Text

PSEG Nuclear LLC EOF Implementing Procedures Update
	ML032190058
Person / Time
Site:	Salem, Hope Creek
Issue date:	07/29/2003
From:	; Public Service Enterprise Group
To:	David Pinckney; Document Control Desk, Office of Nuclear Reactor Regulation
References
	-RFPFR
	Download: ML032190058 (98)
	v • d • e

Document Transmittal Form TO : NRC CO PINCKNEY, DAVID ID: EPIP059 DOCUMENT CONTROL DESK WASHINGTON, DC 20555 Date: 7/29/03 Please update your controlled set of documents with the following documents:

Document ID Revision Status Quantity Format RecNo PRCIAIEE TOC1000 14 A 1 H 172066 PRCINC.EP-EP.ZZ-06031000 6 A 1 H 172129 PRCINC.EP-EP.ZZ-06011000 6 A 1 H 172087 PRCINC.EP-EP.ZZ-06021000 3 A 1 H 172108 ALL PAGES of this acknowledgement receipt must be returned to:

Document Management PSEG Nuclear PO Box 236 Hancocks Bridge, NJ 08038 MC N04 Your signature below verifies that (1) the above documents have been filed and superseded documents have been removed and destroyed or clearly marked as obsolete.

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

[] Place checkmark here to be removed from controlled distribution Signature: Date:

U1t4S

PSEG NUCLEAR LLC EOF IMPLEMENTING PROCEDURES JULY 29, 2003 CHANGE PAGES FOR REVISION #14 The Table of Contents forms a general guide to the current revision of each section of the EOF EPIP. The changes that are made in this TOC Revision #14 are shown below. Please check that your revision packet is complete and remove the outdated material listed below:

ADD REMOVE Page Description Rev. Page Description Rev.

All T.O.C. 14 All T.O.C. 13 All NC.EP-EP.ZZ-0601 06 ALL NC.EP-EP.ZZ-0601 05 All NC.EP-EP.ZZ-0602 03 ALL NC.EP-EP.ZZ-0602 02 All NC.EP-EP.ZZ-0603 06 ALL NC.EP-EP.ZZ-0603 05 EPIP-EOF 1 of 1

AIEE TOC EOF Page 1 of 1 PSEG NUCLEAR LLC EMERGENCY PLAN EOF IMPLEMENTING PROCEDURES TABLE OF CONTENTS e&G July 29,2003 1SE&G EMERGENCY OPERATIONS FACILITY (EOF) PROCEDURES CONTROL pi p o si RGI(PY NAber Effective EMERGENCY COORDINATOR RESPONSE:

Number of Pae Da4 s NC.EP-EPZZ-0401(Q) Emergency Preparedness 03 7 01/31/2003 Coordinator Response NC.EP-EP.ZZ-0402(Q) Site Support Manager 03 6 01/31/2003 Team Response - EOF NC.EP-EP.ZZ-0403(Q) Public Information Liaison 03 4 03/14/2002 (PIL) - EOF NC.EP-EP.ZZ-0404(Q) Protective Action 01 10 09/14/2000 Recommendations (PARS)

Upgrades NC.EP-EP.ZZ-0405(Q) Emergency Termination! 02 22 05/07/2003 Reduction/Recovery ENGINEERING RESPONSE (EOF):

NC.EP-EP.ZZ-0501(Q) EOF - Integrated Engineering 01 6 02/06/2002

Response

RADIATION PROTECTION RESPONSE (EOF):

NC.EP-EP.ZZ-0601(Q) Radiological Support 06 24 07/29/2003 Manager And Radiological Assessment Staff Response NC.EP-EP.ZZ-0602(Q) EOF Radiological Dose 03 19 07/29/2003 Assessment NC.EP-EP.ZZ-0603(Q) Field Monitoring 06 49 07/29/2002 NC.EP-EP.ZZ-0604(Q) Helicopter Plume Tracking 01 10 05/24/2001 ADMINISTRATIVE SUPPORT RESPONSE (EOF):

NC.EP-EP.ZZ-0701(Q) Administrative Support - EOF 06 18 01/31/2003 Rev. 14

PSEG Intemal Use Only PAGE OF 1 PSEG NUCLEAR LLC NC.EP-EP.ZZ-0601 () - REV. 06 RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL ASSESSMENT STAFF

RESPONSE

USE CATEGORY: II REVISION

SUMMARY

1. Deleted the Unit 2 R16 Monitor from Attachment 5, in accordance with notification number 80045432.

2. Added the date to Form - 4 and reformatted the form slightly to address comments from users.

3. Revised Form - 1 to replace social security number to ubadge or employee number."

4. Revised Form - 2 to add or employee number."

PSE&G IMPLEMENTATION REQUIREMENTS CONTROL COPY #PffePo9 Implementation Date: 7/2l q1Zi/r3 APPROVED: - -) - -

Emer n paredness Manager te APPROVED: _____

Director - Operations Date

NC.EP-EP.ZZ-0601 (Q)

RADIOLOGICAL SUPPORT MANAGER AND RADIOLOGICAL ASSESSMENT STAFF

RESPONSE

TABLE OF CONTENTS Section Title Page 1.0 PURPOSE 2 2.0 PREREQUISITES ................................................................................ 2 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure ... 2 3.0 PRECAUTIONS AND LIMITATIONS .2 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure .2 4.0 EQUIPMENT REQUIRED . . . 2 5.0 PROCEDURE ............................................................................... 3 5.1 RSM Duties . .............................................................................. 3 6.0 RECORDS ............................................................................... 3

7.0 REFERENCES

............................................................................... 3 7.1 References . .............................................................................. 3 7.2 Cross References ................................................................................ 3 ATTACHMENTS ATTACHMENT 1 - Pre-activation RSM Duties .............................................. 4 ATTACHMENT 2 - RSM Checklist .............................................. 6 ATTACHMENT 3 - State Liaison And RMS Trending Instructions ......................................... 9 ATTACHMENT 4 - Habitability, EOF Emergency Ventilation And Maplewood Lab Instructions ............................. ................. 11 ATTACHMENT 5 - RMS Quick Reference ................................. 14 ATTACHMENT 6 - Operation Of VAX LA120 Terminal . ............................................. 18 FORMS Form - 1 EOF Dosimetry Log.21 .............................................................................

Form - 2 TLD Issue Log .22 .............................................................................

Form - 3 EOF Habitability Log . ............................................................................ 23 Form - 4 MIDAS Data Form .24 .............................................................................

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NC.EP-EP.ZZ-0601 (Q) 1.0 PURPOSE To outline and describe the Radiological Support Managers (RSM) duties during a declared emergency 2.0 PREREQUISITES 2.1 Prerequisites To Be Followed Prior To Implementing This Procedure Implement this procedure at:

The discretion of the ERM.

Upon staffing of the EOF.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precaution and Limitations To Be Followed Prior To Implementing This Procedure 3.1.1 Medical care takes priority over any radiological conditions unless the radiological conditions are life threatening.

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

3.1.3 Personnel who implement this procedure shall be trained and qualified IAW the Emergency Plan.

3.1.4 All steps listed in this procedure may be implemented at users discretion.

4.0 EQUIPMENT REQUIRED As provided in the EOF.

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NC.EP-EP.ZZ-0601 (Q) 5.0 PROCEDURE 5.1 RSM Duties 5.1.1 REPORT to the ERM to receive a briefing of the current status of the emergency.

5.1.2 UPDATE the ERM of changing radiological conditions, as appropriate.

5.1.3 IMPLEMENT Attachment 1, Pre-activation RSM Checklist.

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

7.0 REFERENCES

7.1 References None 7.2 Cross References 7.2.1 NC.EP-EP.ZZ-0602(Q) Radiological Dose Assessment 7.2.2 NC.EP-EP.ZZ-0603(Q) Field Team Monitoring 7.2.3 NC.EP-AP.ZZ-1014(Q), Emergency Preparedness Classroom Training Administration 7.2.4 NC.EP-DG.ZZ-0009(Z), Salem SPDS Operating Instructions 7.2.5 PSEG Nuclear Emergency Plan Nuclear Common Page 3of 24 Rev. 06

NC.EP-EP.ZZ-0601 (Q)

ATTACHMENT I Page 1 of 2 PRE-ACTIVATION RSM CHECKLIST 1.0 PRE-ACTIVATION RSM CHECKLIST 1.1 RSM Should Ensure The Following Items are Performed:

1.1.1 INITIATE the RSM log.

1.1.2 CONTACT the RAC for a current briefing of the on/offsite radiological conditions.

1.1.3 ASSIGN the Radiological Assessment Staff Members (D2's) functions are as follows:

Dose Assessment (Refer to NC.EP-EP.ZZ-0602(Q), Radiological Dose Assessment):

(Name) (Name)

Habitability. EOF Emergency Ventilation and Environmental Sampling Issues (Refer to Attachment 4, Habitability, EOF Emergency Ventilation and Maplewood Lab Instructions):

(Name) (Name)

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

(Name) (Name)

Coordinating and Tracking Offsite Field Teams Location and Sampling (Refer to NC.EP-EP.ZZ-0603 (Q), Field Monitoring):

(Name) (Name)

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

(Name) (Name) 1.1.4 ENSURE the Radiological Assessment Staff is staffed to perform the D2 tasks as outlined above, as thought appropriate.

1.1.5 ASSIGN personnel to fill each appropriate function and designate an Assistant RSM.

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ATTACHMENT I Page 2 of 2 1.1.6 VERIFY the following tasks are performed:

IF a General Emergency has been declared, THEN Perform EOF habitability every 30 minutes IAW Attachment 4, if thought appropriate.

EOF Radiological Assessment equipment is functioning properly.

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

Dose Assessment can be performed IAW NC.EP-EP.ZZ-0602(Q), Radiological Dose Assessment.

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

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

1.1.7 CONTACT the RAC prior to activation of the EOF to receive an update of the Inplant and Onsite radiological conditions.

1.1.8 IMPLEMENT Attachment 2, RSM Checklist:

Upon completion of Attachment 1.

As thought appropriate by the RSM.

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ATTACHMENT 2 Page 1 of 3 RSM CHECKLIST NOTE

The order that these steps may be performed at the RSM's discretion.

Asterisk (*) steps may NOT be delegated. These steps have RSM written under them.

Mark steps that are not applicable N/A and explain why the step is N/A on Attachment 8, Completion Sign-off Sheet.

RSM's Name: _ I (Print) (Sign) (Date) 1.0 RSM CHECKLIST 1.1 The RSM Should Ensure The Following Items are Performed:

1.1.1 CONTINUE keeping the RSM log.

1.1.2 ENSURE Offsite Radiological Dose Projections are being performed lAW NC.EP-EP.ZZ-0602(Q), Radiological Dose Assessment, and the SSCL Page 2 is being produced every 30 minutes.

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

1.1.3 COORDINATE the transportation of any contaminated injured person offsite with the RAC.

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ATTACHMENT 2 Page 2 of 3 1.1.4 *AUTHORIZE issuance of KI as appropriate IAW NC.EP-EP.ZZ-305(Q), Stable Thyroid Blocking.

RSM 1.1.5 BRIEF EOF Radiological Assessment Staff as changing conditions warrant.

1.1.6 ASSIST with Event Classification.

1.1.7 *PROVIDE Protective Action Recommendations (PARs), as appropriate, IAW NC.EP-EP.ZZ-0404(Q), Protective Action Recommendations (PAR).

RSM NOTE A radiological release is in progress when the Noble Gas (NG) Offsite Dose Calculation Manual (ODCM)/Federal Limits are met or exceeded.

Hope Creek ODCM Limits = 1.20E+04 uCi/sec.

Salem NG ODCM Limits = 2.42E+05 uCi/sec.

1.1.8 ENSURE Maplewood Lab is contacted by assigned personnel lAW Attachment 4, Instructions For Habitability, EOF Emergency Ventilation, and Maplewood Labs.

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

INFORM the ERM 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.

CONSIDER moving essential equipment from the Guard House and the Processing Center.

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

INITIATE Contamination Controls IAW Step 1.1.10, Part A, of this Attachment.

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A1TACHMENT 2 Page 3 of 3

DIRECT the setup of a vehicle decon area, IAW NC,EP-EP.ZZ-0308(Q)IEPIP 308S(H),

Personnel/ehicle Survey and Decontamination, if necessary.

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

1.1.10 PERFORM the following applicable steps upon the declaration of a GENERAL EMERGENCY, if thought appropriate:

A. IMPLEMENT Contamination Controls.

No Eating, Drinking, or Smoking.

Setup Step Off Pads (SOP).

Establish Radiological Postings.

B. ENSURE habitability is being performed every 30 minutes IAW Attachment 4 of this procedure.

C. ENSURE Emergency Ventilation is turned on IAW Attachment 4 of this procedure, if:

A radiological release is in progress and the current or forecast meteorological conditions show a radiological plume will enter the Sector that the EOF is located (NNE).

D. PLACE SRDs at the front and rear entrances of the Nuclear Training Center, Room 50 (Admin Support Area), and in the EOF proper. Log all SRDs on Form -1, EOF SRD Log.

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NC.EP-EP.ZZ-0601 (Q)

ATTACHMENT 3 Page 1 of 2 STATE LIAISON AND RMS TRENDING INSTRUCTIONS 1.0 STATE LIAISON 1.1 The State Liaison Should Perform The Following:

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

1.1.2 PROVIDE State personnel 15 minute updates of RMS data when radiological monitors are in warning, alarm, or as thought appropriate.

1.1.3 IF no radiological release is in progress, THEN PROVIDE Delaware Emergency Management Agency (DEMA) and New Jersey Bureau of Nuclear Engineering (NJ - BNE)

EOF personnel 30 minute updates of radiological plant vent effluent and meteorological data using Form - 4, MIDAS Data Form.

(This data can be obtained from the EOF dose assessors) 1.1.4 IF a radiological release is in progress, THEN PROVIDE DEMA and NJ - BNE EOF personnel 15 minute updates of radiological plant vent effluent and meteorological data using Form - 4, MIDAS Data Form.

(This data can be obtained from the EOF dose assessors) 1.1.5 REFER State and Federal personnel to the RMS Status Board for current and trended RMS data.

1.1.6 REFER State and Federal personnel to appropriate contacts in the EOF, when applicable.

2.0 RMS AND MET TRENDING 2.1 Perform The Following To Trend RMS And MET Data:

2.1.1 OBTAIN radiological data from the following sources:

(HOPE CREEK ONLY) VAX LA120 (Refer to Attachment 6, Operation of VAX LA120 Terminal).

(SALEM UNITS I & 2 ONLY) SPDS Radiation Monitoring Screens (Refer to NC.EP-DG.ZZ 0009(Z), Salem SPDS Operating Instructions).

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NC.EP-EP.ZZ-0601 (Q)

ATTACHMENT 3 Page 2 of 2

Control Room FAX from a Radiation Protection Technician.

A. INFORM the RSM immediately, INCLUDING INTERRUPTING MEETINGS, and then the State Liaison, if any of the High Range Containment or Effluent Monitors indicate the following values.

(HOPE CREEK ONLY)

DAPA UAI or DAPA TB" = > 5000 R/hr.(indication fuel clad barrier has been lost)

NPV, SPV, FRVS, or HTV = > 1.20E+04 uCi/sec. (NG TS limits)

(SALEM UNITS I & 2 ONLY)

R44 An or R44 "B" = > 300 R/hr. (indication fuel clad and RCS barriers have been lost)

R41 itO = 2.42E+05 uCisec. (NG TS limits) 2.1.2 OBTAIN MET data from one of the following sources:

A. VAX LA120 B. Salem or Hope Creek TSC C. Salem or Hope Creek Control Room D. National Weather Service (609-261-6604) or 609-261 -

6602) 2.1.3 ENSURE the RMS data is being recorded and updated on the RMS Status Board approximately every 15 minutes, or as instructed by the RSM.

2.1.4 INFORM the RSM if current meteorological data is within three degrees of another sector, if a PAR has been or is being made.

2.1.5 REFER to Attachment 5, RMS Quick Reference, for information on Effluent and Area Radiation Monitors at Hope Creek and Salem.

2.1.6 REFER to the Salem RMS Manual and Hope Creek Procedure HC.RP-AR.SP-0001(Q), Radiation Monitoring System Alarm Response, for more detailed RMS information.

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NC.EP-EP.ZZ-0601 (Q)

ATTACHMENT 4 Page 1 of 3 HABITABILITY, EOF EMERGENCY VENILATION AND MAPLEWOOD LAB INSTRUCTIONS 1.0 HABITABILITY 1.1 Habitability Should Be Performed In The Followinq Manner:

1.1.1 PERFORM EOF Habitability every 30 minutes, if a GENERAL EMERGENCY is declared.

1.1.2 LOG results on Form 3, EOF Habitability Log.

1.1.3 REFER to the following steps for appropriate actions to be taken:

External dose equivalent (EDE) dose rates are > 500 mR/hr. within the facility, immediate evacuation should be considered.

EDE dose rates are > 250 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.

1.1.4 PERFORM a survey of areas inside and outside the Nuclear Training Center, as thought appropriate by the RSM, and log on Form - 3, EOF Habitability Log.

1.1.5 SETUP the AIR Monitoring Sampler and set background to 2 times current background.

2.0 EOF Emergency Ventilation 2.1 Place the EOF Ventilation In Service Bv:

2.1.1 ENTER the Mechanical Room (Room 46).

2.1.2 LOCATE the EOF Bypass Switch #1 on the right hand wall.

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ATTACHMENT 4 Page 2 of 3 2.1.3 POSITION the Bypass Switch to the ON M position.

2.1.4 LOCATE the DP Gauge next to the Lead's Conference Room.

2.1.5 PRINT the DP Gauge value on the indicated line below.

(W.C.)

(DP GAUGE VALUE) 2.1.6 NOTIFY the RSM if the value indicates < 0.025 inches.

3.0 EOF VENTILATION MAINTENACE 3.1 Perform The Following Maintenance On The EOF Ventilation:

3.1.1 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, ensure the HEPA is dose rated every hour after it is started.

If the contact dose rate is > 500 mR/hr., ensure that consideration is given to changing out the HEPA units.

NOTE Contact the Radiation Protection Supervisor - Offsite, for additional technical support (people, advice concerning handling, storage, etc.) in changing out the HEPA filters, if necessary.

3.1.2 IF any of the following occurs, THEN ensure the HEPA units are changed out lAW NC.EP-EP.ZZ-1016(Z)/EPIP 1016, Test Procedures for Backup Generator Vent System and HVAC Filter Replacement.

Dose rates are> 1000 mR/hr. on contact of the HEPA units.

AtahighDP.

At the RSM's discretion.

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NC.EP-EP2Z-0601 (Q)

ATTACHMENT 4 Page 3 of 3 4.0 MAPLEWOOD LABS NOTE Maplewood Labs phone number may be obtained from Admin. Support.

4.1 Contact Maplewood Research and Testing Lab If:

A radioactive release is thought to be likely.

A radioactive release is in progress.

4.2 Request Personnel From Maplewood Labs To Perform The Following 4.2.1 ASSEMBLE emergency environmental sampling personnel.

4.2.2 CONSIDER the change out of air samples and TLDs in the downwind sector from the radioactive plume and two sectors to each side.

4.2.3 REQUEST the coordinator from Maplewood Labs to come to the EOF, if environmental sampling is going to occur.

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NC.EP-EP ZZ-0601 (Q)

ATTACHMENT 5 Page 1 of 4 RMS QUICK REFERENCE 1.0 Salem RMS (Unit I and 2)

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

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

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

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

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

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

RI OB is an (ARM) located in Containment on the 130' elevation next to the personnel airlock.

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

R34 is an ARM located in the Mechanical Penetration across from the 100' elevation Containment personnel Airlock.

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

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

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

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

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

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

There is a potential for an unmonitored release from this Penetration.

Ranges: 1E-01 to I E+07 mR/hr Nuclear Common Page 140of24 Rev. 06

NC.EP-EP.ZZ-0601 (Q)

ATTACHMENT 5 Page 2 of 4 NOTE

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

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

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

Ranges: I E-07 to 1E-01 uCUcc R41B is the Mid Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1E-04 to 1E-02 uCicc R41C is the High Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1E-01 to 1E+05 uCi/cc R41D is the Effluent Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: OE+OQ to 1E+1 3 uCi/Sec (The R41 D should not be used in MIDAS to perform manual dose assessment calculations)

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

Ranges: 1E-03 uCicc to 1E+01 uCi/cc R45C is the Backup High Range Noble Gas Monitors and is located in the R45 Shed behind the Fuel Handling Building. This monitor should not be used unless the R41 monitors are inoperable.

Ranges: 1E-01 uCicc to 1E+05 uCi/cc Nuclear Common Page 1 of 24 Rev. 06

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ATTACHMENT 5 Page 3 of 4 2.0 Hope Creek NOTE All ARM's in the Reactor Building have maximum ranges of 1.OOE+04 mR/hr, except for the Inner Tip Room Monitor (9RX699). The Inner Tip Room Monitor's maximum range is 1.OOE+07 mR/hr.

DAPA A and DAPA B (9RX635 and 9RX636) are high range ARMs in the Drywell.

DAPA A is approximately twice as high as DAPA B under normal operating conditions.

During a LOCA in the Drywell the two monitors should start to trend closer together due to the atmospheric conditions in the Drywell affecting both monitors equally.

Increases on both of these monitors while DAPA A's reading stays about twice of what DAPA B is reading, would be an indication of fuel damage.

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

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

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

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

Ranges: 1.OOE-01 to 1.OOE+04 mR/hr Nuclear Common Page 16 of 24 Rev. 06

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ATTACHMENT 5 Page 4 of 4 FRVS Effluent monitor (9RX680) monitors what is going out the FRVS Plant Vent.

Under normal operating conditions Reactor Building ventilation would vent through the South Plant Vent. Under accident conditions or when manually initiated, Reactor Building Ventilation isolates and the Reactor Building will vent through the FRVS. FRVS is always a ground release. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to .OOE+12 uCilSec North Plant Vent Effluent (NPV) monitor (9RX590) monitors Offgas and the chemistry lab fume hoods. NPV could be a ground or elevated release depending on the time of year and wind speed. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to I.OOE+12 uCi/Sec South Plant Vent Effluent (SPV) monitor (9RX68t,) monitors Service Radwaste Building, Turbine Building and the Reactor Building (if FRVS hasn't been initiated).

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

Ranges: 1.OOE+00 to .OOE+12 uCi/Sec Hardened Torus Vent Effluent (HTV) monitor (9RX518) would be used to vent the Drywell to relieve pressure. The path it would take would be through the Torus and take advantage of the scrubbing properties of the Torus water, but the release would considered to be an unfiltered release. lodines and particulates could be a major concern. Control Room operators would have to open a valve to use this release path.

Sampling from the PASS Torus Gas Space should be performed to provide information as to what is being released. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: O.OOE+00 to 2.09E+12 uCi/Sec Nuclear Common Page 17of 24 Rev. 06

NC.EP-EP.2Z-0601 (Q)

ATTACHMENT 6 Page 1 of 3 OPERATION OF THE VAX LA120 TERMINAL 1.0 Meteorological Data 1.1 Perform The Following to Obtain Current 15 Minute Average Meteorological Data:

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

1.1.2 ENTER MET and depress the RETURN key NOTE The most current meteorological data should be printed out followed by the Main Meteorological Menu. If no other keys are depressed, the current i5 minute average data will be printed out every 15 minutes.

Meteorological data may be obtained from the Salem SPDS lAW NC.EP-DG.ZZ-0009(Z)

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

ENTER Option 1 (Display Current Meteorological Data) and depress the RETURN key to receive the current 15 meteorological data print out and assume having the current 15 minute MET data printout automatically.

1.2 Perform The Following Steps to Obtain Archived Meteorological Data:

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

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

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

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ATTACHMENT 6 Page 2 of 3 1.2.5 IF you want data from another date and time, THEN go to Step 1.2.6.

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

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

1.2.8 ENTER the end date and time as shown below and depress the RETURN key. (For December 28, 1989 at 0230 enter 28-DEC-1 989 "depress the space bar once" and enter 02:30).

1.2.9 ENTER "Y"if the information is correct or N"if the information is not correct and re-enter it as shown in Step 1.2.6.

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

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

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

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

2.1.4 SELECT Option 1 for Hope Creek.

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

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

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

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

2.2.2 ENTER EOF and depress the RETURN key. (A prompt should be.

displayed asking for PASSWORD).

Nuclear Common Page 19 of 24 Rev. 06

NC.EP-EP.ZZ-0601 (Q)

ATTACHMENT 6 Page 3 of 3 2.2.3 ENTER EOFUSER and depress the RETURN key. (The EOF Plant Menu should be displayed).

2.2.4 SELECT option 1 for Hope Creek.

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

2.2.6 SELECT and enter option number 6 (15 Minute Historical Data).

(Current system date and time should be displayed. A prompt should be displayed for start date and time) 2.2.7 IF this is the data you want, THEN depress the RETURN key. (Your option will be printed out).

2.2.8 IF you want data from another date and time, THEN go to Step 2.2.9.DEPRESS the RETURN key for 15 minute average RMS and MET data. (Your selection will be printed).

2.2.9 ENTER start date and time as shown below and depress the RETURN key. (For December 27, 1989 at 0130 enter 27-DEC-1 989 udepress the space bar once" and enter 01:30).

2.2.10 ENTER Y" if the information is correct or N" if the information is not correct and reenter it as shown in Step 2.2.9.

2.2.11 ENTER the end date and time as shown below and depress the RETURN key. (For December 28, 1989 at 0230 enter 28-DEC-1 989 "depress the space bar once" and enter 02:30).

2.2.12 ENTER uY" if the information is correct or N" if the information is not correct and re-enter it as shown in Step 2.2.9.

Nuclear Common Page 2 of 24 Rev. 06

NC.EP-EP.2Z-0601 (Q)

FORM - I Page 1 of I EOF DOSIMETRY LOG NAME SRD BADGE OR ISSUED RTN INTIAL END TOTAL NUMBER EMPLOYEE DATE DATE VALUE VALUE DOSE NUMBER (mRem) (mRem) (mRem)

4. 4 4. 4 1 4. 4

4. 4. 4. 4 4 4. 4 1* 1 I I I* I

4. 4. 4. 4 4 4. I

4. 4. 4. I I 4. I

4. 4 4. I I 4. I

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

4. 4. 4. 4 4 4. I

4. 4. 4. 4 4 4. 4 7 4. 4. I I 4. 4

4. 4 4. I I I I

4. 4 4. I 1 4. 1

4. 4. 4. 4 I 4. 4

- i. A I b I Nuclear Common Page 21 of 24 Rev. 06

NC.EP-EP.ZZ-0601 (Q)

FORM-2 Page 1 of I TLD ISSUE LOG Name_

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

Signature_

Date Name Date_

TLD Number Badge or Employee Number_

To the best of my knowledge, my current annual exposure is mrem.

Signature_

Date Name_

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

Signature Date_

Nuclear Common Paae g __ of _24.

22 _ Rev. 0

NC.EP-EP.2Z-0601 (Q)

FORM - 3 Page 1 of I EOF HABITABILITY LOG DATE:

DOSE RATE CONTAMINATION

. LOCATION TIME (mRlhr) (CPM) INITIALS I I I I I

_ _ __ _ _ __ _ I.

_ _ _ I _ _ _ _ _ _ I _ _ _

4 4. 4.

.4 1* t

.4 4. 4 -- 4

.4 I. 4.

Nuclear Common Page 23 of 24 Rev. 06

NC.EP-EP.2Z-0601 (Q)

FORM- 4 Page 1 of 1 MIDAS DATA FORM DATE: TIME:

SALEM UNIT 1/ 2 RELEASE CONCENTRATION AND PLANT VENT FLOW RATE (CIRCLE ONE)

Monitor Monitor Monitor Monitor PLANT VENT R41A R41B R41C OTHER FLOW RATE (uCi/ce) (uCi/cc) (uCilcc) (uCi/cc) (cfm)

HOPE CREEK RELEASE CONCENTRATION AND PLANT VENT FLOW RATE FRVS NPV SPV OTHER VENT VENT VENT VENT MONITOR MONITOR MONITOR MONITOR FLOW FLOW FLOW FLOW FRVS SPV NPV OTHER RATE RATE RATE RATE (uCi/cc) (uCi/cc) (uCi/cc) (uCi/cc) (cfm) (cfm) Win) (cfm)

METEOROLOGICAL DATA WIND DIR WIND WIND WIND 33 DIR.

SPEED SPEED FOOT 300 300-33 33 300 - FROM - FOOT STABILITY AMBIENT FOOT FOOT (degrees) - FROM - CLASS TEMP. RAIN (mph) (mph) (degrees) (degree C) (degrees C) (inches)

Nuclear Common Page 24 of 24 Rev. 06

PSEG Internal Use Only PAGE OF PSEG NUCLEAR LLC NC.EP-EP.ZZ-0602 (Q - REV. 03 EOF RADIOLOGICAL DOSE ASSESSMENT USE CATEGORY: II REVISION

SUMMARY

1. Deleted reference to the Unit 2 R16 radiation monitor inAttachment 4 in accordance with notification number 80045432.

PSE&G CONTROL COPY #ros-By~ IMPLEMENTATION REQUIREMENTS Implementation date: 7 / 2 '7 ;z'v3' APPROVED: - 7 1i Enrgency Preparedness Manager APPROVED: A 7/ft I//1 Director - Operations Date

NC.EP-EP.ZZ-0602 (Q)

EOF RADIOLOGICAL DOSE ASSESSMENT TABLE OF CONTENTS Section Title Page 1.0 PURPOSE 2 2.0 PREREQUSITES .2 3.0 PRECAUTIONS AND LIMITATIONS .2 4.0 EQUIPMENT REQUIRED .2 5.0 PROCEDURE .2 5.1 Radiological Assessment Duties .2 6.0 RECORDS .6

7.0 REFERENCES

.6

7.1 REFERENCES

.6 7.2 CROSS REFERENCES .6 ATTACHMENTS ATTACHMENT 1 - Operation Of The VAX LA120 Terminal .......................................... 7 ATTACHMENT 2- Radiological Based Protective Action Recommendation Flow Chart and Worksheet.............................................................................................. 10 ATTACHMENT 3- MIDAS Report Guidance .......................................... 12 ATTACHMENT 4- RMS Quick Reference .......................................... 13 ATTACHMENT 5- Iodine Correction Factor .......................................... 17 Nuclear Common Page 1 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q) 1.0 PURPOSE Provide direction to EOF Radiological Dose Assessment staff for proper performance of their duties and responsibilities.

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

At the discretion of the ERM.

Upon staffing of the EOF.

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

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

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

4.0 EQUIPMENT REQUIRED As provided in the EOF.

5.0 PROCEDURE 5.1 RADIOLOGICAL ASSESSMENT DUTIES 5.1.1 OBTAIN a briefing on current radiological conditions and the emergency status from the Radiological Support Manager (RSM) or RSM designee. The following information should be provided during the briefing.

NOTE A radiological release is in progress when the Noble Gas (NG) Offsite Dose Calculation Manual (ODCM)/Federal Limits are met or exceeded.

Hope Creek ODCM Limits = 1.20E+04 uCi/sec.

Salem NG ODCM Limits = 2.42E+05 uCVsec.

Nuclear Common Page 2 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

A. IS a radiological release in progress?

B. IF YES, THEN what magnitude is the radiological release uCVSec and the time it started ?

C. HAVE any Protective Action Recommendations (PARs) been made or are about to be made?

D. IF YES, THEN what PAR(s) were or will be made?

E. HAVE any Fission Product Barriers (RCS, Fuel, Containment) been breached?

F. IF YES, THEN which barriers have been breached?

G. WHAT is the Emergency classification and the basis?

5.1.2 IF a log book is being kept, THEN RECORD any pertinent information or data in the EOF Dose Assessment Log Book, as time permits.

NOTE A blank Station Status Checklist (SSCL) may be obtained from ECG Attachment 8.

5.1.3 IF automatic data acquisition is operational, THEN go to Step 5.1.7 and:

A. IMPLEMENT NC.EP-EP.ZZ-0309(Q, Dose Assessment.

B. PERFORM dose assessment in automatic mode.

C. OBTAIN a SSCL.

5.1.4 IF automatic data acquisition is NOT operational, THEN:

A. IMPLEMENT NC.EP-EP.ZZ-0309(Q).

B. PERFORM dose assessment in manual mode.

C. OBTAIN a SSCL.

5.1.5 OBTAIN radiological data to perform manual dose assessment from one of the following sources:

Nuclear Common Page 3 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

(HOPE CREEK ONLY) VAX LA120, IAW Attachment 1 of this procedure.

(HOPE CREEK ONLY) A Control Point FAX of RMS Status Sheet.

(SALEM I & 2 ONLY) A Control Room FAX. of Radiological Assessment Data Sheet.

(SALEM I & 2 ONLY) SPDS Radiation Monitoring Screens

[Refer to NC.EP-DG.ZZ-0009(Z), SPDS Operating Instructions].

5.1.6 OBTAIN meteorological data to perform manual dose assessment from one of the following sources:

(HOPE CREEK ONLY) VAX LA120, lAW Attachment 1 of this procedure.

(HOPE CREEK ONLY) A Control Point FAX.

(SALEM I & 2 ONLY) A Control Room FAX.

(SALEM I & 2 ONLY) SPDS Radiation Monitoring Screens

[Refer to NC.EP-DG.ZZ-0009(Z), Salem SPDS Operating Instructions].

(HOPE CREEK, SALEM I & 2) If the meteorological data can NOT be obtained from any other source, call the National Weather Service at 609-261-6604 or 609-261-6602.

5.1.7 IF the SSCL indicates a radiological release is in progress, THEN implement Attachment 2, Radiological Based PAR and PAR Worksheet, to determine if a PAR is necessary.

A. IF necessary, THEN determine the PAR.

B. REVIEW the SSCL and PAR with the RSM.

C. INFORM the RSM that the EOF is ready to assume the SSCLUDose Assessment duties.

5.1.8 IF the SSCL indicates a radiological release is NOT in progress, THEN:

A. REVIEW the SSCL with the RSM.

B. INFORM the RSM that the EOF is ready to assume the SSCLUDose Assessment duties.

Nuclear Common Page4 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q) 5.1.9 PRODUCE the SSCL every 30 minutes and present it to the RSM under any of the following conditions:

IF a radiological release is in progress.

IF the EOF is activated.

IF asked to do so by the RSM.

5.1.10 DETERMINE which MIDAS reports to print out and present to the RSM, IAW Attachment 4, MIDAS Report Guidance.

5.1.11 TRACK and trend the affected Plant's radiological conditions by monitoring the RMS. Refer to Step 5.1.5 for methods to obtain RMS data.

5.1.12 IF any of the following conditions occur to RMS values, THEN notify the RSM immediately, followed by the State Liaison(s):

(HOPE CREEK ONLY) SSCL Noble Gas or Noble Gas value on the VAX LAI20 for North Plant Vent (NPV), South Plant Vent (SPV), Filtration Recirculation Ventilation System (FRVS), and/or Hardened Torus Vent (HTV) > 1.20E+04 uCi/Sec.

(SALEM & 2 ONLY) SSCL Noble Gas or Noble Gas value on SPDS > 2.42E+05 uCi/Sec.

NOTE Refer to the Salem RMS Manuals or HC.RP-AR.SP-0001 (Q) or the Hope Creek Radiation Protection Radiation Monitoring System Alarm Response Procedure, for additional information than what is contained in Attachment 4, RMS Quick Reference for Salem or Hope Creek RMS.

Nuclear Common Page of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q) 5.1.13 REVIEW Attachment 4, RMS Quick Reference, for information concerning effluent, some area radiation monitors (ARM),

Containment and Drywell ARMs.

5.1.14 IF a radiological release is in progress, THEN calculate a Noble Gas to Iodine Correction Factor (ICF), IAW Attachment 5, Iodine Correction Factor, when possible.

5.1.15 IF WHAT IF" dose assessment scenarios are necessary, THEN implement NC.EP-EP.ZZ-0313(Q), Advanced Dose Assessment.

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

7.0 REFERENCES

7.1 References None 7.2 Cross References 7.2.1 NC.EP-EP.ZZ-0309(Q), Dose Assessment 7.2.2 NC.EP-EP.ZZ-0313(Q), Advanced Dose Assessment (MIDAS) Instructions 7.2.3 HC.RP-AR.SP-0001(Q). Salem RMS Manuals 7.2.4 NC.EP-EP.ZZ-0601 (Q), Radiological Dose Assessment 7.2.5 NC.EP-AP.ZZ-1014(Q), Emergency Preparedness Classroom Training Administration 7.2.6 PSEG Nuclear Emergency Plan 7.2.7 NC.EP-DG.ZZ-0009(Z), Salem SPDS Operating Instructions Nuclear Common Page 6of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

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

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

1.1.2 ENTER MET and depress the RETURN key NOTE The most current meteorological data should be printed out followed by the Main Meteorological Menu. If no other keys are depressed, the current 15 minute average data will be printed out every 15 minutes.

Meteorological data may be obtained from the Salem SPDS lAW NC.EP-DG.ZZ-0009(Z).

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

ENTER Option 1 (Display Current Meteorological Data) and depress the RETURN key to receive the current 15 meteorological data print out and assume having the current 15 minute MET data printout automatically.

1.2 Perform The Following Steps to Obtain Archived Meteorological Data:

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

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

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

Nuclear Common Page 7of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT I Page 2 of 3 1.2.5 IF you want data from another date and time, THEN go to Step 1.2.6.

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

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

1.2.8 ENTER the end date and time as shown below and depress the RETURN key. (For December 28, 1989 at 0230 enter 28-DEC-1 989 "depress the space bar once" and enter 02:30).

1.2.9 ENTER Y" if the information is correct or N" if the information is not correct and re-enter it as shown in Step 1.2.6.

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

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

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

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

2.1.4 SELECT Option 1 for Hope Creek.

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

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

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

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

2.2.2 ENTER EOF and depress the RETURN key. (A prompt should be*

displayed asking for PASSWORD).

Nuclear Common Page8 f 9 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT I Page 3 of 3 2.2.3 ENTER EOFUSER and depress the RETURN key. (The EOF Plant Menu should be displayed).

2.2.4 SELECT option 1 for Hope Creek.

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

2.2.6 SELECT and enter option number 6 (15 Minute Historical Data).

(Current system date and time should be displayed. A prompt should be displayed for start date and time) 2.2.7 IF this is the data you want, THEN depress the RETURN key. (Your option will be printed out).

2.2.8 IF you want data from another date and time, THEN go to Step 2.2.9.DEPRESS the RETURN key for 15 minute average RMS and MET data. (Your selection will be printed).

2.2.9 ENTER start date and time as shown below and depress the RETURN key. (For December 27, 1989 at 0130 enter 27-DEC-1 989 "depress the space bar once" and enter 01:30).

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

2.2.11 ENTER the end date and time as shown below and depress the RETURN key. (For December 28, 1989 at 0230 enter 28-DEC-1 989 udepress the space bar once" and enter 02:30).

2.2.12 ENTER Y" if the information is correct or UN' if the information is not correct and re-enter it as shown in Step 2.2.9.

Nuclear Common Page9 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 2 Page OF 2 RADIOLOGICAL BASED PROTECTIVE ACTION RECOMMENDATION FLOW CHART AND WORKSHEET Initial Conditions: If Rad PAR review criteria is not exceeded, Rad PAR is not required.

NC.EP-EP.ZZ-0602 (Q)

A1TACHMENT 2 Page 2 of 2 WIND DIRECTION FROM PAR AFFECTED SECTORS DEGREES COMPASS DOWNWIND +/-1 SECTORS 349 - 011 N SSE - S - SSW 011 - 034 NNE => S-SSW-SW 034- 056 NE SSW- SW- WSW 056- 079 ENE => SW-WSW-W 079- 101 E =:> WSW- W- WNW 101-124 ESE D W-WNW-NW 124 - 146 SE WNW-NW-NNW 146 - 169 SSE NW-NNW-N 169-191 S NNW - N - NNE 191-214 SSW N-NNE-NE N

214 - 236 SW => NNE-NE-ENE 236 - 259 WSW _ _ Ni - ENE - E 259 - 281 W ENE - E - ESE 281 - 304 WNW E - ESE - SE 304 - 326 NW ESE- SE- SSE 326 - 349 NNW __ SE - SSE - S

___ NOTE: CONSIDER ADDING A SECTOR TO THE PAR IF THE WIND DIRECTION (FROM) IS WITHIN +/- 3° OF A SECTOR DIVIDING LINE.

10 3490 MILES

... NORTH 2810 0790 101° 2590 Nuclear Common Page 11 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 3 Page of I MIDAS REPORT GUIDANCE NOTE This Attachment is to be used only as a guidance.

Depending on the RSM's requests, more or less reports may be asked for.

1.0 NO RADIOLOGICAL RELEASE IN PROGRESS Print Out The Following Plots

TEDE 4-DAY DOSE PLOT

As requested by the RSM.

2.0 RADIOLOGICAL RELEASE IN PROGRESS Print Out The Following Plots And Prints.

MIDAS TEDE 4-DAY PLOT (FOR LEADS MEETINGS).

MIDAS TEDE DOSE RATE PRINT

MIDAS THYROID CDE DOSE RATE PRINT

MIDAS PROJECTED DOSE

SUMMARY

PRINT

MIDAS MET AND RAD

SUMMARY

PRINT Nuclear Common Page 12 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 4 Page 1 of 4 RMS QUICK REFERENCE 1.0 Salem RMS (Unit I and 2)

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

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

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

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

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

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

RIOB is an (ARM) located in Containment on the 130' elevation next to the personnel airlock.

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

R34 is an ARM located in the Mechanical Penetration across from the 100' elevation Containment personnel Airlock.

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

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

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

R44B is a (HARM) located in Containment on the 100' elevation between the R1 OA and R7 ARMs.

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

R47 is an ARM located in the 78' Electrical Penetration. The PASS lines are located in the overhead. The skid and PASS lines may be the source of any increase in this area.

This Penetration has its own ventilation flow path and will vent directly into the atmosphere. There is a potential for an unmonitored release from this Penetration.

Ranges: 1E-01 to IE+07 mR/hr Nuclear Common Page 13of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 4 Page 2 of 4 NOTE

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

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

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

Ranges: E-07 to 1E-01 uCi/cc R41B is the Mid Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: E-04 to E-02 uCi/cc R41C is the High Range Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: 1E-01 to 1E+05 uCi/cc R41 D is the Effluent Noble Gas Monitor and is located on the R41 Sample Skid on the 122' elevation of the Auxiliary Building next to the door to the stairs.

Ranges: OE+OO to I E+13 uCVSec (The R41 D should not be used in MIDAS to perform manual dose assessment calculations)

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

Ranges: 1E-03 uCi/cc to 1E+01 uCi/cc R45C is the Backup" High Range Noble Gas Monitors and is located in the R45 Shed behind the Fuel Handling Building. This monitor should not be used unless the R41 monitors are inoperable.

Ranges: I E-01 uCi/cc to 1E+05 uCi/cc Nuclear Common Page 14 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 4 Page 3 of 4 2.0 Hope Creek NOTE All ARM's in the Reactor Building have maximum ranges of 1.OOE+04 mR/hr, except for the Inner Tip Room Monitor (9RX699). The Inner Tip Room Monitor's maximum range is 1.OOE+07 mR/hr.

DAPA A and DAPA B (9RX635 and 9RX636) are high range ARMs in the Drywell.

DAPA A is approximately twice as high as DAPA B under normal operating conditions.

During a LOCA in the Drywell the two monitors should start to trend closer together due to the atmospheric conditions in the Drywell affecting both monitors equally.

Increases on both of these monitors while DAPA A's reading stays about twice of what DAPA B is reading, would be an indication of fuel damage.

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

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

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

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

Ranges: 1.00E-01 to 1.OOE+04 mR/hr Nuclear Common Page 15 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 4 Page 4 of 4 FRVS Effluent monitor (9RX680) monitors what is going out the FRVS Plant Vent.

Under normal operating conditions Reactor Building ventilation would vent through the South Plant Vent. Under accident conditions or when manually initiated, Reactor Building Ventilation isolates and the Reactor Building will vent through the FRVS. FRVS is always a ground release. Values > .20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.OOE+12 uCi/Sec North Plant Vent Effluent (NPV) monitor (9RX590) monitors Offgas and the chemistry lab fume hoods. NPV could be a ground or elevated release depending on the time of year and wind speed. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: 1.OOE+00 to 1.OOE+12 uCi/Sec South Plant Vent Effluent (SPV) monitor (9RX580) monitors Service Radwaste Building, Turbine Building and the Reactor Building (if FRVS hasn't been initiated).

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

Ranges: 1.OOE+00 to 1.OOE+12 uCi/Sec Hardened Torus Vent Effluent (HTV) monitor (9RX518) would be used to vent the Drywell to relieve pressure. The path it would take would be through the Torus and take advantage of the scrubbing properties of the Torus water, but the release would considered to be an unfiltered release. lodines and particulates could be a major concern. Control Room operators would have to open a valve to use this release path.

Sampling from the PASS Torus Gas Space should be performed to provide information as to what is being released. Values > 1.20E+04 uCi/Sec would be an indication that a radiological release is in progress.

Ranges: O.OOE+00 to 2.09E+12 uCi/Sec Nuclear Common Page 16 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 5 Page 1 of 3 IODINE CORRECTION FACTOR 1.0 IODINE CORRECTION FACTOR CALCULATION USING PLANT VENT DATA 1.1 Perform The Following To Obtain An Iodine Correction Factor:

1.1.1 OBTAIN the Plant vent Iodine 131 data in uCi/cc from the Radiation Protection Supervisor-Offsite (RPS-Offsite) located in the TSC.

1.1.2 OBTAIN the Plant Vent RMS Noble Gas value in uCi/cc from the appropriate effluent monitor that the radiological release is being discharged from.

1.1.3 DIVIDE the Iodine value by the Plant Vent Noble Gas value Ttis will produce the Iodine Correction Factor (ICF)

Iodine 131 (uCi/cc) = ICF Plant Vent RMS Noble Gas Value (uCi/cc) 1.1.4 MULTIPLY most current RMS Noble Gas monitor value by the ICF.

The product will be the Corrected Iodine Value.

1.1.5 OBTAIN the Corrected Iodine Value at least every 30 minutes by multiplying the most current Plant Vent RMS Noble Gas monitor value by the ICF.

1.1.6 IMPLEMENT NC.EP-EP.ZZ-0309(Q)/EPIP 309S(H), Dose Assessment, Attachment 3, Manual Dose Assessment, and follow appropriate steps.

1.1.7 INPUT the Corrected Iodine Value into the appropriate RMS - Di location on the MIDAS spread sheet (i.e., FRVS - Di, 2R45B - Di, etc.).

Nuclear Common Page 17 of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 5 Page 2 of 3 NOTE Use the current Plant Vent flow rate for the -DI flow rate.

1.1.8 UPDATE the ICF whenever more recent Plant Vent Iodine 131 is available.

2.0 IODINE CORRECTION FACTOR CALCULATION USING FIELD TEAM DOSE PROJECTION DATA NOTE

The following method will only work if the Field Monitoring Team data is collected at the MIDAS projected center line at a distance of 2, 5, or 10 miles.

The primary methodology of obtaining the ICF should be performed IAW Section 1.0 of this Attachment 2.1 Perform The Following To Obtain An ICF From Field Monitoring Data:

2.1.1 RUN an automatic SSCL. Use the Plant Vent Noble Gas RMS monitor value and current 15 minute MET data if in Manual MIDAS mode.

2.1.2 RECORD the Projected Dose Rate of interest (SSCL TEDE DOSE RATE) in Space A., the distance in miles in Space B., and the direction in Space C.

A. (mRem/hour TEDE Rate) B. (Miles) C. (Degrees)

Nuclear Common Page 18of 19 Rev. 03

NC.EP-EP.ZZ-0602 (Q)

ATTACHMENT 5 Page 3 of 3 2.1.3 RECORD the Projected X/Q of interest (SSCL X/Q) in Space D.

D._

2.1.4 RECORD the Field Team's measured CLOSED WINDOW reading at the location of interest in Space E.

E. mRlhour 2.1.5 RECORD the Field Team Iodine 131 Sample in uCilcc in Space F.

IAW NC.EP-EP.ZZ-0603(Q), Field Monitoring.

F. uCi/cc 2.1.6 CALCULATE the Iodine 131 Release Rate as follows and record in Space G.:

A

1

F

1.OOE+06 = G. (uCi/Sec)

E D (1.00E+06 = Conversion Factor from Cubic Meters to cc) 2.1.7 OBTAIN the Noble Gas Release Rate (uCilSec) using the same SSCL the TEDE DOSE RATE and XIQ that were obtained from and record in Space H.

H._

2.1.8 DETREMINE the Iodine Correction Factor (ICF) as follows:

Iodine Release Rate in uCi/Sec (Space G.) = ICF Noble Gas Release Rate in uCi/Sec (Space H.)

2.1.9 FOLLOWthe directions in 1.0, Steps 1.1.4 - 1.1.9 of this Attachment for instructions in the proper use of the ICF.

Nuclear Common Page 19 of 19 Rev. 03

PSEG Internal Use Only Page of PSEG NUCLEAR LLC NC.EP-EP.ZZ-0603(Q) - REV. 06 FIELD MONITORING USE CATEGORY: 1l

1. Revised Attachment 8, Section 1.1.13 concerning the loading and use of respirators, in accordance with (AW) notification number 80061439.

2. Revised Attachment 4's Note prior to Step 2.0, to say Field Sample Form, instead of Air Sample Form, lAW notification number 80061439.

IMPLEMENTATION REQUIREMENTS PSE&G Implementation Effective Date: 7 /;f/;23 CONTROL COPY # EPoSj APPROVED:

Em ency Preparedness Manager 4ate APPRCVED: C<)Diec .o 7/ga/F

/ 40perations Diector F 'FDate

ML032190058

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