LR-N19-0065, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements

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License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements
ML19189A316
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 07/08/2019
From: Mannai D
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LAR H19-05, LAR S19-05, LR-N19-0065
Download: ML19189A316 (32)
v • d • e


Text

{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0PSEG NudearLLC 10 CFR 50.90 LR-N19-0065 10 CFR 50.54(q) LAR S19-05 LAR H19-05 JUL 0 8 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 SALE M GENERATING STATION, UNITS 1 AND 2 RENEWE D FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 NRC DOCKET NOS. 50-272 AND 50-311 HOPE CREEK GENERATING STATION RENEWE D FACILITY OPERATING LICENSE NO. N PF-57 NRC DOCKET NO. 50-354

Subject:

License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements Pursuant to 10 CFR 50.90, PSEG Nuclear LLC (PSEG) is requesting U.S. Nuclear Regulatory Commission (NRC) approval of proposed changes to the Radiological Emergency Preparedness Plan for the facilities listed above. The proposed changes would revise certain Emergency Response Organization (ERO) positions for the facilities listed with the minimum staff ERO guidance specified in the "Alternative Guidance for Licensee Emergency Response Organizations," finalized in a letter from the NRC to the Nuclear Energy Institute (NEI), June 12, 2018. The guidance will be included in Revision 2 of NUREG-0654/FEMA-RE P-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." The proposed changes have been reviewed considering the requirements of 10 CFR 50.47, "Emergency plans, " paragraph (b), 10 CFR 50 Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities," and other applicable emergency preparedness NRC guidance documents. An evaluation of the proposed changes pursuant to 10 CFR 50.54, "Conditions of licenses," paragraph (q), "Emergency plans, " determined that the proposed changes require prior NRC approval.

JUt 0 8 2019 10 CFR 50.90 Page 2 10 CFR 50.54(q) LR-N19-0065 PSEG has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 10 CFR 50.92, "Issuance of amendments." The proposed changes have been reviewed by the Fleet Review Committee in accordance with the requirements of the PSEG Quality Assurance Program. provides a description and assessment of the proposed changes. Enclosure 1 provides the existing Emergency Plan marked up pages. Enclosure 2 provides clean copies of the proposed changes. The proposed changes have no effect on offsite responses. Emergency Preparedness representatives in the States of New Jersey (NJ Bureau of Nuclear Engineering - NJBNE) and Delaware (Delaware Emergency Management Agency - DE MA) have reviewed and are in agreement with the proposed Emergency Plan changes. PSEG requests NRC approval of the proposed License Amendment within one year of submittal to be implemented within 60 days of issuance. There are no regulatory commitments contained in this letter. In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), PSEG is notifying the State of New Jersey of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official. If you have any questions or require additional information, please contact Mr. Lee Marabella at (856) 339-1208. I declare under penalty of perjury that the foregoing is true and correct. Executed on _....tf._'J. 

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(Date) Respectfully, {jt-- David Mannai Senior Director, Regulatory Operations & Nuclear Oversight

Attachment:

1. Evaluation of Proposed Changes

Enclosures:

1. Emergency Plan Marked-Up Pages
2. Emergency Plan Clean Copy Pages

JUt 0 8 2019 1 0 CFR 50.90 Page 3 1 0 CFR 50.54(q) LR-N 1 9-0065 cc: Administrator, Region I, NRC Project Manager, NRC NRC Senior Resident Inspector, Salem NRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Chief, NJBNE Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. T. Cachaza, Site Regulatory Compliance Commitment Tracking Coordinator

LR-N 1 9-0065 Attachment 1 Evaluation of Proposed Changes

LR-N 1 9-0065 LAR S 1 9-05 LAR H 1 9-05 SALE M GENERATING STATION AND HOPE CREEK GENERATING STATION RENEWE D FACILITY OPERATING LICENSE NOS. DPR-70. DPR-75 AND N PF-57 DOCKET NOS. 50-272. 50-3 1 1 AND 50-354 Evaluation of Proposed Changes

Subject:

License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements Table of Contents 1 .0

SUMMARY

DESCRIPTION 2.0 DETAILE D DESCRIPTION

2. 1 Proposed Changes 2.2 Bases For Proposed Changes

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration Analysis 4.4 Conclusions

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

Supporting Enclosures Enclosure 1 - Emergency Plan Marked-up Pages Enclosure 2- Emergency Plan Clean Copy Pages Page 1

LR-N19-0065 LAR S19-05 LAR H19-05 1 .0

SUMMARY

DESCRIPTION PSEG Nuclear, L LC (PSEG) is requesting NRC approval of a proposed revision to the PSEG Nuclear Radiological Emergency Preparedness Plan. The proposed changes would revise certain Emergency Response Organization (ERO) positions in the PSEG Emergency Plan to align with the Alternative Guidance for Licensee Emergency Response Organizations (Alternative Guidance) finalized in a letter from the NRC to the Nuclear Energy Institute (NE I), June 12, 2018 (Reference 6.1). The guidance will be included in Revision 2 of NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" (Reference 6.3)(referred to as NUREG-0654 hereafter) when published. The proposed changes have been reviewed considering the requirements of 10 CFR 50.47, "Emergency plans," paragraph (b), 10 CFR 50 Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities," and other applicable emergency preparedness NRC guidance documents. An evaluation of the proposed changes pursuant to 10 CFR 50.54, "Conditions of licenses," paragraph (q), "Emergency plans," determined that the proposed changes result in a reduction in effectiveness of the Emergency Plan for the affected facilities and, therefore, require prior NRC approval. 2.0 DETAILED DESCRIPTION 2.1 Proposed Changes Enclosures 1 and 2 provide marked-up and clean copy pages of Emergency Plan Section 3. Brief descriptions of the proposed changes are provided below. The justifications for the Functional Area changes are discussed in Section 2.2.

  • Paragraph 2.7 of Section 3, Radiation Protection/Chemistry Organization- Modified reference to the Chemistry organization and Chemistry Technician.
  • Paragraph 9.5 of Section 3, Radiation Protection Onsite o Deleted duty description 5 under E.6 Chemistry Technician (CT) -
                "CT at the unaffected station should support the affected stations CT and if needed, support RP with onsite/offsite monitoring (driver)"

o Modified duty description 14 under E.3, Radiation Protection Technicians (RPT), to add ... "with onsite/offsite monitoring (driver)" o Modified duty description 14 under E.3/E.4, Shift Radiation Protection Technicians E.4 (SRPT)/Onsite Radiation Protection Technician E.3 (ORPT), to add ... "with onsite/offsite monitoring (driver)"

  • Table 3-2, PSEG Nuclear Correlation To Supplement 1 of NUREG-0737, Supplement 1, Table 2 (NUREG-0654, TABLE B-1)- Removed two on-shift positions filled by Chemistry Technicians from the Radiological Accident Assessment and Support of Operational Accident Assessment major functional area and thus reduced the total staffing number by 2.
  • Figure 3-1, On-Shift Staffing Emergency Response Organization- Removed 2 Chemistry Technician positions and associated reference in Note 1.
  • Figure 3-2, Station Response With External Interface- Removed 2 Chemistry Technician positions, one each at Hope Creek and Salem.

Page 2

LR-N 1 9-0065 LAR S 1 9-05 LAR H 1 9-05 2.2 Bases for Proposed Changes The proposed revision removes the Chemistry personnel from the on-shift Emergency Response Organization. The Chemistry/Radiochemistry function listed in Table B- 1 of Revision 1 of NUREG-0654 (Reference 6.2) is no longer needed as the need for immediate reactor coolant sampling has been reduced due to the variety of available plant indications of fuel damage available at Hope Creek and Salem. Early indications of fuel damage can be identified through Containment Radiation Monitors, Core Instrumentation, or Effluent Radiation Monitors, all of which are available in the Salem and Hope Creek Main Control Rooms. The proposed ERO staffing is consistent with the NRC's Alternative Guidance (Reference 6. 1 ).

3.0 TECHNICAL EVALUATION

3. 1 Functional Analysis This analysis evaluates the impact of revising the functional areas and, removing some positions from paragraph 2.7 of Section 3, Table 3-2, Figure 3- 1 and Figure 3-2 of the Emergency Plan. The analysis demonstrates that no degradation or loss of function would occur as a result of the change.

The Chemistry Technician is no longer specified as an on-shift position in the proposed Table 3-2 and in the proposed Figures 3- 1 and 3-2. Current Emergency Plan Section 3, Paragraph 9.5.E.6, describes the five duties of the Chemistry Technician. The first four duties all relate to the sampling of nuclides, and sampling of nuclides is not required to support emergency response decision-making during the initial phases of an accident. This information can be effectively provided by other indications or process parameters, or measurement of radiation levels. The fifth and final Emergency Plan duty of the Chemistry Technician states the unaffected station Chemistry Technician "should" support the affected station Chemistry Technician and if needed, support Radiation Protection with onsite/offsite monitoring (driver). A similar duty is currently assigned in Paragraphs 9.5.E.3 and E.4 to the Radiation Protection Technicians at the unaffected station, and these on-shift personnel could satisfy the final listed duty of the on-shift Chemistry Technician during the initial phase of an accident. The proposed Emergency Plan revision will clarify this support duty for the unaffected station Radiation Protection Technicians. As a result of the above, there is no longer a need for the on-shift Chemistry Technician role in the Emergency Plan. A review of the on-shift staffing analysis under 1 0 CFR 50, Appendix E, Section IV.A.9 was performed to ensure that the Chemistry major task is not required per the Salem or Hope Creek procedures prior to augmentation. The On-shift Staffing Assessment (OSA) indicates that the primary responsibility of the on-shift Chemistry technician is chemistry/radiochemistry sampling to identify fuel damage; however, no chemistry sampling tasks were noted as being time critical in any of the analyzed events. Therefore it is not necessary to have dedicated on-shift staffing for Chemistry support in the Emergency Plan. The proposed ERO staffing is consistent with the draft NUREG-0654, Revision 2 guidance. Page 3

LR-N 1 9-0065 LAR S 1 9-05 LAR H 1 9-05

4.0 REGULATORY EVALUATION

4. 1 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met.

Section 50.47, "Emergency plans," of Title 1 0 of the Code of Federal Regulations ( 1 0 CFR) sets forth the U.S. Nuclear Regulatory Commission's (NRC) Emergency Plan requirements for nuclear power plant facilities. Section 50.47(b) establishes the standards that the onsite and offsite emergency response plans must meet. Planning Standard (2) of this section requires that: On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified. Section IV.A of 1 0 CFR 50, Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities," states in part: The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included: o A description of the normal plant operating organization. o A description of the onsite emergency response organization (ERO) with a detailed discussion of plant staff emergency assignments. o By December 24, 20 1 2, for nuclear power reactor licensees, a detailed analysis demonstrating that on-shift personnel assigned emergency plan implementation functions are not assigned responsibilities that would prevent the timely performance of their assigned functions as specified in the emergency plan. Revision 1 to NUREG-0654/FEMA-RE P- 1 (Reference 6.2) was intended to aid licensees, applicants for licenses, or State and local emergency response organizations in the development of their Radiological Emergency Response Plans. The NRC endorsed this document for use in this effort via Revision 2 to Regulatory Guide (RG) 1 .1 0 1 , "Emergency Planning and Preparedness for Nuclear Power Reactors," dated October 1 98 1 (Reference 6.4). RG 1 . 1 0 1 allows for licensees to submit alternatives to the guidance provided in NUREG-0654/FEMA-RE P- 1 (Reference 6.2) for staff review and approval if necessary. Section 11.8 of NUREG-0654/FEMA-RE P- 1 , Revision 1 , states, in part: On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional Page 4

LR-N 1 9-0065 LAR S 1 9-05 LAR H 1 9-05 areas is maintained at all times, timely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified. Evaluation Criteria 5 of Section 11.8 of NUREG-0654/FEMA-RE P- 1 , Revision 1 , states, in part: Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table 8- 1 entitled, "Minimum On-Site Staffing Requirements for Nuclear Power Plant Emergencies." The minimum on-shift staffing levels shall be as indicated in Table 8- 1 . The licensee must be able to augment on shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table 8- 1 .

  • 1 0 CFR 50.54(q) establishes requirements that all holders of a nuclear power reactor operating license must follow and maintain in effect emergency plans which meet the planning standards in 1 0 CFR 50.47(b) and the requirements in 1 0 CFR 50, Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities."
  • Regulatory Guide 1 .2 1 9, "Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors," (Reference 6.5) provides guidance related to emergency preparedness and specifically to making changes to emergency response plans.
  • NSIR/D PR- ISG-0 1 , " Interim Staff Guidance, Emergency Planning for Nuclear Power Plants," provides guidance for addressing emergency planning requirements for nuclear power plants. This guidance is based on changes to Emergency preparedness regulations 1 0 CFR 50.47 and 1 0 CFR 50 Appendix E, that were published in the Federal Register (FR) on November 23, 20 1 1 (i.e., reference 76FR 72560). The guidance should be used by licensees and applicants for implementing changes to onsite E P programs based on the revised emergency preparedness requirements and by NRC for reviewing the adequacy of the revised onsite emergency preparedness programs.

In addition, PSEG also reviewed the "Alternative Guidance for Licensee Emergency Response Organizations" (Alternative Guidance) finalized in the letter from the NRC to NE I, dated June 1 2, 20 1 8, (Reference 6.1 ) and RIS 20 1 6- 1 0, "License Amendment Requests for Changes to Emergency Response Organization Staffing and Augmentation" (Reference 6.6), in support of this submittal. PSEG has evaluated the proposed changes against the applicable regulatory requirements and guidance criteria and concluded that the Emergency Plan, as revised, will continue to meet the requirements in Appendix E to 1 0 CFR 50 and the planning standards of 1 0 CFR 50.47(b). Page 5

LR-N 1 9-0065 LAR S 1 9-05 LAR H 1 9-05 4.2 Precedent In the three amendments listed below, the NRC approved changes to Emergency Response Organizations, including the removal of the on-shift Chemistry Technician from Emergency Plan staffing, as per the Reference 6. 1 guidance and are therefore applicable to the proposed changes to the PSEG Nuclear Emergency Plan. 4.2. 1 South Texas Project, Units 1 and 2 - Issuance of Amendments re: Emergency Response Organization Time Augmentation and Staffing Changes To the Emergency Plan (CAC NOS. MG0024 AND MG0025; E PI D L-20 1 7-LLA-0265) (ADAMS Accession No. ML18159A212) dated July 1 9, 20 1 8. 4.2.2 Braidwood Station, Units 1 and 2; Byron Station, Unit Nos. 1 and 2; Clinton Power Station, Unit No. 1 ; Dresden Nuclear Power Station, Units 1 , 2, and 3; Lasalle County Station, Units 1 and 2; and Quad Cities Nuclear Power Station, Units 1 and 2 - Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements (E PID L-20 1 8-LLA-0045) (ADAMS Accession No. ML19036A586) dated March 2 1 , 20 1 9. 4.2.3 Limerick Generating Station, Units 1 and 2, and Peach Bottom Atomic Power Station, Units 1 , 2, and 3 - Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements (EP I D L-20 1 8-LLA-0 1 50)(ADAMS Accession No.: ML19078A018), dated May 24, 20 1 9. 4.3 No Significant Hazards Consideration Analysis In accordance with the requirements of 1 0 CFR 50.90, PSEG Nuclear LLC (PSEG) requests approval of an amendment to revise the PSEG Nuclear Emergency Plan. The proposed changes would result in a revision in the staffing for certain Emergency Response Organization positions. PSEG has evaluated the proposed amendment against the standards in 1 0 CFR 50.92 and has determined that the proposed amendment presents no significant hazards. PSEG has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 1 0 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No. The proposed amendment, which eliminates two Chemistry technicians from the Emergency Response Organization minimum staffing, has no effect on normal plant operation or on any accident initiator or precursors and does not impact the function of plant structures, systems, or components. The proposed changes do not alter or prevent the ability of the Emergency Response Organization to perform their intended functions to mitigate the consequences of an accident or event. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. Page 6

LR-N 1 9-0065 LAR S 1 9-05 LAR H 1 9-05

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No. The proposed amendment does not impact any accident analysis. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), a change in the method of plant operation, or new operator actions. The proposed change does not introduce failure modes that could result in a new accident, and the change does not alter assumptions made in the safety analysis. The proposed change revises the on-shift staffing in the PSEG Nuclear Emergency Plan. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed change is associated with the PSEG Emergency Plan staffing and does not impact operation of the plant or its response to transients or accidents. The change does not affect the Technical Specifications. The proposed change does not involve a change in the method of plant operation and no accident analyses will be affected by the proposed change. Safety analysis acceptance criteria are not affected by the proposed change. The revised PSEG Emergency Plan will continue to provide the necessary response staff. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, PSEG concludes that the proposed change presents no significant hazards consideration under the standards set forth in 1 0 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified. 4.4 Conclusions In conclusion, based on the considerations discussed above, ( 1 ) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Page 7

LR-N19-0065 LAR S19-05 LAR H19-05

5.0 ENVIRONMENTAL CONSIDERATION

The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

6.0 REFERENCES

6.1 Letter from NRC to NEI, "Alternative Guidance for Licensee Emergency Response Organizations," June 12, 2018 (ML18022A352). 6.2 NUREG-0654/FE MA-RE P-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Revision 1, U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency, November 1980 (ML040420012) 6.3 Draft NUREG-0654/FEMA-RE P-1, Revision 2, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" (ML14163A605) 6.4 Regulatory Guide (RG) 1.101, "Emergency Planning and Preparedness for Nuclear Power Reactors," Revision 2, dated October 1981 (ML13038A097). 6.5 Regulatory Guide 1.219, "Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors," dated November 2011 (ML102510626). 6.6 NRC Regulatory Issue Summary 2016-10, "License Amendment Requests for Changes to Emergency Response Organization Staffing and Augmentation", dated August 5, 2016 (ML16124A002). Page 8

LR-N 1 9-0065 Enclosure 1 Emergency Plan Marked-Up Pages

the Maintenance Department for normal assignments and supervision but receives on shift direction from the shift maintenance supervisor in coordination with the SM concerning priority repairs to support plant operations.

2. 5 Technical The Technical Engineers with specialties in controls, electrical, mechanical, and core thermal engineering are assigned to the Technical Support Team. The PSEG Nuclear, LLC plant technical support provides primary system engineering support during normal operations.

2.6 Security Organization The on-duty Security Shift Manager and the Security Force are responsible for station security. Security personnel are assigned in accordance with the PSEG Nuclear Security Plan and report to the Manager Security Operations for normal assignments and directions, but receive on-shift direction from the Shift Manager, concerning special access control requirements or accountability.

2. 7 Radiation Protection/Chemistry Organization The Salem and Hope Creek Generating Stations back-shift Radiation Protection/Chemistry Organization consists of one Shift Radiation Protection Technician (SR PT) and one Onshift Radiation Protection Technician (ORPT), who is directed by the SRPT, and one Chemistry Technician.

When Radiation Protection Supervision is not present, the SRPT, ORPT, and any Radiation Protection Technicians (RPTs), who may be on shift, report to the SM. Radiation Protection personnel on the back-shift are normally responsible for conducting routine and special surveys, operating counting room instrumentation, maintaining access control at the Control Points, writing Radiation Work Permits, and providing job coverage as required. The Chemistry Technicians are the members of the Station Chemistry Department who are responsible for performing reactor coolant chemistry sampling and analysis. This position reports to the Chemistry Department for normal assignments and supervision, but receives on-shift direction from the SM concerning sampling required to support station operations. During an Emergency, Chemistry Supervisors and technicians report to the SM, until the TSC is activated. The Chemistry Supervisor(s) and technicians report to the Radiological Assessment Coordinator (RAC), upon activation of the TSC. PSEG NUCLEAR LLC - E P 3.3 Rev. W. 31

Duties:

1) Perform onsite radiation and air sampling surveys.
2) Conduct operational checks on all equipment.
3) Perform dose calculations.
4) Perform access control, and issue dosimetry.
5) Decontaminate personnel and equipment.
6) Provide sampling results to appropriate R PS.
7) Assist in Radiological Work Permits (RWP) preparation.
8) Support Repair corrective action missions as required.
9) Maintain communication with the Control Point.

1 0) Provide communications to onsite and offsite Field Teams (R PT Radio).

11) Perform onsite/offsite radiological monitoring.
12) Issue radiological monitoring equipment.
13) Initiate, perform, and assist in sampling and analysis of samples.
14) If assigned to the unaffected stations, support affected station as needed, i.e. with onsite/offsite monitoring (driver).

E.3/E.4 Shift Radiation Protection Technician E.4 (SRPT)/Onsite Radiation Protection Technician E.3 (OR PT) The SRPT/OR PT will assist and advise SM with respect to radiological conditions prior to TSC activation. Duties:

1) Perform initial dose assessment.
2) Advises SM on radiological matters prior to being relieved by an R PS.
3) Evaluate Radiation Monitoring System (RMS) and provide long term RMS information to all Emergency Response Facilities.
4) Provide CR contamination control/habitability monitoring.

PSEG NUCLEAR LLC - E P 3.23 Rev. 31

5) Support repair and corrective action missions with personnel and equipment (medical, search and rescue, fire fighting, escort, etc.)
6) Assist with count room activities and direct instrument issue activities.
7) Assist in radwaste activities.
8) Coordinate inplant surveys, obtain inplant samples (noble gas/iodine),

and effluent grab samples.

9) Direct access control and dosimetry issue.

1 0) Request dosimetry and whole body count support for inplant personnel.

11) Coordinates decon of personnel and equipment.
12) Assess RMS readings for inplant habitability and protective equipment use.
13) Coordinate, initiate, perform, and assist in sampling and analysis of samples.
14) If assigned to the unaffected stations, support affected station as needed, i.e. with onsite/offsite monitoring (driver).

E. 5 Chemistry Supervisor The Chemistry Supervisor, located at the TSC, coordinates Chemistry's response for sampling and analysis functions. The Chemistry Supervisor reports to the RAC. This is a common position between Hope Creek and Salem Generating Stations and during dual Site events, the Chemistry Supervisor will initially report to the Station that first paged him/her. He/She will upon arrival report to the Station that has the most significant chemistry concern, according to the RAC and/or the EDO's guidance. Duties:

1) Coordinates Chemistry personnel activities.
2) Directs and coordinates high activity samples, main steam sampling, and analysis of samples.
3) Coordinates activation of high activity sampling systems and necessary ventilation systems in those areas.
4) Relays sample analysis data to the RAC and then the RSM once the EOF is activated.

PSEG NUCLEAR LLC - EP 3.24 Rev. W 31

5) Coordinates sample results with the Core Thermal-Hydraulics Engineer and the Technical Support Team Leader.
6) Initiates sample log.
7) Augments Chemistry Staff when necessary.
8) Coordinates with Core Thermal-Hydraulics Engineer in the TSC.

E.6 Chemistry Technician (CT) The CT will assist and advise the Chemistry Supervisor with respect to sampling activities from the Control Point. Duties:

1) Directs and coordinates high activity samples, main steam sampling, and analysis of samples.
2) Disassembles, assembles, and operates the multi-channel analyzer.
3) Establishes backup laboratory facility (Hope Creek Count Room for Salem and Salem for Hope Creek).
4) Coordinates activation of high activity sampling systems and necessary ventilation systems in those areas if the TSC is not activated.
5) CT at the unaffected station should support the affected stations CT and if needed, support RP *.vith onsite/offsite monitoring (driver).

9.6 F. PLANT SYSTEMS ASSESSMENT AND ENGINEERING F.1 Technical Support Supervisor (TSS) The TSS has overall responsibility for tracking and trending plant conditions, identifying plant condition EALs, and providing advice on PARs to the EDO, and when the EOF is activated, the SSM. The TSS is the lead evaluator and decision maker for the Severe Accident team. Duties:

1) The TSS reports to the EDO.
2) The TSS evaluates the potential for an offsite radiological release based upon plant conditions in accordance with EALs. Prior to activation of the EOF, these evaluations are provided to the EDO for action. After activation of the EOF, these evaluations are provided to the SSM for action and the EDO for information.

PSEG NUCLEAR LLC - EP 3.25 Rev . .W. 31

TABLE 3-2 PSEG NUCLEAR CORRELATION TO SUPPLEMENT 1 OF NUREG-0737 TABLE 2 (NUREG-0654, TABLE B-1) (Note 2) (NUREG- On* Capabilities for Shift Additions 90 min 0654, TABLE Major Tasks Position Title or Expertise B-1) (Note 1) Major Functional Area Plant Operations Shift Manager (SM) (SRO) 1 A4 and Assessment of Operational Aspects 1 B2 Control Room Supervisor (CRS) (SRO) Reactor/Plant Operator 2B3 (RO/PO) Nuclear Equipment 2B5 Operator (NEO) Emergency Direction and 1 **A4 Control Shift Manager (SM)(SRO) (Emergency Coordinator Notification/ Notify Licensee, Control Room 2B4 Communication State, Local and Communicator Federal personnel and maintain TSC&EOF 2 F8 & 2 15 (TSC & EOF communication Communicators Communicators) Radiological EOF- Manager Emergency Response 1 A1 (Emergency Response Mgr) Accident Manager (ERM)*** Assessment and Offsite Dose Support of Assessment Shift RP Tech 1 E4 (Note 3) 2E 1 (RACs) Operational (SRPT)/RP Supervisor-Accident Offsite Assessment Offsite Surveys Technician (RPT) (Note 9) 4D4 (Offsite Monitors/Drivers) Onsite (out-of-plant) Technician (RPT) 1 E3 (Note 5) 1 E2A (RPS Offsite) 1 E6 (}!ete 5) In-plant Surveys Technician (RPT) 2 E3 (Note 5) 1 E3 (Callout RPT) Chern/Radio-chemistry Technician (CT) 1 E5 (Chemistry Supv) PSEG NUCLEAR LLC - E P 3.40 Rev . .W 31

TABLE 3-2 (cont.) PSEG NUCLEAR CORRELATION TO SUPPLEMENT 1 OF NUREG-0737 TABLE 2 (NUREG-0654, TABLE B-1) (Note 2) On* Capabilities for Major Functional Shift Additions 90 min Area Major Tasks Position Title or Expertise (Note 1) Site Access Control Security, Fire Security Personnel All per Security Plan Local and State Support and Personnel Fighting, Accountability Communications, Personnel Accountability Total Staffing: 26 20 Notes: F or each u naffected n uclear u n it in operation, maintain at least one Control Room Supervisor, one Reactor/Plant Operator and one Equ ipment Operator. M ay be provided by S h ift person nel assigned other fu nction s . Staffing designated with double asterisk is not cou nted in "Total Staffi ng" values at end of table. Overal l d irections of facility response to be assu m ed by EOF Em ergency Response Manager when all facilities are fu l ly ma nned & activated. Note 1: Thirty (30) - m i n ute responder positions in N U REG - 0737, Table 2, S upplement 1, are addressed in the 

         " On-Shift" staffing col u m n. There is not a 30 - m i n ute callout process.

Note 2: This chart provides a table that correlates the emergency response organization to the position g u idance of Table 2, N U REG-0737, Supplement 1. Staffing response times are as discussed in Section 9 of the E mergency Plan. N ote 3 : W i l l be performed by the S h ift Radiation Protection Techn ician (E4) u ntil relieved by the Radiation Protection Supervisor - Offsite. Note 4: Advisory function will be performed by S hift Tech n ical Advisor (STA) until relieved by Core/Thermal Hydrau lics Engineer. Note 5: Add itional personnel avai lable from the u naffected station to s upport In-plant activities . Note 6: At Hope Creek, the STA can also be assig ned the d uties of the Control Room Supervisor or S h ift Manager i n accordance with techn ical specification provis ions. Note 7: Ind ivi d u als who are radiation worker q u al ified m ay fil l this position . Note 8: An ons h ift N uclear Eq u ipment Operator (Salem) or Rad Waste Operator (Hope Creek) m ay concurrently fil l the Mechanical Mainten ance/Rad Waste Operator position u ntil relieved. Note 9: Offsite surveys may be performed by onsite field monitoring person nel u ntil the offsite field monitorin g team members report t o t h e EOF. PSEG NUCLEAR LLC - EP 3.42 Rev. W 31 

"1J

(/) SALEM m *-------------------- 1 MEDICAL --------------------* I G) SALEM I CENTER I HOPE CREEK I I I I z I I I I c SM I I I I SM NOTES I I 0 I I I I r A4 CR I I A4 CR

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PAGE 1 OF 2 C2 I osc C5E I osc C3 I osc C5D I osc C5B I osc

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LR-N1 9-0065 Enclosure 2 Emergency Plan Clean Copy Pages

the M a i nte n a n ce Department fo r n o rm a l ass ig n ments a n d su pervision b u t rece ives o n s h ift d i rectio n from t h e sh ift mainte n a n ce s u pe rviso r i n coo rd i n ation with the S M co n ce rn i n g prio rity repairs t o s u pport plant operatio n s . 2.5 Tech n ica l The Tech n ica l E n g i n ee rs with specia lties i n controls, e lectrica l , mech a n ica l , a n d co re thermal e n g i n ee ri n g a re assig ned to the Tech n ica l S u pp o rt Tea m . The P S E G N u clear, LLC p lant tech n ica l su pport p rovid es p rimary system e n g i n eering s u p p o rt d u ri n g n o rm a l operatio n s . 2.6 Secu rity O rgan izatio n The o n-d uty Secu rity S h ift M a nager a n d t h e Secu rity Fo rce a re res p o n s i b le fo r statio n secu rity. Secu rity perso n n e l a re ass i g n ed i n acco rd a n ce with t h e P S E G N u clea r Secu rity P l a n a n d report to the M a n a g e r Secu rity Operations fo r n o rm a l assig n m e nts a n d d i rections , but rece ive o n -s h ift d i rection fro m the S h ift M a nager, co n cern i n g special access co ntro l req u i rements o r acco u nta b i l ity. 2.7 Rad iatio n P rotectio n/C hemistry O rgan izatio n The S a l e m and H o p e C reek G e n e rati n g Stations back-sh ift Rad iatio n P rotectio n O rg a n izatio n co nsists o f o n e S h ift Rad iation P rotection Tech n icia n ( S R PT) a n d o n e O n s h ift Rad iation P rotectio n Tech n ician (O R PT) , who i s d i rected b y the S R PT . When Rad iation P rotection S u pe rvision i s n ot p rese nt, t h e S R PT, O R PT, a n d a ny Rad iation P rotection Tech n icians ( R PTs) , who may be o n s h ift, re p o rt to the S M . Rad iation P rotection perso n n e l o n the back-s h ift a re n o rm a l ly res p o n s i b le fo r co n d u cting routine and specia l s u rveys , operati n g co u nti n g roo m i nstru m entatio n , main ta i n i n g access co ntro l at the Co ntro l P o i nts , writing Rad iation Wo rk P e rm its , a n d p rovi d i n g job cove rage as req u i red . The C h e m istry Tech n icians a re the members of the Station C h e m istry Department who a re responsible for perfo rm i n g reacto r coolant chemistry sa m p l i n g and a n a lysi s . Th is position repo rts t o t h e C he m istry Department fo r n o rmal assig n me n ts a n d s u pe rvision , b u t rece ives o n -s h ift d i rectio n from t h e S M co n ce rn i n g s a m p l i n g req u i red to s u p po rt station ope rati o n s . D u ri n g a n Emerg e n cy, C h e m istry S u p e rvisors a n d tech n icians rep o rt t o the S M , u ntil the TSC is activated . The C h e m istry S u pe rviso r(s) and tech n icia n s report to the Rad io log ical Assessment C o o rd i n ato r (RAG ) , u p o n activation of the TS C . P S E G N U C L EAR LLC - E P 3.3 Rev. 31

D uties :

1) Perfo rm o n s ite rad iation a n d a i r samp l i n g su rveys .
2) C o n d u ct o p e rati o n a l checks o n all eq u ipment.
3) Perfo rm d ose ca lcu latio n s .
4) Perfo rm access contro l , a n d iss u e dosimetry .
5) Deco nta m i n ate perso n n e l a n d eq u ip me nt .
6) P rovid e sam p l i n g res u lts t o a p p ro priate R P S .
7) Ass ist in Rad io log ica l Wo rk P e rm its (RWP) p re p a rati o n .
8) S u p p o rt Rep a i r co rrective action missions as req u i red .
9) M a i nta i n com m u n icatio n with the Contro l P o i nt.

1 0) P rovide com m u n ications to o n s ite a n d offsite Field Teams (RPT Rad io). 1 1) Perfo rm ons ite/offs ite rad iolog ica l m o n ito ri n g . 1 2) Issue rad iolog ica l m o n ito ri n g eq u ip ment. 1 3) I n itiate , perfo rm , a n d assist i n sa m p l i n g a n d a n a lysis of samples . 1 4) If assig ned to the u n affected stati o n s , s u p p o rt affected statio n as needed , i . e . with o n site/offsite m o n ito ri n g (d rive r) . E . 3/E.4 S h ift Rad iati o n P rotectio n Tech n ician E . 4 (S R PT)/O nsite Rad iation P rotection Tech n ician E.3 (OR PT) The S R PT/O R PT will assist a n d advise SM with respect to rad io log ica l co n d itions p r i o r t o T S C activatio n . D uties :

1) Pe rfo rm i n iti a l d ose assessment.
2) Advises S M o n rad iolog ica l matte rs p rior to be i n g rel ieved by an R P S .
3) Eva l u ate Rad i ation M o n ito ri n g System ( R M S ) and p rovide long te rm RMS i n fo rmati o n to a l l E m e rg e n cy Response Faci l ities .
4) P rovide C R co nta m i n ation co ntro l/h a b ita b i l ity mon itoring .

P S E G N U C L EAR LLC - E P 3 . 23 Rev. 3 1

5) S u p p o rt repair and co rrective actio n miss ions with p e rso n n e l a n d eq u i pment (med ica l , search a n d rescue , fi re fig hting , esco rt, etc . )
6) Ass ist with co u nt roo m activities a n d d i re ct i n stru m e n t iss u e activities .
7) Ass ist in radwaste activities .
8) C o o rd i n ate i n plant su rveys , o bta i n i n p lant samp les ( n o b l e g as/iod i n e) ,

a n d effl u e nt g ra b samples.

9) D i rect access co ntrol and d os i metry iss u e .

1 0) Req u est dosimetry a n d whole body cou nt s u pport fo r i n p lant pe rso n n e l . 1 1) C o o rd i n ates d eco n of perso n ne l and eq u i pment. 1 2) Assess R M S read ings fo r i n p lant h a b ita b i l ity a n d p rotective e q u i p ment use . 1 3) C o o rd i n ate , i n itiate , perfo rm , a n d assist i n s a m p l i n g a n d a n a lysis of samples. 1 4) If ass i g n ed to the u n affected stati o n s , s u p p o rt affected station a s needed , i . e . with o n s ite/offsite m o n ito ri n g (d rive r) . E.5 C h e m istry S u pe rviso r The C h e m istry S u pe rvisor, located at the TS C , coo rd i n ates C h e m istry's response fo r sampling a n d a n a lysis fu n cti o n s . T h e C h e m istry S u pervisor reports to the RAG . T h i s is a common positio n between H o pe C reek a n d Salem G e n e rati ng Statio ns a n d d u ri n g d u a l S ite events , t h e C h e m istry S u p e rvis o r wi l l i n iti a l ly report to the Station that fi rst paged h im/her. H e/S h e w i l l u p o n a rriva l rep o rt t o t h e Statio n that h as t h e most sig n ifica nt chem istry co n ce rn , acco rd i ng to the RAG a n d/o r the E DO's g u id a n ce . D uties :

1) C o o rd i n ates C h e m istry perso n n e l activities .
2) D i rects and coo rd i n ates high activity samples, main steam samp l i n g ,

a n d a n a lysis o f samples.

3) C o o rd i n ates activation of high activity sa m p l i n g systems a n d necessary ve ntilati o n systems i n those a reas .
4) Relays sample a n a lysis d ata to the RAG and then the RSM o n ce the E O F is activated .

P S E G N U C L EAR LLC - E P 3 . 24 Rev. 3 1

5) Coord i n ates s a m p le resu lts with the Core Thermal-Hyd ra u l ics E n g i n eer a n d the Tech n ica l S u pport Tea m Leader.

6) I n itiates sa m p le log .
7) Augme nts C h e m istry Staff whe n necessary.
8) C o o rd i n ates with C o re Thermal-Hyd ra u l ics E n g i neer in the TSC .

E.6 C h e m istry Tech n ician (CT) T h e C T w i l l assist a n d advise t h e C h e m istry S u perviso r with respect to sampling activities from the Contro l P o i nt. D uties :

1) D i rects a n d coo rd i n ates h ig h activity samples, main steam sam p l i n g ,

a n d a n a lys is of samples.

2) D isassembles, assembles, a n d ope rates the m u lti-ch a n n e l a n a lyze r.
3) Esta b l ishes backu p laborato ry facility ( H o p e C reek C o u nt Room fo r Salem and Salem fo r H o pe C reek) .
4) Coord i n ates activation of h i g h activity sampling systems a n d n e cessary ve ntilation syste ms i n those a reas if the TS C is n ot activated .

9.6 F. P LANT SYST E M S ASS E S S M E NT A N D E N G I N E E R I N G F.1 Tech n ica l S u pport S u pe rvisor (TSS) The TSS h as ove ra l l respo n s i b i l ity fo r tracking and tre n d i n g p lant co n d iti o n s , ide ntifying p lant con d ition EALs , a n d p rovid i n g advice o n PARs t o t h e E D O , a n d when t h e E O F i s activated , the SSM . T h e T S S i s the lead eva l uato r a n d d ecision m a ke r fo r the Seve re Accid ent tea m . D uties :

1) The TSS re ports to the E D O .
2) The TSS eva l u ates the p otential for a n offs ite rad iolog ica l release based u po n plant con d itions i n accord a nce with EALs . P rior to activation of the E O F , these eva l u ations a re provided to the E D O for acti o n . Afte r activatio n of the E O F , these eva l u atio n s a re p rovid ed to the S S M fo r action a n d the E D O fo r info rmatio n .
3) The TSS p rovides advice to the E D O o n p ri orities fo r p lant re pa i r a n d co rrective acti o n s .

P S E G N U C L EAR LLC - E P 3 .2 5 Rev. 3 1

TAB LE 3-2 PSEG N U C LEAR CORRELATION TO S U PP L E ME NT 1 O F N U REG-0737 TABLE 2 ( N U REG-0654, TABLE B-1 ) (Note 2) (NUREG- On* Capabilities for Shift Additions 90 min 0654, TABLE Maj or Tasks Position Title or Expertise B-1) (Note 1)

  • Maj or Functional Area Plant Operations Shift Manager (SM) (SRO) I A4 and Assessment of Operational Aspects 1 B2 Control Room Supervisor (CRS) (SRO)

Reactor/Plant Operator 2 B3 (RO/PO) Nuclear Equipment 2 B5 Operator (NEO) Emergency Direction and 1 * *A4 Control Shift Manager (SM)(SRO) (Emergency Coordinator Notification/ Notify Licensee, Control Room 2 B4 Communication State, Local and Communicator Federal personnel and maintain TSC&EOF 2 F8 &2 15 (TSC & EOF communication Communicators Communicators) Radiological EOF- Manager Emergency Response 1 A 1 (Emergency Response Mgr) Accident Manager (ERM)* *

  • Assessment and Offsite Dose Support of Assessment Shift RP Tech 1 E4 (Note 3) 2E 1 (RACs)

Operational (SRPT)/RP Supervisor-Accident Offsite Assessment Offsite Surveys Technician (RPT) (Note 9) 4D4 (Offsite Monitors/Drivers) Onsite (out-of-plant) Technician (RPT) 1 E3 (Note 5) 1 E2A (RPS Offsite) In-plant Surveys Technician (RPT) 2 E3 (Note 5) 1 E3 (Callout RPT) Chem/Radio-chemistry Technician (CT) 1 E5 (Chemistry Supv) PSEG N U C L EAR LLC - E P 3 .40 Rev. 3 1

TABLE 3-2 (cont.) PSEG N U C LEAR CORRE LAT I O N TO S U PPLEMENT 1 OF N U RE G -0737 TABLE 2 ( N U REG-0654, TAB LE B-1 ) (Note 2) On* Capabilities for Major Functional Shift Additions 90 min Area Major Tasks Position Title or Expertise (Note 1) Site Access Control Security, Fire Security Personnel All per S ecurity Plan Local and State S upport and Personnel Fighting, Accountability Communications, Personnel Accountability Total Staffing : 26 20 Notes: For each u naffected n u clear u n it in operation, maintain at least one Control Room S u pervisor, one Reactor/Plant Operator a n d one Equipm ent Operator. M ay be provided by S h ift person n el assigned other fu nctions . Staffin g designated with double asterisk is not cou nted in "Total Staffi ng" values at end of tab le. Overa l l d i rections of facil ity response to be ass u m ed by EOF Emergency Response Manager when all facilities a re fu l ly m a n ned & activated. N ote 1 : Thirty (30) - m i n ute responder positions in N U REG - 0737, Table 2, S u pplement 1 , a re addressed i n the "On-Shift" staffi ng col u m n . There is not a 30 - m i n ute callout p roces s . N ote 2 : This c h a rt p rovides a table that correlates t h e emergency response o rg a n ization t o the position g u idance of Tab le 2, N U REG-0737, S upplement 1. Staffi ng response times are as d iscussed i n Section 9 of the Emergency P l a n . N ote 3 : Will be perfo rmed b y the S h ift Rad iation P rotection Technician (E4) u ntil relieved b y the Radiation P rotection S upervisor - Offsite. N ote 4: Advisory fu nction wil l be performed by S h ift Tech nical Advisor (STA) u ntil relieved by Core/Therm a l Hyd rau l ics Engineer. N ote 5: Add itional personnel avai lable from the u naffected station to s upport I n-plant activities . N ote 6: At Hope C reek, the STA can also be assigned the d uties of the Control Room S u pervisor o r Shift Manager in accordance with tec h n ical s pecification p rovis ions . N ote 7: I n d ivid uals who a re rad iation worker qu al ified m ay fil l this pos itio n . N ote 8 : An onshift N uclear Eq u ip m ent Operator (Salem ) or Rad Waste Operator ( H o p e Creek) m ay concu rrently fi l l the Mechan ical Maintenance/Rad Waste Operator position u ntil rel ieved . N ote 9: Offsite su rveys m ay be perform ed by onsite field m onitori ng personnel u ntil the offsite field monitoring team mem bers report to the E OF . PSEG N U C LEAR LLC - E P 3 .42 Rev. 3 1

"U (/) SALEM m t* * * * * - - - * * * * * * * * - * *

  • MEDICAL - - - - - - - - - - - - - - - - - - - -*

SALEM I CENTER I HOPE CREEK G) I I I I I I z I I I I c SM I I I I SM NOTE 6 () I I I I r I I A4 CR I I A4 CR m _________ I I )> PUBLIC I NFO

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r r G14 I N/A () I m MEDI "U NOTE 1 l NOTE 1 1 I I osc SECURITY SECURITY osc NOTE2 NOTE 3 SRPT SRPT NOTE 3 NOTE2 COORD, FORCE FORCE COORD. C1 osc AS PER S/P E4 I CRICP E4 I CR/CP AS PER SIP C1 I esc I I I 5 I I I 2 I I ON.SHIFT STOCK SHIFT ON-SHIFT SHIFT HANDLER RADWASTE FIRE FIRE RADWASTE MAINT. EO STOCK ORPT ORPT EO MAl NT. OPERATOR DEPT. DEPT. OPERATOR SUPV. HANDLER SUPV. C7 osc C4C I osc C5A I osc B5 osc C6 osc C7 osc E3 I CP E3 I CP C6 I osc Bs 1 osc C5A I osc C4C osc I NOTE 7 NOTE S NOTE 4 NOTE 4 NOTE S SCHEDULED SHIFT I I SCHEDULED SHIFT I&C TECH ELEC. NOTE S I I I&C TECH ELEC. osc I osc CM1 CM2 NSTA/CRS C2 I osc C3 osc r*r-C2 C3 NSTA/CRS NSTA/CRS CM1 CM2 UNIT 1 UNIT2 *r* I NOTES 5 , 6 I_ J I I B4 I CR I B4 CR B1 / B2 CR i_ CR 1 1 I I I B 1 / B2 B 1 / B2 CR2 B4 I CR I I B4 CR I I I I 2 I I 2 2 .. . . . . .,. . . . . . . ______,. ____________, ____ I I I I RO/PO RO/PO RO/PO I I I I I UNIT 1 UNIT2 I I I NJ B3 I CR B3 I CR 1 B3 I CR2 I I NRC NRC STATE I ENS / HQ REGION 1 I POLICE I NOTE 1 RP TECHS FROM UNAFFECTED STATION WILL BE AVAILABLE TO RESPOND TO AFFECTED UNIT.

L-----'

I CODE KEY I NOTE 2 INITIAL OSC COORDINATOR WILL BE THE SHIFT MAINTENANCE SUPERVISOR OR THE 1 I I OPS SUPERVISOR UNTIL RELIEVED BY THE DUTY RESPONDER OSCC. I I I IF MULTIPLE SUPPORT POSITIONS, NUMBER RESPONDER NOTE 3 SECURITY FORCE AS SPECIFIED IN SECURITY PLAN (S/P). IND ICATES TOTAL DEL PLUME OTHER POSITIONS STATE EPZ NOTE 4 FIRE DEPARTMENT AS SPECIFIED IN TECHNICAL SPECIFICATIONS. CONTACTS POLICE COUNTIES ERO POSITION NOTE 5 NSTA STAFFING PER TECHNICAL SPECIFICATIONS. NOTE 6 NSTA/SM OR NSTA/CRS CAN BE THE SAME INDIVIDUAL AT HOPE CREEK AND AN ERO POSITION CODE LOCATION ADDITIONAL SRO WILL FILL THE ROLE OF THE 'INCIDENT ASSESSOR". P S E G N U C LEAR LLC SEE SECTION 9.0 O N S H I FT STAF F I N G COMMAND AND CONTROL FLOW NOTE 7 AT SALEM, THE RADWASTE OPERATOR POSITION IS FILLED BY A s EO. EME RGENCY RESPONSE COMMUNICATION AND COORDINATION FLOW - - - - - - - - NOTE 8 EO ASSIGNED TO OSC CAN NOT CONCURRENTLY BE ASSIGNED A CONTROL ROOM O R GAN IZAT I O N COMMUNICATOR. ( F I G U R E 3-1 )

iJ SALEM (/) C O DE KEY m EMERGENCY G) DUlY IF MULTIPLE OFFICER POSITIONS, NUMBER ------ #

  • g6 ER z INDICATES TOTAL c

A3 TSC POSITIONS () ----- ---- ERO POSITION / I r m  : I c-G 

                                                                                                                                                        -,                                  ERO POSITION CODE                                    LOCATION

)> SALEM PUBLIC SEE SECTION 9.0

0 INFORMATION MEDICAL MANAGER COMMAND AND CONTROL FLOW CENTER r

r G1 4 I N/A COMMUNICATION AND COORDINATION FLOW ---- - () - - I I I m ADMIN SECURilY SECURilY TECHNICAL iJ SUPPORT SHIFT SHIFT SUPPORT EPA RAC SUPERVISOR SUPERVISOR r- MANAGER SUPERVISOR J3 TSC 11 I TSC 2 1 I SEC OPS F1 TSC F7 I TSC E1 TSC ADVISOR 3 lliQII;. TECHNICAL ADMIN FBB I TSC SUPPORT TSC TSC CHEMISTRY SECURilY PER SECURilY PLAN (SP). ORPT TEAM LEADER COMM 1 COMM2 SUPERVISOR 1- -, - J4 TSC F2 TSC I I I I FB TSC I FB TSC E5 l TSC E3 CP I l I SM ELECTRICAL MECHANICAL I CHEMISTRY RAD PRO ENGINEER c- - ENGINEER NRC I NRC TECH TECH 1- -, - I ENS / HQ REGION 1 A4 I CR F3 TSC F4 I TSC I EB I CP E3 I CP I CORE I CONTROLS THERMAL osc NSTA/CRS NSTA/CRS ENGINEER HYDRAULICS I RAD PRO c-'-- 1- -{ - NJ STATE DEL STATE TECH COORDINATOR UNIT 1 UNIT2 ENGINEER POLICE POLICE F5 I TSC FSA I TSC C1 osc 8 1 / 82 1 CR 1 8 1 / 82 1 CR2 I E3 I CP I 2 2 I osc ROIPO RO/PO I RAD PRO r---- PLUME EPZ OTHER SUPERVISOR 1- _j - CLERK UNIT 1 UNIT2 COUNTIES CONTACTS OFFFSITE C10 I osc 83 I CR 1 83 I CR2 E2 L TSC I I I RAD PRO 5 SUPPORT SHIFT RAD PRO ON-SHIFT TECH OPS FIRE RADIO MAINTENANCE MAINTENANCE SUPERVISOR PLANNER STOCK SUPERVISOR DEPARTMENT SUPPERVISOR SUPERVISOR EXP CONTROL HANDLER E3 I TSC C4A osc C6 I osc C48 I osc C4C L osc E2 I osc CB J OSC C7 I osc L_, I I 5 2 RADWASTE RAD PRO RAD PRO EO CM1 CM2 SRPT OPERATOR TECH TECH C5A osc 85 1 osc E3 OSC/CP E3 OSC/CP 84 I CR 84 I CR E4 I CR I I I I

0 . STATION RESPONSE WITH EXTERNAL INTERFACE CD (FIGURE 3-2)
< I&C TECH I&C TECH ELEC TECH ELEC TECH MECH TECH PAGE 1 OF 2 w

..... C2 I osc C5E I osc C3 I osc C5D I osc C58 I osc

"'U H O PE CREEK (f) CODE KEY m EMERGENCY G) DUTY IF MULTIPLE OFFICER POSITIONS, NUMBER ------- #

  • ER z INDICATES TOTAL POSITIONS c A3 TSC 0 ERO POSITION / I r I m I c-G
                                                                                                             - - - - - ----                                                 ERO POSITION CODE                                        LOCATION

)> PUBLIC SEE SECTION 9.0 SALEM INFORMATION

u MEDICAL MANAGER COMMAND AND CONTROL FLOW CENTER r COMMUNICATION AND COORDINATION FLOW r G14 I NIA 0 - - - - - - -

I I I I m ADMIN SECURITY SECURITY TECHNICAL "'U SUPPORT SHIFT SHIFT SUPPORT EPA RAC SUPERVISOR SUPERVISOR r- MANAGER SUPERVISOR J3 I TSC 11 I TSC 12 I SEC OPS F1 I TSC F7 I TSC E1 TSC ADVISOR 3 NOTE TECHNICAL ADMIN SECURITY PER SECURITY PLAN (SP). FBB I TSC SUPPORT TSC TSC CHEMISTRY RAD PRO SUPERVISOR TEAM LEADER COMM 1 COMM 2 SUPERVISOR OFFFSITE J4 I TSC F2 TSC I FB I TSC 

                                                                                                                                                                   - ,I -     F8   I   TSC        E5   I  TSC                  E2   I  TSC I                               I SM ELECTRICAL               MECHANICAL                           I                                                        RAD PRO ENGINEER       -

1- ENGINEER NRC I NRC CHEMISTRY TECH TECH RADIO ENS I HQ REGION 1 A4 CR F3 I TSC F4 I TSC I 

                                                                                                                                                                   - ,I -                         E6   I    CP                 E3   I   TSC CORE                             I CONTROLS                  THERMAL osc                                                               ENGINEER       -   '--  HYDRAULICS I

NSTAICRS NJ STATE DEL STATE COORDINATOR ENGINEER POLICE POLICE F5 I TSC F6A I TSC C1 osc 811 82 CR 

                                                                                                                                                                   -- I I

2 I osc I ROIPO CLERK - PLUME EPZ _ _j _ OTHER SRPT COUNTIES CONTACTS C10 osc 83 CR E4 I CPICR I I I J 5 SUPPORT SHIFT RAD PRO ON-SHIFT ORPT OPS FIRE MAINTENANCE MAINTENANCE SUPERVISOR PLANNER STOCK SUPERVISOR DEPARTMENT SUPPERVISOR SUPERVISOR EXP CONTROL HANDLER E3 CP C4A I osc C6 osc C48 osc C4C osc E2 osc C8 I osc C7 1 osc L___, 2 3 RAD PRO RAD PRO 2 TECH TECH COMM-ROIPO EO CM1 CM2 OPS ADVISOR E3 I CP E3 I CP C5A I osc 85 osc 84 CR 84 I CR 84A I CR STATION RESP O N SE WITH EXTERNAL I N TER FACE I&C TECH I&C TECH ELEC TECH ELEC TECH MECH TECH (FIGURE 3-2) C2 osc C5E osc C3 osc C5D osc C58 I osc PAGE 2 OF 2}}

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