airborne Threat ABs as needed. - I-

ENSURE any onsite page announcements regarding personnel movement are modified as needed based on the ongoing Security Threat or Events.

- I-3.3. As needed, DIRECT that onsite protective action page announcements made lAW abnormal procedure "SECURITY EVENT or AIRBORNE THREAT",

be periodically re-broadcast over the station page system. I 3.4. During a security event, DIRECT security to periodically re-broadcast the OCA protective action page announcement lAW Attachment 10 Step 2.5.2 - I-3.5. IF/WHEN, Assembly or Accountability and Evacuation is required by Section 5.1 or 5.2 of this procedure, THEN CONSIDER delaying or modifying associated page announcements or actions based on the type of security event that is in progress and based on the protective actions already taken:

COORDINATE revised or new onsite protective action announcements with the other station's SM. I

CONSULT with Security to determine if Assembly, Accountability, or Evacuation can or should be implemented.

- I-

CONSIDER use of alternate assembly locations (e.g., Hope Creek Unit 2 Reactor Building, Material Center, "B" Building).

- I-

CONSIDER leaving personnel in their current office I shop areas. - I-Continued on next page Nuclear Common Page 40 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 10 SECURITY EMERGENCY GUIDELINE (SEG)

Page 4 of 5 (Continued)

CONSIDER potential alternate evacuation routes for EXITING SITE:

Via the Material Center

Via the South Sally Port

Via water/aircraft - I-

MODIFY plant page announcements for both stations as needed to maximize the safety of the plant and plant personnel. - I-3.6. (Salem Only) START Unit 3 if needed to provide additional backup power. - I-3.7. (HOPE CREEK ONLY) WHEN the OSC is staffed, THEN DIRECT the OSCC to have the Hope Creek TSC ventilation system place in Recirculation Mode. (NC.EP-EP.ZZ-0201(0), Attachment 1) - I-3.8. (SALEM ONLY) WHEN the OSC is staffed, THEN DIRECT the OSCC to have the Salem TSC ventilation placed in the "Operations During Toxic or Chemical Release" lineup. (SC.OP-SO.TSC-0051) I 3.9. IF Onsite personnel have been directed to, "take cover and shelter-in-place" THEN, DIRECT the following page announcement be made every two (2) hours while "sheltering-in-place";

Attention All Personnel Sheltering in Place, If you have a phone available at your location, contact extension 3030 and leave a message with your name, present location and phone number. - I-Continued on next page Nuclear Common Page 41 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

ATTACHMENT 10 SECURITY EMERGENCY GUIDELINE (SEG)

Page 5 of 5 NOTE The area adjacent to the EOF at the EERC in Salem City is designated as the Alternative Emergency Response Facility (AERF) for onsite ERO Responders if the site is not accessible. I 3.1 O.IF a HOSTILE ACTION is occurring or has occurred as reported by Security THEN, in coordination with the other station's SM, DIRECT the Security Supervisor in SAS to request LAC Police to:

Block off the access road

DIRECT all PSEG Emergency Responders to report to the EOF at the EERC (Environmental & Energy Resource Center)in Salem City. - I-REQUEST LAC Police to have offsite emergency responders such as law enforcement, fire fighters and emergency medical personnel STAGE support equipment and personnel at the LAC municipal complex or other offsite location as selected by the offsite Incident Commander or designee. --- I -

3.11.1MPLEMENT I RETURN to Section 5.1, SM Actions, of this procedure. --- I -

Nuclear Common Page 42 of 46 Rev.23

NC.EP-EP.ZZ-01 02(Q)

Attachment 11 ALLOWABLE DEVIATIONS FROM NORMAL WORK PRACTICES IN EMERGENCIES Page 1 of 2

1. The Shift Manager or Emergency Coordinator may authorize deviations from normal work practices in a declared Emergency.

These deviations are authorized in existing PSEG Nuclear procedures and are summarized in page 1 of this Attachment.

2. When a Site Area Emergency or General Emergency is declared, deviations from normal processes outside of existing PSEG Nuclear procedures may be authorized by the Shift Manager or Emergency Coordinator, or designee, in order to take action to restore core cooling, mitigate an off-site release in progress, or maintain spent fuel pool cooling, using page 2 of this Attachment.

Process Area Allowed Deviations Applicable Procedure Deviation from Deviation from Technical Specifications or license condition to protect the public health OP-AA-1 01-111-Technical and safety- use of 10CFR50.54(X): 1003 Specifications or The SRO with overall command and control shall make the decisions to deviate from License Condition a procedure or Technical Specification to protect the public health and safety. Such departures shall meet the following criteria:

No equivalent action consistent with the license conditions or Technical Specifications is immediately apparent.

Action is immediately required

The departure is reasonable based on the information available at the time

The departure is the minimum necessary to protect the public health and safety

The departure is taken only for the duration of the emerg_ency situation Work Planning I For "(1 )" priority emergency work (as determined by the Shift Manager or Designee) it is WC-AA-106 Priorities permissible to have the work in progress, under the direction of the First Line Supervisor using approved Procedures I Processes where possible, while the Work Order Package is being prepared. Additional supervision I oversight is required to ensure adequate control of the work activities in the absence of a work package:

Work Priority (1)- Emergency:

Work having an immediate and direct impact on the health and safety of the general public or plant personnel,

Pose a significant industrial hazard,

Require immediate attention to prevent the deterioration of plant condition to a possible unsafe or unstable level,

Unit reliability related work during Maximum Emergency Generation Alert Condition .

Loss of Site FLEX Capability Conduct of Maintenance Planning Performance of Work During Emergency or Abnormal Operating MA-AA-716-01 0 Maintenance Work Conditions:

in an Emergency Mitigation of an emergency, where immediate attention is required to protect the health and safety of the general public, to correct a significant industrial safety hazard, or to prevent the deterioration of plant conditions to a possible unsafe or unstable level, shall always allow work to begin before the generation of documentation (notifications, minor work order, or a normal work order).

Planning, reviews, and documentation activities will normally be performed in parallel with corrective actions or as soon as plant conditions allow.

Where maintenance activities are directed as an emergency, those activities shall be documented after the fact and receive the same degree of review as if they had been preplanned.

The Plant Manager or Shift Manager may direct maintenance activities to be performed without a Work Document.

Equipment/ Utilize Abnormal Component Position Sheet (ACPS) to document approval, positioning OP-AA-108-101 Component Control and restoration of abnormally positioned components.

Emergency In an emergency, the On-Duty Shift Manager (SM) can authorize the repositioning of a OP-AA-109 Tagging Boundary tagged component if it presents an immediate challenge to the safety of personnel or Control plant equipment. Prior to component operation, all personnel shall be verified clear of affected equipment, and, following component manipulation, all personnel signed on the WCD shall be notified Radiation Emergency Exposures above normal Administrative Limits can be authorized per E-Pian RP-AA-203 Protection Procedure: &

Emergency

Up to 25 Rem TEDE to mitigate the accident NC. EP-EP .ZZ-0304 Exposures

Up to 75 Rem TEDE to save-a-life Industrial Safety No deviations specified NONE Nuclear Common Page 43 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Attachment 11 ALLOWABLE DEVIATIONS FROM NORMAL WORK PRACTICES IN EMERGENCIES Page 2 of 2 When a Site Area Emergency or General Emergency is declared, deviations from normal processes outside of existing PSEG Nuclear procedures may be authorized by the Shift Manager or Emergency Coordinator, or designee, in order to take action to restore core cooling, mitigate an off-site release in progress, or maintain spent fuel pool cooling, using this Attachment.

Consider the use of 10CFR50.54(x) when using this Attachment (refer to OP-AA-1 01-111-1 003).

Date~ime: _______________________________________________________________

0 Indicates deviations from normal work processes Configuration Control Work Process CJ Clearance/Equipment Tagging CJ Work Order Process CJ Procedure (used as status control CJ Manual Process mechanism) CJ CJ Boundary Control CJ Radiation Protection Industrial Safety CJ RP Job Coverage CJ Working at heights CJ Dose Limits CJ Working over or near water CJ Turn Back Dose/Dose Rate CJ Heat Stress CJ Protective Clothing/Contamination Control CJ PPE CJ CJ Electrical Safety CJ List minimum requirements required for each deviation indicated:

Approved by SM/EC Post-job debrief (for example: describe the as-found plant conditions, actions taken, as-left plant conditions):

Reviewed by OSCC/SM/EC Nuclear Common Page 44 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Attachment 12 ORGANIZATION OF ALL-CALL EXTRA RESPONDERS Page 1 of 2 On-Site Facilities

1. Once all on-site positions have been staffed DIRECT remaining personnel to mustering area(s). Below are some suggestions:

Hope Creek Cafeteria (Capacity: 90)

Hope Creek General Purpose Room (Capacity: 84)

Salem Cafeteria (Capacity: 79)

Salem Lobby Conference Room (Capacity: 46)

Processing Center Auditorium (Capacity: 294)

NHQ/LDC Cafeteria (Capacity: 207)

2. CONTACT the OSC (Hope Creek ext. 3123; Salem ext. 2518) to inform them of the mustering location for their extra responders.

3. CONTACT the Control Point (Hope Creek ext. 3490; Salem ext. 2608) to inform them of the mustering location for their extra responders.

4. DIRECT the individuals in the mustering area(s) to sign-in on Page 2 of this attachment.

5. PROVIDE completed Mustering Area Sign-In sheet(s) to the Emergency Operations Facility (EOF) (call Ext. 2375 for further instructions).

1. Once all EOF positions have been staffed DIRECT remaining personnel to mustering area(s). Below are some suggestions:

Alternative Emergency Response Facility (Capacity: 62)

Unified Command Center (Capacity: 60)

EERC Auditorium (Capacity: 132)

EERC Cafeteria (Capacity: 84)

2. DIRECT the individuals in the mustering area(s) to sign-in on Page 2 of this attachment.

3. PROVIDE completed Mustering Area Sign-In sheet(s) to the Administrative Support Manager (ASM) in the Emergency Operations Facility (EOF).

Nuclear Common Page 45 of 46 Rev.23

NC.EP-EP .ZZ-01 02(Q)

Attachment 12 ORGANIZATION OF ALL-CALL EXTRA RESPONDERS Page 2 of 2 MUSTERING AREA SIGN-IN SHEET Mustering Area: _ _ _ _ _ _ _ _ _ _ _ _ _ _Telephone No.: _ _ _ _ _ _ _ __

Emp.# Name (Printed) Team Position Facility Nuclear Common Page 46 of 46 Rev.23

PSEG Internal Use Only PSEG NUCLEAR L.L.C PSEG Nuclear Common EMERGENCY PREPAREDNESS NC.EP-EP.ZZ-0309(0)- Rev. 16 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS ADHERENCE LEVEL: LEVEL 2 - REFERENCE USE Biennial Review Performed: Yes D No IZJ Configuration Change Packages and Affected Document Numbers incorporated into this revision:

None OTSCs incorporated into this revision:

None Operational Experience (OPEX) incorporated into this revision:

None Revision Summary Location Description of Change Entire Procedure

Converted to new procedure format.

Section 2.1

Deleted Original Step 3.1.5 as individuals that would be in the emergency facilities during an event would be qualified.

Step 2.1.4

Added clarification to indicate that NC.EP-EP.ZZ-0313(0) is used at the EOF.

Step 2.2.2

Added information to reference EP-Aid-025 for obtaining meteorological data when automatic meteorological data acquisition is not operational. (SAP #70196625/001 0)

Step 4.4.18

Added new step concerning Time of Trip and renumbered remaining steps.

Section 4.5.1

Revised to remove mention of recommended radiological protective action recommendations (RAD PARs) (SAP #70196625/0020)

Step 4.6.1

Updated diagram of the Teletector/Telepole Rad Monitor Location .

Step 4.6.1 and

Added reference to telepole instrumentation for performing dose assessment calculations using Main Steam Line Teletector Readings. , Page 3

Deleted information for Hope Creek Containment Leakage "What If' calculations which was printed twice. (SAP #80120090/0180)

NC.EP-EP .ZZ-0309(Q) Page 2 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE AND SCOPE .................................................................................................. 3 2.0 PRECAUTIONS AND LIMITATIONS ............................................................................... 3 3.0 PREREQUISITES ............................................................................................................. 5 4.0 INSTRUCTIONS ............................................................................................................... 6 4.1 Start-Up Instructions For MIDAS ....................................................................... 6 4.2 Auto Quick Dose Projection (MENU G) Mode Instructions ............................. 7 4.3 Manual Quick Dose Projection (MENU A) Mode Instructions ......................... 9 4.4 Manual Isotopic Entry on Spreadsheet (MENU M) Mode Instructions ......... 11 4.5 Dose Assessment Guidance

Effluent Monitors Increase By A Factor Equal To Or Greater Than 10 ........................................................................... 14 4.6 Preplanned Alternative Guidance .................................................................... 15 4.7 Additional Guidance and Instructions for MIDAS .......................................... 16

5.0 REFERENCES

AND COMMITMENTS .......................................................................... 17 6.0 RECORDS ...................................................................................................................... 18 , Salem/Hope Creek Dose Assessment Guidance ................................................ 19

NC. EP-EP .ZZ-0309( Q) Page 3 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1. This procedure provides guidance and operating instructions concerning performing basic dose assessment using the MIDAS dose assessment program.

1.2 Scope 1.2.1. None 2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions 2.1.1. Sections/Steps in this procedure may be PERFORMED in the order deemed appropriate for the emergency situation. Only Sections/Steps that are applicable to the specific MIDAS dose assessment mode of operation that is being PERFORMED need to be followed.

2.1.2. Initials should be used in the place keeping sign-offs next to the step being PERFORMED. Place keeping may be suspended for simple and repetitive steps, after first use, if approved by supervisor in accordance with HU-AA-104-101.

2.1.3. This procedure is limited to performance of basic dose assessment calculations; Automatic/Manual "Quick Dose Projection", "Isotopic Entry on Spreadsheet" and guidance if instantaneous monitor values increase

~a factor of 10 (Section 4.5). (If the reactor has been shut down ~90 minutes use Enhanced Dose Projection, instead of the Quick Dose Projection mode found in NC.EP-EP.ZZ-0313(0), used at the EOF.

2.1.4. IF there are concurrent multiple releases from Salem and Hope Creek THEN REFER to NC.EP-EP.ZZ-0313(0), Advanced Dose Assessment (MIDAS) Instructions, to PERFORM dose assessment at the EOF(necessary if the combined releases could exceed the EPA Protective Action Guideline (PAG) of ~1 ,000 mRem TEDE or ~5000 mRem Thyroid CDE beyond the Site Boundary).

2.1.5. IF a "Release is in Progress" THEN continue each subsequent run using the Run Next Time Step or Save Without Exiting options in order to integrate previous cumulative dose, if possible. If Run Next Time Step is not possible the dose projection is still accurate but previous assessments will not be part of the cumulative dose. (lE changing pathways in the middle of a MIDAS run THEN MIDAS should be restarted).

NC.EP-EP .ZZ-0309(Q) Page 4 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 2.1.6. The R-46 Main Steam Line Monitor should only be used as an effluent monitor for dose assessment if a primary to secondary leak is occurring and the Steam Generator is releasing directly to atmosphere through the safety relief valve(s) (SRV) or through the atmospheric vent (MS-1 0). If the R-46 monitor is changing, verification of an atmospheric pathway should be obtained.

2.1.7. LAN 2.5 computers should be left running at all times. When done running MIDAS leave the computer on but turn off the monitor.

2.2 Limitations 2.2.1. Dose Assessment should be performed using 10 or 15 minute average radiation monitor system (RMS) and meteorological (MET) data, UNLESS circumstances in Section 4.5 are met (instantaneous monitor readings increase > a factor of 10). Auto data collection captures average data values so it is not appropriate to run in Auto when running dose assessment for rapid monitor increases.

2.2.2. Use references: EP Aid-018, Salem SPDS Instructions for MET and Radiological Data, EP Aid-019, Hope Creek CRIDS/SPDS- Instructions for MET and Radiological Data and EP Aid-090, HC EOF RM-11 Instructions for Radiological and Flow Data (EOF ONLY) for directions concerning functions of the SPDS radiological screens. EP Aid-025 can be utilized to obtain meteorological data when automatic meteorological data acquisition is not operational.

2.2.3. Use references: EP Aid-048, Salem Radiation Monitoring System Summary and EP Aid-049, Hope Creek Radiation Monitoring System Summary when information is needed concerning specific radiation monitors (i.e. units, detector location, alarm set points).

2.2.4. Prior to starting dose assessment activities determine the active effluent pathways by checking for effluent flow:

1. Hope Creek- NPV, SPV, FRVS and HTV.

2. Salem - Plant Vent (Steam Generator to Atmosphere must be determined by visual observations).

2.2.5. Process Flow and Radiation Readings for the HTV can be obtained in four locations. (Detailed directions for HTV dose assessment are found in NC.EP-EP.ZZ-0313[0]).

1. RM 11: Low Range HTV Gaseous Radiation Concentration (9RX516) in ~Ci/cc and HTV vent flow (9RX519) in CFM are available while still on scale and not saturated.

2. SPDS: Use 15 Min RMS Report Point ID AA519 for HTV Flow in CFM and Point ID R9516T3 for HTV Low Range Gaseous Radiation in ~Ci/cc.

NC.EP-EP .ZZ-0309(Q) Page 5 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 NOTE To obtain HTV High Range Radiation data and HTV Flow rate data from the POS or ROS, work with the EOF - OPS Advisor or the Nuclear Shift Tech Advisor (NSTA) in the Control Room.

3. HTV Primary Operating Station CPOS): High Range Radiation Monitoring and HTV vent flow data are available at the POS in Room 3576 (Remote Shutdown Panel) of the Unit 1 Auxiliary Building I Rad Waste Area on EL 137'-0". The POS panel has key-lock switches for controlling the vent valves, indicating lights for valve position indication, a graphic recorder displaying the HTV flow rate (CFM on 1SPFR-11542A) (max 25000 cfm) and radiation dose rate (R/hr on 1SPRR-11542A) from the High Range HTV monitor.

4. HTV Remote Operating Station CROS): The ROS is located in Room 5301, the electrical chase on EL 102' 0" of the Control/Diesel (Auxiliary) Building. The Process Indicator Panel (PIP), H1 GS-1 0-C-1 01, displays the process flow rate (in milliamps on 1SPFI-11542A) with CFM conversion chart available below on page 7 of 7 of this attachment) and dose rate (R/hr on 1SPRI-11542A) from the High Range HTV monitor.

2.2.6. A blank SSCL page 2 can be found in the Event Classification Guide (ECG), Attachment 8 or from Communicator Number 2.

3.0 PREREQUISITES 3.1 IMPLEMENT this procedure:

3.1.1. Upon the declaration of an Unusual Event or higher emergency classification.

3.1.2. At the request of the Shift Manager (SM).

3.1.3. At the request of the Radiation Protection Duty Supervisor (RPDS) or Shift Radiation Protection Technician (SRPT).

3.1.4. In accordance with (lAW) Salem and Hope Creek applicable station procedures.

3.1.5. MIDAS Dose Assessment software is loaded on the hard drive of each computer connected to the LAN 2.5 Network, in all emergency facilities.

While MIDAS will run independent of the network, the automatic data collection (auto mode) will not function without the network and dose assessment will have to be run in manual mode. Salem SPDS, Hope Creek CRIDS/SPDS and the "EOF RM-11" also reside on the LAN 2.5 network and is a source of data for running MIDAS dose assessment software. (EOF RM-11 only resides on the EOF Dose Assessment Area computers.)

NC.EP-EP.ZZ-0309(Q) Page 6 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.0 INSTRUCTIONS 4.1 Start-Up Instructions For MIDAS 4.1.1. ENSURE the computer and monitors are both turned on. IF necessary, PRESS the "Power" button to turn them on. (If the computer was off, turning it on will boot the LAN 2.5 to the desktop where the MIDAS Accident Cales icon can be seen.)

4.1.2. IF the monitor screen is blank THEN MOVE the mouse to "wakeup" the monitor.

4.1.3. POSITION the cursor on the MIDAS Accident Cales icon and double left click the mouse. (The Sheet# 1 screen will be displayed).

4.1.4. SELECT Unit (Hope Creek, Salem Unit 1, Q! Salem Unit 2).

4.1.5. SELECT the appropriate Section for type of dose assessment mode, from the list below:

REFER to Section 4.2 for instructions on how to PERFORM Dose Assessment in Automatic QUICK DOSE PROJECTION (MENU G).

REFER to Section 4.3 for instructions on how to PERFORM Dose Assessment in Manual QUICK DOSE PROJECTION (MENU A).

REFER to Section 4.4 for instructions on how to PERFORM Dose Assessment in ISOTOPIC ENTRY ON SPREADSHEET (MENU M).

REFER to Section 4.5 to PERFORM Dose Assessment When Plant Vent Effluent Monitor(s) Increase By A Factor of 10 or greater.

REFER to Section 4.6 for Preplanned Alternative Guidance to PERFORM Dose Assessment.

REFER to Section 4.7 for Additional Guidance and Instructions for MIDAS concerning:

Screen print or print an additional station status checklist (SSCL),

Print a map,

Additional map guidance,

NC.EP-EP .ZZ-0309(Q) Page 7 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.2 Auto Quick Dose Projection (MENU G) Mode Instructions 4.2.1. SELECT AUTOMATIC.

4.2.2. SELECT AUTO QUICK DOSE PROJECTION (MENU G) using the down arrow located in the Accident Run Menu Selection box.

4.2.3. SELECT OK (MIDAS will calculate a dose assessments for all monitored pathways that auto data collection has a current radiation monitor reading and flow indication. If a normal effluent pathway monitor is out of service MIDAS will NOT calculate that pathway and will need to be done in manual. Automatic dose calculations will also not be calculated for Steam Generator to atmosphere or Containment Leakage because there isn't a flow monitor. Ensure all pathways with Effluent Flow print on SSCL if not resolve issues by running in manual.)

4.2.4. REVIEW data on the "Meteorological Raw Data" spreadsheet and USE SPDS to update any missing or inaccurate data on the "Current Time" data line (row). Then SELECT "OK".

4.2.5. REVIEW data on the "Radiation Monitor & Flow Raw Data" spreadsheet.

USE SPDS to update any missing or inaccurate data on the "Current Time" data line (row). IF the calculation is for a Steam Generator Tube Rupture (SGTR) to Atmosphere or Containment leakage THEN ENTER the appropriate flows on the spreadsheet from Attachment 1 (from Steam Generator or Containment leakage dose assessment sections). Then SELECT "OK".

4.2.6. SELECT the appropriate "Accident Type" from the pull-down menu.

(Salem; Core Accident, Tube Rupture [SGTR] or Spent Fuel Accident)

(Hope Creek; Routine Effluent, Core Accidents or Spent Fuel)

For Salem and Hope Creek SELECT Spent Fuel Pool if the event is due to damage to fuel in the Spent Fuel Pool

For Salem SELECT Tube Rupture if the event is due to a SGTR select

For Hope Creek SELECT Routine Effluents if there is no increase in effluent concentration

IF none of the above are applicable, choose Core Accident 4.2.7. LEFT CLICK on the "Next" button then LEFT CLICK on "Start Calc".

4.2.8. If MIDAS is available in automatic mode the display will change to the map display and a SSCL will automatically print. IF MIDAS input data from MET or RAD Monitors is not available THEN EXIT and GO TO Section 4.3 and run a Quick Dose Projection in manual.

NC.EP-EP .ZZ-0309(Q) Page 8 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.2.9. IF a SSCL needs to be printed to the screen, or an additional SSCL printed out, THEN GO to Step 4. 7.1 for guidance.

4.2.1 0. IF another dose assessment calculation is required or to EXIT, THEN SELECT END RUN (A pop~up screen will appear).

NOTE When a release starts or is in-progress use the Run Next Time Step option in order to integrate previous cumulative dose. The three other remaining options should be used PRIOR to a radiological release since dose integration is not necessary.

If using Run Next Time Step is not appropriate for the situation then select Save Run & Exit if dose integration is needed later the data will be available in the "RECAP" mode.

Exit Without Saving should be only used if the user knows the data which won't be saved will never be needed, for any reason.

4.2.11. PERFORM one of the following options as available:

IF the user wishes to Run Next Time Step dose assessment calculation, THEN SELECT it, CLICK OK, and RETURN to Step 4.2.4.

(MIDAS will PERFORM dose assessment calculations, the SSCL will automatically printout, and the screen map with plume will appear).

IF the user wishes to Save the Run and EXIT, THEN SELECT Save Run ~ Exit , CLICK OK and RETURN to Step 4.1.3.

IF the user wishes to EXIT Without Saving the Run, THEN SELECT Exit Without Saving, CLICK OK and RETURN to Step 4.1.3.

NC.EP-EP .ZZ-0309(Q) Page 9 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16

IF another dose assessment calculation is needed IMMEDIATELY, THEN SELECT Save Without Exiting, CLICK OK and RETURN to Step 4.2.4.

4.3 Manual Quick Dose Projection (MENU A) Mode Instructions NOTE Manual Mode Dose Assessment, should be PERFORMED IF:

A Plant Vent Effluent monitor is not operational.

A surveillance of the Plant Vent Effluent monitor is ongoing.

Automatic radiological data acquisition is not operational.

Automatic meteorological data acquisition is not operational.*

To input the total isotopic noble gas and iodine 131 values.

The criteria in Section 4.5 is met.

The criteria in Section 4.6 is met 4.3.1. SELECT Manual mode.

4.3.2. SELECT Quick Dose Projection (Menu Al using the down arrow located in the Accident Run Menu Selection box.

4.3.3. SELECT OK.

4.3.4. If applicable, PERFORM the appropriate steps listed below:

IF "CHANGING UNITS", a pop-up screen will appear concerning initializing data, THEN SELECT OK.

IF this is the "FIRST" dose assessment run, THEN SELECT New and OK. (A pop-up screen will appear concerning destroying data) SELECT OK.

IF this is a "CONTINUATION" of dose assessment runs, THEN SELECT EDIT LAST and SELECT OK.

4.3.5. INPUT 15 minute average MET Data on the highlighted time line (Meteorological Spreadsheet- Sheet# 4).

4.3.6. SELECT OK.

NC.EP-EP .ZZ-0309(Q) Page 10 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 NOTE For general guidance or specific guidance on selection of monitors/

channels/flows to be used for dose assessment REFER to Attachment 1.

4.3.7. IF PERFORMING (dose calculations using instantaneous data follow additional guidance in Section 4.5) dose calculations using 10 or 15 minute averages, THEN INPUT the appropriate 10 or 15 minute average radiological and plant vent flow rate data on the highlighted time line. (Radiation Monitor

& Flow Spreadsheet- Sheet# 5). (Remember, both rad monitor reading and flow are both required for each pathway, to be calculated.)

4.3.8. SELECT OK.

4.3.9. SELECT the appropriate "Accident Type" from the pull-down menu.

(Salem; Core Accident, Tube Rupture [SGTR] or Spent Fuel Accident)

(Hope Creek; Routine Effluent, Core Accidents or Spent Fuel).

4.3.10. LEFT CLICK on the "Next" button then LEFT CLICK on "Start Calc".

4.3.11. IF a SSCL needs to be printed to the screen, or an additional SSCL printed out, THEN GO to Step 4. 7.1 for guidance.

4.3.12. IF another dose assessment calculation is required or to EXIT, THEN SELECT END RUN (A pop-up screen will appear).

NC.EP-EP .ZZ-0309(Q) Page 11 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.3.13. PERFORM one of the following options as available:

IF the user wishes to PERFORM another dose assessment calculation as a continuation, THEN SELECT RUN NEXT TIME STEP, CLICK OK and RETURN to Step 4.3.5.

IF the user wishes to Save the Run and EXIT, THEN SELECT Save Run & Exit, CLICK OK and RETURN to Step 4.1.3.

IF the user wishes to EXIT Without Saving the Run, THEN SELECT Exit Without Saving, CLICK OK and RETURN to Step 4.1.3.

IF another dose assessment calculation is needed IMMEDIATELY, THEN SELECT Save Without Exiting, CLICK OK and RETURN to Step 4.1.4.

4.4 Manual Isotopic Entry on Spreadsheet (MENU M) Mode Instructions 4.4.1. SELECT Manual mode.

4.4.2. SELECT Isotopic Entry On Spreadsheet (Menu Ml.

4.4.3. SELECT OK.

NOTE A Pop-up Warning Screen will appear concerning SELECTING AT LEAST ONE RELEASE POINT.

4.4.4. SELECT OK.

4.4.5. SELECT the appropriate release point for the isotopic sample.

[HOPE CREEK- ill FRVS, ill NPV, ill SPV, {!l.!:illl]

OR

[SALEM -ill PLT Vent, ill STM Line, ill CTMTl

NC.EP-EP .ZZ-0309(Q) Page 12 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.4.6. SELECT Next.

4.4.7. ENSURE the Times (hrs) to be Calculated are:

[1] 0.25

[2] 1.00

[3] 4.00

[4] 24.00 INPUT the above values.

4.4.8. SELECT NEXT.

4.4.9. PERFORM one of the appropriate steps listed below:

IF "Changing Units", a pop-up screen will appear concerning initializing data, THEN SELECT OK.

IF this is the "FIRST ISOTOPIC" dose assessment run, THEN SELECT New and OK. (A pop-up screen will appear concerning destroying data).

0 SELECT OK and go to Step 4.4.1 0.

IF "CONTINUING ISOTOPIC" of dose assessment runs, THEN SELECT EDIT LAST.

D SELECT OK and go to Step 4.4.1 0.

4.4.1 0. ENTER appropriate Meteorological Data on the Meteorological Spreadsheet - Sheet # 4.

4.4.11. SELECT OK (A Pop-up Screen will appear- Type Of Isotopic Values).

4.4.12. SELECT Enter Isotopic Concentrations And Flow Rate.

4.4.13. SELECT OK.

4.4.14. ENTER Plant Vent Flow Rate under Fan Flow CFM.

4.4.15. ENTER Appropriate Isotopic Values.

4.4.16. SELECT OK.

NC.EP-EP .ZZ-0309(Q) Page 13 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.4.17. SELECT Next.

4.4.18. DETERMINE Date, Time of Trip/Shutdown if applicable by selecting appropriate choice in the lower left corner.

4.4.19. SELECT Start Calc (The SSCL will automatically printout and the 13-mile map will be displayed).

NOTE A Pop-up Warning Screen will appear concerning Time of Trip.

4.4.20. IF a SSCL needs to be printed to the screen or an additional SSCL printed out, THEN GO to Step 4.7.1 for guidance.

4.4.21. IF another dose assessment calculation is required or to EXIT, THEN SELECT END RUN (A pop-up screen will appear).

4.4.22. PERFORM one of the following selections:

lE another dose assessment calculation is needed THEN SELECT Save Without Exiting and RETURN to Step 4.4.1.

IF the user wishes to EXIT, THEN SELECT Save Run §! Exit.

4.4.23. SELECT OK.

NC.EP-EP .ZZ-0309(Q) Page 14 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.5 Dose Assessment Guidance

Effluent Monitors Increase By A Factor Equal To Or Greater Than 10 NOTE Salem and Hope Creek Plant Effluent Monitors are:

SALEM PLANT EFFLUENT MONITORS USED FOR DOSE ASSESSMENT o Unit 1 or 2 R41 A, B, or C (uCi/cc) o Unit 1 or 2 R46 (A, B, C or D) (mR/hr) if a Steam Generator with a primary to secondary leak is being released directly to atmosphere through the SRV(S) or the manual atmospheric vent (MS-1 0)

HOPE CREEK PLANT VENT EFFLUENT MONITORS USED FOR DOSE ASSESSMENT o SPV- 9RX606, 9RX607, or 9RX581 (uCi/cc) o NPV- 9RX602, 9RX603, or 9RX591 (uCi/cc) o FRVSV- 9RX640, 9RX610, or 9RX611 (uCi/cc) o HTV- 9RX518 (uCi/sec) 4.5.1. IF any Plant Vent Effluent Monitor(s) increase by a factor of 10 or more, THEN PERFORM the following:

1. PERFORM dose assessment calculations in the manual mode using instantaneous value(s) lAW Section 4.3 of this procedure;

2. WRITE on top of Page 2 of the Station Status Checklist (SSCL),

"RELEASE RATE CALCULATED FROM INSTANTANEOUS MONITOR VALUES."

3. ADVISE the appropriate person SM, RAC, or RSM that, "the SSCL was calculated from instantaneous Plant Vent data and may not reflect actual radiological conditions. An additional SSCL will be forth coming in approximately 20 minutes.

4. PERFORM another dose assessment in approximately 15 to 20 minutes. SELECT END RUN (A pop screen will appear).

5. SELECT Save Run And Exit., CLICK OK and RETURN to Step 4.1.4. Use the 15-minute average MET and 10 or 15-minute average radiological data.

6. PROVIDE the SSCL, if applicable, to the appropriate person (SM, RAC, or RSM).

NC.EP-EP .ZZ-0309(Q) Page 15 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 4.6 Preplanned Alternative Guidance NOTE SALEM UNIT 1 I 2 ONLY Contact the Shift Manager (SM) prior to performing dose assessment calculations for preplanned alternative, if the 1R41 or 2R41 monitor(s) are out of service I inoperational and are needed to PERFORM dose assessment calculations.

4.6.1. PERFORM the appropriate steps listed below, to calculate a SSCL, when the normal method to PERFORM dose assessment at SALEM UNIT 1 and/or SALEM UNIT~ IS NOT possible:

IMPLEMENT Section 4.3, to PERFORM dose assessment calculations using Main Steam Line (MSL) Teletector/Telepole Readings. [All contact teletector/telepole readings on the MSLs should be obtained on the curve of the line prior to the main steam isolation valve (MSIV). (See the diagram below)].

Teletector/Telepole readings must be multiplied by a conversion factor prior to being used in MIDAS calculation. See NOTE in Section 4.3.

Teletector/Telepole Rad Monitor Location Teletector/Telepole Rad Monjtor Location MAIN STEAM LINES 12, 14, 22, 24 ARE FOUND IN THE OUTSIDE PIPING PENETRATIONS.

MAIN STEAM LINES 11, 13, 21, 23 ARE ACCESSIBLE BYWAY OF THE CHILLER ROOMS AND ARE LOCATED IN THE INNER PIPE PENETRATIONS.

4.6.2. IF ISOTOPIC DATA is available, THEN IMPLEMENT Section 4.4, to PERFORM dose assessment calculations based on isotopic plant vent sample values for Hope Creek, Salem Unit 1, or Salem Unit 2.

NC.EP-EP .ZZ-0309(Q) Page 16 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16

4. 7 Additional Guidance and Instructions for MIDAS 4.7.1. PERFORM the following to "PRINT an additional SSCL":

1. SELECT the Special Reports Box located on the lower menu bar of the map screen.

2. IF the SSCL Box is already highlighted, THEN GO to Step D.

3. CLICK on the BOX below the Special Reports Box until the highlighted SSCL Box appears.

4. CLICK CONFIRM. (The latest SSCL will be printed to the screen).

5. CLICK on the Printer ICON located on the top menu bar. (A pop-up screen will appear).

6. SELECT OK.

7. SELECT the ~ box in the upper right hand corner to EXIT out of the SSCL Screen Print and return to the Map Screen.

4.7.2. PERFORM the following to print a SCREEN or REPORT:

SELECT the ltem(s) you wish to print.

SELECT the Confirm box.

SELECT the PRINTER icon located on the bottom of the menu bar.

4.7.3. PERFORM the following to Print a Plume Map

With the cursor on the plume map right CLICK the mouse.

SELECT Print Map from the selection.

SELECT printer from pull down menu if more than one printer is available).

SELECT OK.

4.7.4. DETERMINE distance between two points on the plume map display

POSITION the cursor on the plume map at the first point of interest.

PRESS DOWN and hold the Shift key.

NC.EP-EP .ZZ-0309(Q) Page 17 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16

CLICK and hold down the left mouse button and move the mouse to the second area of interest and the distance between the two points will be displayed.

4.7.5. VIEW different Map Features on the display

CLICK on the Map Features button, from the Plume Map display screen.

CLICK on all the items that should be displayed.

SELECT OK (selected items will be displayed on the map).

END of Instructions

5.0 REFERENCES

AND COMMITMENTS 5.1 Commitments 5.1.1. None 5.2 Performance References 5.2.1. NC.EP-EP.ZZ-031 0 (Q), Radiation Protection Supervisor- Offsite And Field Monitoring Team Response 5.2.2. NC.EP-EP.ZZ-0313 (Q), Advanced Dose Assessment (MIDAS) Instructions 5.2.3. HC.EP-EP.ZZ-0301 (Q), Shift Radiation Protection Technician Response 5.2.4. SC.EP-EP.ZZ-0301 (Q), Shift Radiation Protection Technician Response 5.2.5. EP Aid-018, Salem SPDS Instructions for MET and Radiological Data 5.2.6. EP Aid-019, Hope Creek CRIDS/SPDS - Instructions for MET and Radiological Data 5.2.7. EP Aid-025, Get Weather from NOAA 5.2.8. EP Aid-048, Salem Radiation Monitoring System Summary 5.2.9. EP Aid-049, Hope Creek Radiation Monitoring System Summary 5.2.10. EP Aid-090, HC EOF RM-11 Instructions for Radiological and Flow Data 5.3 Developmental References 5.3.1. EPA 400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 5.3.2. PSEG Nuclear Emergency Plan 5.3.3. MIDAS Documentation

NC.EP-EP.ZZ-0309(Q) Page 18 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 5.3.4. DCP 80057520 Upgrade of the 1R46 Rad Monitors 5.3.5. DCP 80057587 Upgrade of the 2R46 Rad Monitors 6.0 RECORDS

RETURN completed procedures and documentation to the Emergency Preparedness Manager.

NC.EP-EP .ZZ-0309(Q) Page 19 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 Attachment 1, Salem/Hope Creek Dose Assessment Guidance GENERAL GUIDANCE:

10 or 15 Minute Average Effluent radiological monitor data and Effluent flow rates should be input every 15 Minutes. Leaving blank cells between lines of data are interpreted by MIDAS as a puff release (no release for that time period). Rad monitor data and the flow data for that pathway both need to be entered or a calculation for that pathway will not be made.

Monitored release pathways for Hope Creek are: NPV, SPV, FRVS and HTV. Monitored release pathways for Salem are Plant Vent (R41 ), Steam Generator to atmosphere (R46) and Containment (R44). Normally occurring discharges from the stations are coming from the NPV/SPV for HC and the Plant Vent for Salem.

The following monitors should be used for manual dose assessment:

o Hope Creek: NPV-NG, SPV-NG, FRVS-NG and HTV-NG (WRGM channels). Under specific conditions DAPA monitors can be used to evaluate "What If' calculations for Containment Leakage o Salem: R41 and under specific conditions the R46 and or R44 monitors

For assistance with obtaining flow data use EP Aid-018 (Salem) and EP Aid-019 & 090 (Hope Creek).

SALEM UNIT 1 & 2 ONLY

Plant Vent Dose Assessment: Follow the below guidance to help in making the correct decision for which R41 monitor value to use. Only ONE should be used in MIDAS for performing dose assessment.

o R41A should be used if values are > 1E-08 uCi/cc to 9.99E-02 uCi/cc.

o R41 B should be used if values are > 1E-01 uCi/cc to 9.99E+01 uCi/cc.

o R41C should be used if values are> 1E+02 uCi/cc to 1E+05 uCi/cc.

STEAM GENERATOR DOSE ASSESSMENT o R46: Dose assessment may be PERFORMED using the R46 monitor value during a primary to secondary leak or Steam Generator Tube Rupture (SGTR) if the Steam Generator is being released directly to atmosphere. The R46 value is entered in the R46A-D column in MIDAS for each S/G and use the default flow rate value of 4.50E+05 lbs/hr. More accurate flow can be provided with the assistance of Operations or Engineering but don't wait for this data to run dose assessment, use the default until updated. If the R46 reading is erratic use substitution of TELETECTOR/TELEPOLE readings for R46MSL values, method below.

Page 1 of 3

NC.EP-EP .ZZ-0309(Q) Page 20 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 Attachment 1, Salem/Hope Creek Dose Assessment Guidance (continued)

Substitution of TELETECTORITELEPOLE readings for R46MSL values.

o Teletector/Telepole values should be used instead of R46 values if the R46 values are not available or trends of R46 data shows a stream of spikes making the average data unreliable.

o REFER to section 5.6 of this procedure concerning where contact readings on the Main Steam Lines (MSL) should be taken.

o The Teletector/Telepole value obtained from contact reading (in mR/hr) on the MSL MUST be multiplied by the Correction Factor of 1.16E-2 prior to being used in MIDAS.

o The value should be entered in the R46MSL column.

o The value 4.50E+05 lbs/hr should be used as the default flow rate.

Containment Leakage Dose Assessment: R44 monitor values may be used for "WHAT IF" type Calculations or if the containment has been breached and an unmonitored release is in progress.

o Enter the R44 value along with a projected flow rate from containment. Operations or Engineering may be able to provide assistance with determining the projected flow rate.

o Salem UFSAR section 6.2.2.2.2 lists the Salem Containment air volume as 2.62E+06 cubic feet so the following flow rates could be useful to determine source term due to containment leakage.

Design Basis leak rate is 0.1% per day which would be 1.82 CFM

10% per day leak rate would be 1.82E+02 CFM

100% per day would be 1.82E+03 CFM

And for a catastrophic failure, 100% in an hour, would be 4.37E+04 CFM Page 2 of 3

NC.EP-EP.ZZ-0309(0) Page 21 of 21 DOSE ASSESSMENT (MIDAS) INSTRUCTIONS Rev: 16 Attachment 1, Salem/Hope Creek Dose Assessment Guidance (continued)

HOPE CREEK ONLY Follow the guidance below is for help in making the correct decision for which effluent channel value to use. (DO NOT use more than one channel per monitor. On the RM-11 in the HC RPCP and the HC TSC the value displayed on channel icon is the instantaneous value; average values are displayed on the channel display. View the channel display by clicking on the channel icon. The Mid-Hi range sample pump for the NPV, SPV and FRVS starts at 1.00E-03 uCi/cc so values displayed below this value are not valid.).

For SPV Monitor:

o Use channel 9RX606 from 1.00E-08 to 1.00E-02 uCi/cc (Low Range) o Use channel 9RX607 from >1.00E-02 to 1.00E+01 uCi/cc (Mid Range) o Use channel 9RX581 from >1.00E+01 to 1.00E+05 uCi/cc (Hi Range)

For NPV Monitor:

o Use channel 9RX602 from 1.00E-08 to 1.00E-02 uCi/cc (Low Range) o Use channel 9RX603 from >1.00E-02 to 1.00E+01 uCi/cc (Mid Range) o Use channel 9RX591 from >1.00E+01 to 1.00E+05 uCi/cc (Hi Range)

For FRVS Monitor:

o Use channel 9RX640 from 1.00E-08 to 1.00E-02 uCi/cc (Low Range) o Use channel 9RX610 from >1.00E-02 to 1.00E+01 uCi/cc (Mid Range) o Use channel 9RX611 from >1.00E+01 to 1.00E+-5 uCi/cc (Hi Range)

For HTV Monitor o Use 9RX518 (Effluent Monitor in uCi/sec). For additional guidance refer to NC.EP-EP.ZZ-0313(0).

Hope Creek Containment Leakage "What If" calculations use the DAPA monitor value (R/hr) along with the projected flow (CFM) for the Primary Containment leakage. According to the Hope Creek UFSAR Table 15.6-12 the air volume of the HC Primary Containment is 3.06E+05 cubic feet so the following flow rates could be useful to determine source term due to containment leakage.

o Design Basis leak rate is 0.5% per day which would be approx. 1.10 CFM o 10% per day leak rate would be 2.13E+01 CFM o 100% per day leak rate would be 2.13E+02 CFM o For a catastrophic failure, 100% in an hour, would be 5.11 E+03 CFM Page 3 of 3

PSEG Internal Use Only PSEG NUCLEAR L.L.C PSEG Nuclear Common EMERGENCY PREPAREDNESS NC.EP-EP.ZZ-0601(0)- Rev. 13 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL ASSESSMENT STAFF

RESPONSE

ADHERENCE LEVEL: LEVEL 2 - REFERENCE USE Biennial Review Performed: Yes D No~

Configuration Change Packages and Affected Document Numbers incorporated into this revision:

None OTSCs incorporated into this revision:

None Operational Experience (OPEX) incorporated into this revision:

None

!Revision Summary Location Description of Change

Procedure converted to new template .

Entire Procedure

Corrected title of NC.EP-EP.ZZ-0602(0). (SAP #70161063/0010)

Corrected formatting of procedure numbers NC.EP-EP.ZZ-0308, NC.EP-EP.ZZ-0305. (SAP #70161063/0030)

Section 4.0

Moved initiation of RSM log to Section 4.0 from Attachment 1 Old Step 3.1

Deleted step that provided guidance to initial steps as this is part of the procedure process and does not need to be included in this procedure.

Deleted step that stated only qualified individuals are to implement procedure. This step is not required as the only individuals contacted to implement procedure would be qualified.

Old Step 4.0

Step deleted. Not part of new template and all equipment is maintained within the EOF.

Step 7.2

Cross references were updated and reordered .

Deleted bullet to contact RAC. This is performed in Section 4.0

NC.EP-EP .ZZ-0601 (Q) Page 2 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev:13 ASSESSMENT STAFF RESPONSE

Revise Note prior to Step A to remove that steps can be performed in any order. This instruction is already in Precautions Step 2.1.1 ,

second bullet.

Revised Step A.1.d to reflect RSM issuance of Kl to offsite PSEG radiation workers and corrected title of procedure NC.EP-EP.ZZ-0305(0), Potassium Iodide (KI) Administration.

(SAP #70161063/0010)

Revised Step A.1.g to add reference to guidance for initial PAR and PAR upgrades. (SAP #70161063/0010)

Revised Step A.1.g to correct title for NC.EP-EP.ZZ-0404(0) .

(SAP #70161063/0020)

Added new Step A.1.j to provide direction for EOF relocation if needed due to Radiological or External Event concerns. (SAP #70198023)

Revised Section i for RSM actions when a release is in progress .

Moved bullet for Coast Guard Helicopter approval to end of Section i

Step A.2.c added (at 5 miles or 10 miles) to clarify the range that the projected doses are applicable.

Step 3.c,last bullet, removed " ... that could indicate exceeding a PAG",

this criteria is not required,

Reordered steps and corrected numbering/bullets .

Added step to verify and/or issue dosimetry for EOF personnel.

(SAP #70161063/0040)

Form-2

Formatted and added signature line for entry of data into Sentinel.

Form-3

Added line for second instrument and deleted Calibration Due Date field as not required.

Form-4

Page 1, changed "TRIP" to "SCRAM" .

Updated HTV NG values to match NC.EP-EP.ZZ-0313, Attachment 5 values.

Form-5

Form-5, Page 1, changed "ATWS" to "ATWT" .

NC.EP-EP .ZZ-0601 (Q) Page 3 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev:13 ASSESSMENT STAFF RESPONSE TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE AND SCOPE .................................................................................................. 4 2.0 PRECAUTIONS AND LIMITATIONS .........................*..................................................... 4 3.0 PREREQUISITES ............................................................................................................. 4 4.0 INSTRUCTIONS ................................................*................*............................................. 4 4.1 The RSM shall: .................................................................................................... 4

5.0 REFERENCES

AND COMMITMENTS ............................................................................ 5 6.0 RECORDS ........................................................................................................................ 6 , Pre-Activation RSM Checklist. ............................................................................... 7 , RSM Checklist ....................................................................................................... 9 , State Liaison Instructions .................................................................................... 13 , Habitability, EOF Emergency Ventilation and Laboratory and Testing Services (LTS) Instructions ......................................................................................................... 16 , Reserved ............................................................................................................. 20 , Reserved ............................................................................................................. 21 Form- 1 EOF Dosimetry Log ...................................................................................................... 22 Form - 2 DLR Issue Log ............................................................................................................. 23 Form - 3 EOF Habitability Log .................................................................................................... 24 Form - 4 Hope Creek MIDAS Input. ............................................................................................ 25 Form- 5 Salem MIDAS Input. ..................................................................................................... 26

NC.EP-EP .ZZ-0601 (Q) Page 4 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1. h"o outline and describe the Radiological Support Manager's (RSM) duties during a declared emergency I 1.2 Scope 1.2.1. !None I 2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions 2.1.1. !Precaution and Limitations To Be Followed Prior To Implementing This Procedure:

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

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.

2.2 Limitations 2.2.1. !None I 3.0 PREREQUISITES 3.1 !Implement this procedure at:

3.1.1. The discretion of the Emergency Response Manager (ERM).

3.1.2. Upon staffing of the EOF.

4.0 INSTRUCTIONS 4.1 [The RSM shall:

4.1.1. INITIATE the RSM log. Ill 4.1.2. CONTACT the Radiological Assessment Coordinator (RAC) OR the I Shift Radiation Protection Technician (SRPT) and OBTAIN a briefing on the current onsite and offsite radiological conditions. II 4.1.3. REPORT to the ERM and OBTAIN a briefing of the current status of the emergency.

4.1.4. UPDATE the ERM on radiological conditions, as appropriate.

NC.EP-EP .ZZ-0601 (Q) Page 5 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE 4.1.5. IMPLEMENT Attachment 1, Pre-activation RSM Checklist.

END of Instructions

5.0 REFERENCES

AND COMMITMENTS 5.1 Performance References 5.1.1. ;NC.EP-EP.ZZ-0305(0), Potassium Iodide (KI) Administration 5.1.2. NC.EP-EP.ZZ-0308(0), PersonneiNehicle Survey and Decontamination 5.1.3. NC.EP-EP.ZZ-0313(0), Advanced Dose Assessment (Midas) Instructions 5.1.4. NC.EP-EP.ZZ-0404(0), Protective Action Recommendations (PAR) Upgrades 5.1.5. NC.EP-EP.ZZ-0602(0), EOF Radiological Dose Assessment 5.1.6. NC.EP-EP.ZZ-0603(0), Field Team Monitoring 5.1. 7. NC.EP-FT.ZZ-0009(0), Emergency Operations Facility (EOF) Ventilation System Testing 5.1.8. EP-HC-111-F4, General Emergency Classification 5.1.9. EP-SA-111-F4, General Emergency Classification 5.1.10. EP Aid-005, EP Phone Directory 5.1.11. EP Aid-018, Salem SPDS- Instructions for MET and Rad Data 5.1.12. EP Aid-019, Hope Creek CRIDS/SPDS- Instructions For Met and Radiological Data 5.1.13. EP Aid-025, Get Weather from NOAA 5.1.14. EP Aid-048, Salem Radiation Monitoring System Summary 5.1.15. EP Aid-049, Hope Creek Radiation Monitoring System Summary 5.1.16. EP Aid-090, HC EOF RM-11 -Instructions for Radiological and Flow Data 5.1.17. EPAid-095, PSEG Nuclear- ERO Backup Mustering Areas 5.2 Developmental References 5.2.1. !PSEG Nuclear LLC Emergency Plan 5.2.2. EP-AA-120-1 010, Emergency Preparedness Training Administration I 5.3 Commitments 5.3.1. :None I

NC.EP-EP .ZZ-0601 (Q) Page 6 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE 6.0 RECORDS

'RETURN completed procedure and any information or data thought to be pertinent to the Manager - Emergency Preparedness.

NC.EP-EP.ZZ-0601 (Q) Page 7 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 1, Pre-Activation RSM Checklist A. PRE-ACTIVATION RSM CHECKLIST

1. RSM should ENSURE the following items are performed:

ASSIGN the Radiological Assessment Staff Members (D02's & D03) to the following job assignments:

Dose Assessment (D02A)

(Refer to NC.EP-EP.ZZ-0602(0) EOF Radiological Dose Assessment):

(Name) (Name)

State Liaison, assisting states with RMS and Meteorological data (D028)

(Refer to Attachment 3, State Liaison and RMS Trending Instructions):

~'------------------

(Name) (Name)

Habitability, EOF Emergency Vent. and Environmental Sampling Issues (D02C)

(Refer to Attachment 4, Habitability, EOF Emergency Ventilation and Laboratory and Testing Services (LTS) Instructions):

*'----------~------

(Name) (Name)

Coordinating and Tracking Offsite Field Teams Location and Sampling (D03)

(Refer to NC.EP-EP.ZZ-0603 (Q), Field Monitoring):

~'------------------

(Name) (Name)

a. ENSURE the Radiological Assessment Staff is fully staffed to perform the D02/D03 tasks as outlined above, as thought appropriate for current conditions. (LOG any deviations)

Page 1 of 2

NC.EP-EP .ZZ-0601 (Q) Page 8 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 1, Pre-Activation RSM Checklist (continued)

2. ASSIGN an individual to act as an Assistant RSM when the RSM is in Leads meetings or temporarily out of the EOF. (ENSURE this individual understands that he/she cannot perform items identified in Attachment 2 which may not be delegated.)

3. VERIFY the following tasks are being performed:

If appropriate and a General Emergency has been declared, DIRECT EOF habitability surveys be performed every 30 minutes lAW Attachment 4.

EOF Radiological Assessment equipment is functioning properly.

EOF AMS is turned on and the alarm set for 2 times the current background.

Dose Assessment is being performed lAW NC.EP-EP.ZZ-0602(0), EOF Radiological Dose Assessment.

Offsite Field Monitoring Teams are functional or in the process of becoming functional.

Current and forecasted meteorological data has been acquired or is in the process of being acquired.

4. INFORM the ERM WHEN the Radiological Assessment Staff is ready to activate.

5. WHEN directed by the ERM to take turnover of dose assessment THEN:

DIRECT the EOF Dose Assessor to take turnover of dose assessment from the Technical Support Center (TSC)/Shift Radiation Protection Technician (SRPT).

CONTACT the RAG to coordinate turnover of dose assessment duties and Station Status Check List (SSCL) from the TSC/SRPT to the EOF.

IMPLEMENT Attachment 2, RSM Checklist.

Page 2 of 2

NC.EP-EP .ZZ-0601 (Q) Page 9 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 2, RSM Checklist NOTE Asterisk (*) steps may NOT be delegated (These steps have RSM designated below the place keeping initial line).

A. RSM CHECKLIST

1. The RSM should ensure the following items are performed:

a. CONTINUE/MAINTAIN the RSM log.

b. ENSURE Offsite Radiological Dose Projections are being performed lAW NC.EP-EP.ZZ-0602(0), EOF Radiological Dose Assessment, and the SSCL Page 2 is being produced every 30 minutes when a radiological release is in progress.

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

c. If necessary, COORDINATE the transportation of any contaminated injured person offsite with the RAC.

d. *AUTHORIZE issuance of Kl to offsite PSEG radiation workers, I as appropriate lAW NC.EP-EP.ZZ-0305(0), Potassium Iodide I (KI) Administration.

RSM II

e. BRIEF EOF Radiological Assessment Staff as changing conditions warrant.

f. ASSIST with Event Classification.

Page 1 of4

NC.EP-EP .ZZ-0601 (Q) Page 10 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 2, RSM Checklist (continued)

g. *PROVIDE Protective Action Recommendations (PARs), as appropriate lAW;

For Initial PAR- EP-HC-111-F4 or EP-SA-111-F4, General Emergency classification.

RSM

For PAR Upgrades- NC.EP-EP.ZZ-0404(0),

Protective Action Recommendations (PAR)

Upgrades.

RSM

h. ENSURE Laboratory and Testing Services (LTS) is contacted lAW Attachment 4.

i. PERFORM the following applicable steps if a RADIOLOGICAL RELEASE is in progress:

INFORM the Radiological Assessment Staff immediately when it is known a radiological release is in progress.

OBTAIN frequent briefings concerning the Offsite Field Team's assignments from Offsite Team Coordinator (OTC) reports.

INFORM ERM if Dose Assessment or radiological field surveys show a Protective Action Guideline (PAG) could be exceeded in an area not already covered by a PAR.

REQUEST the RAC to obtain a plant vent isotopic sample and provide the results to the Dose Assessor as soon as possible after the start of a release.

CONSIDER moving essential equipment from the Security Center and the Processing Center.

INITIATE Habitability AND Contamination Controls lAW Attachment 4 AND VERIFY the following:

No Eating or Drinking has been announced in the EOF as needed

Step-Off-Pads (SOP) have been setup as needed.

Page 2 of4

NC.EP-EP .ZZ-0601 (Q) Page 11 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 2, RSM Checklist (continued)

Radiological Postings are in place as needed.

IF a GENERAL EMERGENCY has been declared, THEN ENSURE habitability is being performed every 30 minutes lAW Attachment 4 of this procedure.

IF the current OR forecast meteorological conditions show a radiological plume will enter the NNE Sector, (EOF Location),

THEN ENSURE Emergency Ventilation is placed in service lAW Attachment 4.

INSTRUCT the D02A to PERFORM an isotopic dose assessment from the plant vent sample results, determine the NG to Iodine ratio and to communicate the results to the representatives from Delaware Emergency Management Agency (DEMA) and New Jersey Bureau of Nuclear Energy (NJBNE).

COORDINATE with the RAG and recommend travel routes, modes of transportation, and appropriate controls in/out of Salem and Hope Creek Stations for all vehicles and personnel.

IF necessary, THEN DIRECT the setup of a vehicle decontamination area, lAW NC.EP-EP.ZZ-0308(0), PersonneiNehicle Survey and Decontamination.

IF necessary, THEN DISCUSS the use of State Emergency WorkerNehicle Decon Facilities) with the Emergency Preparedness Coordinator (EPC).

OBTAIN ERM approval for Coast Guard or Helicopter assistance in tracking the plume, if thought necessary.

Page 3 of 4

NC.EP-EP .ZZ-0601 (Q) Page 12 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 2, RSM Checklist (continued)

j. PROVIDE EOF evacuation recommendations/options to the ERM based on habitability concerns or based on external events that necessitate EOF relocation:

Recommend that the EOF staff be evacuated and relocated to Salem County 911 Center/ENG

- Primary EOF Back-up Mustering Area, (refer to EP Aid-095) or the Unaffected Station's TSC.

Recommend that all portable Satellite Phones, portable radios, EOF Laptops, Field Team vehicles & monitoring equipment and one set of EGGs and EOF EP Implementing Procedures, as a minimum be moved to the relocated EOF location.

Page 4 of4

NC.EP*EP .ZZ-0601 (Q) Page 13 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 3, State Liaison Instructions A. STATE LIAISON NOTE As needed, use the following references to complete activities in this attachment

EP Aid-018, Salem SPDS MET and Rad Data

EP Aid-019, HC CRIDS SPDS MET and Rad Data

EP Aid-025, Get Weather from NOAA

EP Aid-048, Salem Radiation Monitoring System (RMS) Summary

EP Aid-049, Hope Creek Radiation Monitoring System (RMS) Summary

EP Aid-090, HC EOF RM-11 -Instructions for Radiological and Flow Data

SC.EP EP.ZZ 0301[0] Attachment 2 for Unit #1

SC.EP EP.ZZ 0301 [Q] Attachment 3 for Unit #2

1. The State Liaison Should PERFORM The Following:

ESTABLISH communications with the representatives from the States of New Jersey, Delaware, and the NRC, upon their arrival at the EOF.

ASSIST State personnel with 15 minute updates of MET/RMS data when radiological monitors are in warning, alarm, or as thought appropriate. (Delaware Emergency Management Agency (DEMA) and the New Jersey Bureau of Nuclear Engineering (NJBNE) personnel have station SPDS display terminals in their areas to obtain MET/RMS data but may need some assistance.)

IF no radiological release is in progress, THEN PROVIDE DEMA and NJBNE EOF personnel 30 minute updates of radiological plant vent effluent and meteorological data using Form-4 for Hope Creek or Form-5 for Salem dose assessment input. (This data can be obtained from the EOF dose assessors.)

IF a radiological release is in progress, THEN PROVIDE DEMA and NJBNE EOF personnel 15 minute updates of radiological plant vent effluent and meteorological data using Form-4 for Hope Creek or Form-5 for Salem dose assessment input. (This data can be obtained from the EOF dose assessors.)

Page 1 of 3

NC.EP-EP .ZZ-0601 (Q) Page 14 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 3, State Liaison Instructions (continued)

REFER State and Federal personnel to the RMS Status Board for current and trended RMS data if SPDS is not operable in the EOF.

REFER State and Federal personnel to appropriate contacts for other support in the EOF, when applicable.

2. RMS and MET Data

a. As needed, OBTAIN radiological and effluent flow data from the following sources:

HOPE CREEK SPDS and the RM-11 Displays.

SALEM SPDS Radiation Monitoring Screens and/or from Control Room FAX from the SRPT.

b. INFORM the RSM immediately, INCLUDING INTERRUPTING MEETINGS, IF

Any effluent monitor increase at Salem or Hope Creek.

Any of the High Range Containment Monitors increase to the following values:

HOPE CREEK ONLY

DAPA "A" or DAPA "B" = .:::_2,000 R/hr (indication that the fuel clad barrier has been lost)

DAPA "A" or DAPA "B" .:::_10,000 R/hr (indication of potential loss of Containment.)

SALEM UNITS 1 & 2 ONLY

R44 "A" or R44 "B" >300 R/hr (indication that the fuel clad and RCS barriers have been lost)

R44 "A" or R44 "B" >2,000 R/hr (indication of potential loss of Containment)

Page 2 of 3

NC.EP-EP.ZZ-0601(Q) Page 15 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 3, State Liaison Instructions (continued)

c. OBTAIN MET data from one of the following sources:

Hope Creek/Salem SPDS

Hope Creek/Salem TSC or Control Room

National Weather Service (NWS)

(609-261-6604 or 609-261-6602)

National Weather Service (NWS) Website

d. INFORM the RSM & Duty Dose Assessor of conditions that could initiate a PAR Upgrade (Must be at a General Emergency).

Wind Shift to a new sector

Any meteorological change which could increase the concentration of the release, such as decreasing wind speed, increasing stability class or less rain.

INCREASING Projected TEDE Dose ?:,1 ,000 I (1.0E+3) mRem (at 5 miles or 10 miles) as seen I on a MIDAS SSCL page 2. I I

OR I INCREASING Projected Thyroid Dose ?:,5,000 (5.0E+3) mRem (at 5 miles or 10 miles) as seen II on a MIDAS SSCL page 2.

Reports from an Offsite Field Team with 1 increasing dose rates. /1

e. IF SPDS is not available in the EOF THEN ENSURE the MET/RMS data is being recorded and updated on the RMS Status Board approximately every 15 minutes unless directed otherwise by the RSM.

Page 3 of 3

NC.EP-EP.ZZ-0601 (Q) Page 16 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 4, Habitability, EOF Emergency Ventilation and Laboratory and Testing Services (LTS) Instructions A. HABITABILITY AND CONTAMINATION CONTROLS

1. IF a RADIOLOGICAL RELEASE is in progress THEN PERFORM the following steps as applicable OR as directed by the RSM:

a. IMPLEMENT Contamination Controls

NO Eating or Drinking in the EOF.

SETUP Step-Off-Pads (SOP).

ESTABLISH Radiological Postings.

b. IMPLEMENT Habitability Controls

VERIFY all personnel in the EOF have dosimetry. ISSUE dosimetry to all personnel who do not have dosimetry using Sentinel or Form-2.

PLACE at least 3 electronic dosimeters within the EOF and in occupied adjoining rooms to monitor exposure.

SETUP the AIR Monitoring Sampler and set background at 2 times the current background (monitor background 30 minutes after starting).

PERFORM a habitability survey of areas inside and outside the Energy and Environmental Resource Center (EERC), as deemed appropriate by the RSM, AND LOG on Form- 3, EOF Habitability Log.

IF a GENERAL EMERGENCY is declared.

THEN PERFORM EOF Habitability surveys every 30 minutes.

LOG results on Form 3, EOF Habitability Log.

c. INFORM the RSM if any criteria below is exceeded:

External dose equivalent (EDE) dose rates are >500 mR/hr within the facility- immediate evacuation should be considered.

Page 1 of 4

NC.EP-EP.ZZ-0601 (Q) Page 17 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE , Habitability, EOF Emergency Ventilation and Laboratory and Testing Services (L TS) Instructions (continued)

EDE dose rates are >250 mR/hr, but

<500 mR/hr within the facility - evacuation within (1) hour should be considered.

The EDE dose rates are > 50 mR/hr, but < 250 mR/hr within the facility - evacuation within (2) hours should be considered.

NOTE There are two Bypass Switches which can be used to initiate the Pressurized Mode of the EOF Ventilation System. Switch # 1 is located in the Mechanical Room (Room 46) (the switch is located on the right hand wall) and Switch #2 is located in the EOF Dose Assessment area of the EOF. Both switches are three-way switches and both operate the system.

A light on the switch will illuminate when the system is running.

2. WHEN directed by the RSM, PLACE the EOF Ventilation In Pressurized Mode as follows:

a. LOCATE EOF Bypass Switch #1 or #2.

b. POSITION the Bypass Switch to the "ON" position (switch illuminates when the system is "ON").

c. LOCATE the DP Gauge next to the Lead's Conference Room in the EOF. RECORD the DP Gauge reading on the line below:

(NOTIFY the RSM if the gauge reading is < 0.025 inches)

d. NOTIFY the RSM when EOF Ventilation is in the Pressurized Mode.

e. RETURN the EOF Ventilation to the Normal Mode when Pressurized operation is no longer needed by changing position of the Bypass Switch and verifying that the light goes out.

Page 2 of 4

NC.EP-EP .ZZ-0601 (Q) Page 18 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 4, Habitability, EOF Emergency Ventilation and Laboratory and Testing Services (L TS) Instructions (continued)

B. EOF VENTILATION MAINTENANCE

1. As needed, PERFORM the following maintenance on the EOF ventilation:

a. IF the following conditions exist, THEN PERFORM the following maintenance/ALARA tasks on the EOF Emergency Ventilation HEPA Units.

IF the EOF is in the plume path, THEN ENSURE that dose rates are obtained on the HEPA filter every hour after EOF ventilation is placed in the Pressurized mode.

IF the contact dose rate is> 500 mR!hr, THEN CONSIDER changing out the HEPA unit filter.

NOTE The Radiation Protection Supervisor - Offsite may be contacted for additional technical support (people, advice concerning handling, storage, etc.) in changing out the HEPA filters, as necessary.

b. IF any of the following occurs, THEN ENSURE the HEPA units are changed out lAW NC.EP-FT.ZZ-0009(0),

Emergency Operations Facility (EOF) Ventilation System Testing.

Dose rates are >1 000 mR/hr on contact of the HEPA units.

At a high DP gauge reading (>1. 75 inches) or at the RSM's discretion (gauge on front of HEPA housing)

C. LABORATORY AND TESTING SERVICES (L TS)

NOTE LTS phone number may be obtained from the EP Phone Directory (EP Aid-005) available in the Administrative Support Area.

1. CONTACT LTS if a radioactive release is thought to be likely or a radioactive release is in progress.

Page 3 of 4

NC.EP-EP.ZZ-0601(Q) Page 19 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE , Habitability, EOF Emergency Ventilation and Laboratory and Testing Services (LTS) Instructions (continued)

2. REQUEST Personnel From LTS Perform The Following:

ASSEMBLE LTS Emergency Environmental Sampling personnel at the EOF and REPORT to the RSM.

REQUEST the coordinator from LTS REPORT to the EOF, if environmental sampling is necessary.

CONSIDER the change out of air samples and dosimetry in the down-wind sector from the radioactive plume and two sectors to each side.

ASSIST the RSM in determination of an environmental sampling plan.

After the radioactive plume is terminated, DISPATCH the environmental sampling teams to collect samples, in accordance with LTS procedures.

Page 4 of 4

NC.EP-EP .ZZ-0601 (Q) Page 20 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 5, Reserved RESERVED See EP Aid-048 (Salem)

OR EP Aid-049 (Hope Creek)

For RMS Quick Reference Page 1 of 1

NC.EP-EP .ZZ-0601 (Q) Page 21 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Attachment 6, Reserved RESERVED See EP Aid-018 (Salem) or EP Aid-019 (HC)

For aid in using Salem SPDS or HC CRIDS/SPDS OR EP Aid-090 (HC EOF RM-11)

For aid in using the HC EOF RM-11 Displays Page 1 of 1

NC.EP-EP .ZZ-0601 (Q) Page 22 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Form - 1 EOF Dosimetry Log BADGE OR INTIAL END TOTAL SRD ISSUED RTN NAME EMPLOYEE VALUE VALUE DOSE NUMBER DATE DATE NUMBER (mRem) (mRem) (mRem)

Page 1 of 1

NC.EP-EP .ZZ-0601 (Q) Page 23 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Form - 2 DLR Issue Log DLR N u m b e r : - - - - - - - - - - - - - Badge or Employee #:

To the best of my knowledge, my current annual exposure is _ _ mrem.

Name ( P r i n t / S i g n ) : - - - - - - - - - - - - - - - - - - - - Date:

DLR N u m b e r : - - - - - - - - - - - - - Badge or Employee#:

To the best of my knowledge, my current annual exposure is _ _mrem.

Name ( P r i n t / S i g n ) : - - - - - - - - - - - - - - - - - - - - Date:

DLR Issued to: ( N a m e ) : - - - - - - - - - - - - - - - - - - - - - - - - - - -

DLR N u m b e r : - - - - - - - - - - - - - Badge or Employee#:

To the best of my knowledge, my current annual exposure is _ _ mrem.

Name ( P r i n t / S i g n ) : - - - - - - - - - - - - - - - - - - - - Date:

DLR N u m b e r : - - - - - - - - - - - - - Badge or Employee #:

To the best of my knowledge, my current annual exposure is _ _mrem.

Name ( P r i n t / S i g n ) : - - - - - - - - - - - - - - - - - - - - Date:

Entry into Sentinel Complete: - - - - - - - - - - - - - - - - - Date:

(Print/Sign)

Page 1 of 1

NC.EP-EP .ZZ-0601 (Q) Page 24 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Form - 3 EOF Habitability Log DATE: - - - - - - - - - - - - - - -

Instrument Type: __________ Serial Number: _ _ _ _ Source Check Sat: 0 Yes 0 No Instrument Type: _________ Serial Number: _ _ _ _ Source Check Sat: 0 Yes 0 No DOSE RATE CONTAMINATION LOCATION TIME (mR/hr) (CPM) INITIALS Page 1 of 1

NC.EP-EP .ZZ-0601 (Q) Page 25 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Form - 4 Hope Creek MIDAS Input Date: _ _/_ _/__ Time: _ _ _ __

Wind Speed @ 33': mph Wind Speed @ 300': _ _ _ mph Wind Direction (From) @ 33': degrees Delta T: oc (0 300' -33') OR (Stability Class for _ _ _ D 150'-33' Delta T)

NPVFiow: CFM SPVFiow: CFM If process flow exists for a potential release pathway, enter the appropriate flow, otherwise mark N/A. If flow exists for the FRVS Flow: CFM pathway also enter a NG values for that pathway or mark N/A.

HTVFiow: CFM NPV NG: For NPV, SPV and FRVS use:

SPV NG: jJCi/cc Low Range if between 1.00E-08 and 1.00E-02 jJCi/cc FRVS NG: jJCi/cc Mid-Range if between 1.00E-02 and 1.00E+01 jJCi/cc H Ra if between 1.00E+01 and 1.00E+05 Ci/cc Low Range if between 1.00E-04 and 1.00E-02 jJCi/cc H 1.00E-02 and 1.00E+04 Ci/cc

~~~~~~~~~

Flow Values: The flow is based on the expected Drywell Leakage in CFM. If at the design basis leak rate of 0.5% of the containment Drywell DAPA R/hr volume per day, then assume 1.1 CFM. 10% per day leakage is Monitor Value 2.13E+01 CFM. 100% per day leakage is 2.13E+02 CFM and Catastro ic failure is 100% in and hour and is 5.11 E+03 CFM.

~~~~

Run 1 Run 2 Run 3 Run 4 Run 5 Unit= Unit= Unit= Unit= Unit=

Menu= Menu= Menu= Menu= Menu=

MixiD= MixiD= MixiD= MixiD= MixiD=

Comments:

Page 1 of 1

NC.EP-EP .ZZ-0601 (Q) Page 26 of 26 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL Rev: 13 ASSESSMENT STAFF RESPONSE Form- 5 Salem MIDAS Input

/ / D Unit #1 D Unit #2 DYES/ D NO Wind Speed @ 33': _ _ _ mph Wind Speed @ 300': _ _ _ mph Wind Direction (From)@ 33': degrees Delta T: oc (0 300' -33') OR (Stability Class for _ _ _ D 150'-33' Delta T)

If process flow exists for this release pathway, enter the appropriate flow, Plant Vent: CFM otherwise mark N/A. If process flow exists for this release pathway, enter the a NG value for the R41 or R45 value NLY For R41 use:

R41 A if between 1.00E-08 and 1.00E-02 !JCi/cc R41 NG: !JCi/cc R41 B if between 1.00E-02 and 1.00E+01 !JCi/cc R41C if between 1.00E+01 and 1.00E+05 ONLY enter S/G to atmosphere flow if a tube leakage or a tube rupture makes this a release pathway through a steam relief or a MS-10 valve.

S/G to Atm.

Lbs/hr The default flow rate is 4.50E+05 Lbs/hr but as pressure decreases so will Release:

flow, Engineering support can provide flow data but use default to avoid nol*<>u*r*n dose assessment results.. Use actual flow value when available.

ONLY enter R46 value if a S/G release to atmosphere is in progress. S/G leakage is monitored by the plant vent monitor if not through the relief or MS-1 0. A Main Steam Line (MSL) break outside of containment would R46_ mR/hr also apply.

S/G #11/21 use R46C, S/G #12/22 use R46A, S/G #13/23 use R46D and for S/G #14/24 use R46B.

This would normally be a "What If' calculation when high activities are bottled up in Containment. The Design Basis leakage is 0.1% per day Containment which is about 1.82 CFM (1.0% per day = 18 CFM, 10% per day= 182 CFM Leakage CFM, 100% per day= 1820 CFM, 100% in an hour= 43,700 CFM for Catastrophic Failure). Engineering can assist in determining the leak rates if this is the release n<:>tlh\At~>\1 R44 response to high levels of activity released to containment during a R44_ R/Hr LOCA should result in both R44 monitors reading approximately the same. Use the hest valid read from the R44s.

Run 1 Run 3 Run 4 Unit= _ __ Unit= _ __ Unit= _ __

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LR-N18-0074, Enclosure 2 to LR-N18-0074, Emergency Plan Document Revisions Implemented June 25, 2018

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LR-N18-0074, Enclosure 2 to LR-N18-0074, Emergency Plan Document Revisions Implemented June 25, 2018

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