RA-20-0008, Submittal of 10 CFR 50.54(q) Screening Evaluation Form and Effectiveness Evaluation Form for AD-EP-HNP-0106, Revision 2

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Submittal of 10 CFR 50.54(q) Screening Evaluation Form and Effectiveness Evaluation Form for AD-EP-HNP-0106, Revision 2
ML20009E557
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/09/2020
From: Riley K
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0008
Download: ML20009E557 (14)
v • d • e


Text

DUKE Kevin P. Riley Support Services Manager ENERGY Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 10 CFR 50.4(b)(5)(ii) 10 CFR 50.54(q)(5)

January 9, 2020 Serial: RA-20-0008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63

Subject:

10 CFR 50.54(q) Evaluation Ladies and Gentlemen:

In accordance with 10 CFR 50.4(b)(5)(ii) and 10 CFR 50.54(q)(5), Duke Energy Progress, LLC, is submitting the 10 CFR 50.54(q) Screening Evaluation Form and the 10 CFR 50.54(q)

Effectiveness Evaluation Form for a revision to a Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Emergency Plan implementing procedure. AD-EP-HNP-0106, "HNP Site Specific OSC

[Operations Support Center] Support," Revision 2, was issued on December 19, 2019.

This submittal contains no regulatory commitments. Please refer any questions regarding this submittal to Sarah McDaniel at (984) 229-2002.

Sincerely, k-P Kevin P. Riley

Enclosure:

10 CFR 50.54(q) Screening Evaluation Form and 10 CFR 50.54(q) Effectiveness Evaluation Form for AD-EP-HNP-0106, Revision 2 cc: J. Zeiler, NRC Senior Resident Inspector, HNP T. Hood, NRC Project Manager, HNP NRC Regional Administrator, Region II

Document Control Desk Serial: RA-20-0008 Enclosure ENCLOSURE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NUMBER NPF-63 10 CFR 50.54(Q) SCREENING EVALUATION FORM AND 10 CFR 50.54(Q) EFFECTIVENESS EVALUATION FORM FOR AD-EP-HNP-0106, REVISION 2 (12 PAGES PLUS COVER)

EMERGENCY PLAN CHANGE SCREENING AD-EP-ALL-0602 AND EFFECTIVENESS EVALUATIONS 10 Rev. 6 CFR 50.54(Q)

ATTACHMENT 4 Page 1 of 5

<< 10 CFR 50.54(q) Screening Evaluation Form >>

Screening and Evaluation Number Applicable Sites BNP EREG #: 2307755 CNS CR3 HNP MNS 5AD #: 2307752 ONS RNP GO Document and Revision AD-EP-HNP-0106 Rev 2 Part I. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the emergency plan or affect the implementation of the emergency plan):

  1. E-Plan or Current (Existing) Text Proposed (Change) Text Procedure Section Reference 1 5.2.3 In Part (RM-11 or DICSP) (DICSP)

Step 2 Deleted RM-11 Part II. Activity Previously Reviewed? Yes No Is this activity Fully bounded by an NRC approved 10 CFR 50.90 submittal or 10 CFR 50.54(q) Continue to Alert and Notification System Design Report? Effectiveness Attachment 4, Evaluation is not 10 CFR If yes, identify bounding source document number or approval reference and required. Enter 50.54(q) ensure the basis for concluding the source document fully bounds the proposed justification Screening change is documented below: below and Evaluation complete Form, Part III Justification: Attachment 4, Part V.

Bounding document attached (optional)

Part III. Editorial Change No or Yes Partially

EMERGENCY PLAN CHANGE SCREENING AD-EP-ALL-0602 AND EFFECTIVENESS EVALUATIONS 10 Rev. 6 CFR 50.54(Q)

ATTACHMENT 4 Page 2 of 5

<< 10 CFR 50.54(q) Screening Evaluation Form >>

Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification: required. Enter address non justification and editorial complete changes Attachment 4, Part V.

Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria)

Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II? If answer is yes, then check box.

1 10 CFR 50.47(b)(1) Assignment of Responsibility (Organization Control) 1a Responsibility for emergency response is assigned.

1b The response organization has the staff to respond and to augment staff on a continuing basis (24-7 staffing) in accordance with the emergency plan.

2 10 CFR 50.47(b)(2) Onsite Emergency Organization 2a Process ensures that on shift emergency response responsibilities are staffed and assigned 2b The process for timely augmentation of on shift staff is established and maintained.

3 10 CFR 50.47(b)(3) Emergency Response Support and Resources 3a Arrangements for requesting and using off site assistance have been made.

3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. (NA for CR3) 4 10 CFR 50.47(b)(4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. (Requires final approval of Screen and Evaluation by EP CFAM.)

5 10 CFR 50.47(b)(5) Notification Methods and Procedures 5a Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes (60 minutes for CR3) after declaration of an emergency and providing follow-up notification.

5b Administrative and physical means have been established for alerting and providing prompt instructions to the public within the plume exposure pathway. (NA for CR3) 5c The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)

EMERGENCY PLAN CHANGE SCREENING AD-EP-ALL-0602 AND EFFECTIVENESS EVALUATIONS 10 Rev. 6 CFR 50.54(Q)

ATTACHMENT 4 Page 3 of 5

<< 10 CFR 50.54(q) Screening Evaluation Form >>

Part IV. Emergency Planning Element and Function Screen (cont.)

6 10 CFR 50.47(b)(6) Emergency Communications 6a Systems are established for prompt communication among principal emergency response organizations.

6b Systems are established for prompt communication to emergency response personnel.

7 10 CFR 50.47(b)(7) Public Education and Information 7a Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ). (NA for CR3) 7b Coordinated dissemination of public information during emergencies is established.

8 10 CFR 50.47(b)(8) Emergency Facilities and Equipment 8a Adequate facilities are maintained to support emergency response.

8b Adequate equipment is maintained to support emergency response.

9 10 CFR 50.47(b)(9) Accident Assessment 9a Methods, systems, and equipment for assessment of radioactive releases are in use.

10 10 CFR 50.47(b) (10) Protective Response 10a A range of public PARs is available for implementation during emergencies. (NA for CR3) 10b Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3) 10c A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

10d KI is available for implementation as a protective action recommendation in those jurisdictions that chose to provide KI to the public.

11 10 CFR 50.47(b) (11) Radiological Exposure Control 11a The resources for controlling radiological exposures for emergency workers are established.

12 10 CFR 50.47(b) (12) Medical and Public Health Support 12a Arrangements are made for medical services for contaminated, injured individuals.

13 10 CFR 50.47(b) (13) Recovery Planning and Post-Accident Operations 13a Plans for recovery and reentry are developed.

14 10 CFR 50.47(b) (14) Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) is established.

14b Drills, exercises, and training evolutions that provide performance opportunities to develop, maintain, and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.

14c Identified weaknesses are corrected.

EMERGENCY PLAN CHANGE SCREENING AD-EP-ALL-0602 AND EFFECTIVENESS EVALUATIONS 10 Rev. 6 CFR 50.54(Q)

ATTACHMENT 4 Page 4 of 5

<< 10 CFR 50.54(q) Screening Evaluation Form >>

Part IV. Emergency Planning Element and Function Screen (cont.)

15 10 CFR 50.47(b) (15) Emergency Response Training 15a Training is provided to emergency responders.

16 10 CFR 50.47(b) (16) Emergency Plan Maintenance 16a Responsibility for emergency plan development and review is established.

16b Planners responsible for emergency plan development and maintenance are properly trained.

PART IV. Conclusion If no Part IV criteria are checked, then provide Justification and complete Part V below.

Justification:

If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete , 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)

Effectiveness Evaluation. Program Element 4a requires final approval of Screen and Evaluation by EP CFAM.

Part V. Signatures:

EP CFAM Final Approval is required for changes affecting Program Element 4a. If CFAM approval is NOT required, then mark the EP CFAM signature block as not applicable (N/A) to indicate that signature is not required.

Preparer Name (Print): Jamey Sharlow Preparer Signature: CAS Date: CAS Reviewer Name (Print): CAS Reviewer Signature: CAS Date: CAS Approver (Manager, Nuclear Support Services) Approver Signature: CAS Date: CAS Name (Print): CAS Approver (EP CFAM, as required) Name (Print) Approver Signature: N/A Date:

If the proposed activity is a change to the E-Plan, then initiate PRRs.

If the proposed activity is a change to the E-Plan, then create two EREG General assignments If required by Section 5.6, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

EMERGENCY PLAN CHANGE SCREENING AD-EP-ALL-0602 AND EFFECTIVENESS EVALUATIONS 10 Rev. 6 CFR 50.54(Q)

ATTACHMENT 4 Page 5 of 5

<< 10 CFR 50.54(q) Screening Evaluation Form >>

QA RECORD

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 1 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

Screening and Evaluation Number Applicable Sites BNP EREG #: 2307755 CNS CR3 HNP MNS 5AD #: 2307752 ONS RNP GO Document and Revision AD-EP-HNP-0106 Rev. 2 Part I. Description of Proposed Change:

  1. E-Plan or Current (Existing) Text Proposed (Change) Text Procedure Section Reference 1 5.2.3 In Part (RM-11 or DICSP) (DICSP)

Step 2 Deleted RM-11 , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

PLP-201, Emergency Plan revision 3 states the following:

3.9.3 Radiological Monitoring The Radiation Monitoring System (RMS) is a plant-wide radiation information gathering and control system encompassing the process and effluent monitors and the area and airborne monitors. Process radiological monitors are provided for:

  • Component Cooling Water System
  • Auxiliary Steam Condensate Tank Liquid
  • Auxiliary Steam Condensate Waste Processing Systems
  • Waste Processing Building Cooling Water System
  • Gas Decay Tanks Effluent radiological monitors are provided for:

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 2 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

  • Fuel Handling Building Normal and Emergency Exhausts
  • Reactor Auxiliary Building Normal and Emergency Exhausts
  • Plant Vent Stack
  • Turbine Building Drains
  • Tank Area Drain Transfer Pumps
  • Condenser Vacuum Pump Effluent Treatment System
  • Treated Laundry and Hot Shower Tank Pumps
  • Secondary Waste Sample Tank
  • Waste Processing Building Exhaust System
  • Containment Pre-Entry Purge System

3.10.3 Radiological Monitoring The Radiation Monitoring System (RMS) is a plant-wide radiation information gathering and control system encompassing the process and effluent monitors and the area and airborne monitors. Radiological monitors are provided for plant systems as described in the FSAR Sections 11.5 and 12.3.4 Effluent radiological monitors are provided for:

  • Plant Vent Stacks
  • Turbine Building Drains
  • Tank Area Drain Transfer Pumps
  • Treated Laundry and Hot Shower Tank Pumps
  • Secondary Waste Sample Tank
  • Main Steam Lines Typical portable radiation monitors and laboratory equipment are described in Section 12.5 of the FSAR.

The locations of the normal off-site and on-site environmental monitoring stations and the location of the TLD monitoring stations are described in the Off-Site Dose Calculation Manual. Additional predetermined emergency off-site monitoring locations are contained in environmental monitoring procedures.

The Radiation Monitoring System, (RMS) provides the necessary activity or radiation levels required for determining source terms in dose projection procedures. The RMS is data linked to the ERFIS and radiation monitoring channel values are available in the TSC and EOF via ERFIS. The isotopic mix is based upon the mix discussed in NUREG-1741. Grab samples and on-site or off-site monitoring samples can then be analyzed to determine the true isotopic mix and the results used in the computerized dose projection software.

The differences in approved revisions and the current revisions of the Emergency Plans have been reviewed, and they have been determined to meet the regulatory requirements required during the course of revisions.

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 3 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

Applicable 10 CFR 50.47(b) requirements for this change:

(8) Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

(9) Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency are in use.

Applicable 10 CFR 50 Appendix E requirements for this change:

IV. B. Assessment Actions

1. The means to be used for determining the magnitude of, and for continually assessing the impact of, the release of radioactive materials shall be described.

IV.E. Emergency Facilities and Equipment

2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment.

This change does not modify the functional capabilities of any critical plant radiation monitor, nor does it modify any functional aspect of the safety related portion of the Radiation Monitoring System (RMS). This completes the migration of the legacy system hardware to a Distributed Instrumentation & Controls System Platform (DICSP) with a fiber optic network infrastructure. The use of a new, enhanced graphics package for the RMS application on the DICSP serves as a common Human Machine Interface (HMI) to help reduce the operator burden in the rapid assimilation of plant radiological data in both normal and off-normal plant conditions. The migration of critical plant radiation monitors to the DICSP from the legacy RMS computing platform significantly improves the quality, reliability and availability of radiation monitoring system information. This change will also eliminate the obsolescence issues with maintaining the legacy system. Adequate emergency equipment to support the emergency response continues to be provided and maintained. Adequate equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency continue to be in use. Therefore, this change continues to meet the requirements of the Emergency Plan and the requirements of 10 CFR 50.47(b) and Appendix E.

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 4 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Part IV of associated Screen):

10 CFR 50.47(b)(8)

Standard Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

Function Adequate equipment is maintained to support emergency response.

NUREG-0654 II.H.5.b Element Each licensee shall identify and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment. The equipment shall include:

Radiological monitors (e.g. process, area, emergency, effluent) 10 CFR 50.47(b)(9)

Standard Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Function Methods, systems, and equipment for assessment of radioactive releases are in use.

NUREG-0654 II.I. Elements

2. Onsite capability and resources to provide initial values and continuing assessment throughout the course of an accident shall include post-accident sampling capability, radiation and effluent monitors, in-plant iodine instrumentation, and containment radiation monitoring in accordance with NUREG-0578, as elaborated in the NRC letter to all power reactor licensees dated October 30, 1979.
3. Each licensee shall establish methods and techniques to be used for determining:

3.a. the source term of releases of radioactive material within plant systems. An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.

3.b. the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 5 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Radiation Monitoring System (RMS) Migration to the Distributed I&C System Platform (DICSP) / Abandonment of Non-Critical Plant Radiation Monitors (RM-80s), in conjunction with related project Engineering Change Packages EC 83371 ERFIS/DICSP OPC Data Communications Interface Upgrade and EC 80849 Radiation Monitoring System (RMS) RM-80 / Distributed I&C System Platform (DICSP) Fiber Optic Network Infrastructure, perform the following:

Implement an infrastructure upgrade for the Distributed Instrumentation & Controls System Platform (DICSP-System 6300) by replacing legacy system hardware servers and ancillary software components to achieve improved operational performance in support of various plant process applications, inclusive of the new RMS application. (Ref.: EC 83371)

Implement a fiber optic network infrastructure to interconnect each plant radiation monitor in a star topology to the Distributed I&C System Platform (DICSP), thereby eliminating the existing 30mA current loop, device-to-device network topology. Ethernet-to-Current-Loop Adapters (ECLAs) will be installed to bridge RM-80 radiation monitor data communications via fiber to the redundant network core/edge switches and OPC Host Servers of the DICSP. (Ref.: EC 80849)

Eliminate legacy, non-safety related control and display computers (i.e., General Atomics Electronic Systems Inc. Models RM-11 and RM-21) used to collect, process, manipulate (i.e., as appropriate for non-safety related monitors only), display and store data from a distributed, loop-interconnected network of both safety related and non-safety related smart radiation monitors (i.e., General Atomics Electronic Systems Inc. Model RM-80).

Develop and deploy custom OPC Server/Client application software to establish highly reliable, data sharing communications links between: (1) the ERFIS Computer and the DICSP; and (2) a network of RM-80 Radiation Monitors and the DICSP. (Ref.: EC 83371 and EC 66216, respectively)

Develop and deploy a DICSP Graphics Application Package, interlinked via a top-down navigation menu, to facilitate the HMI User Interface for the display and control of Radiation Monitoring System information.

Install five new DICSP HMI Workstations to supplement the deletion/removal of the existing RM-11 HMI User Consoles (i.e., Main Control Room CRS/SM, Main Control Room BOP, RAB 305 Computer Room, WPB Control Room, Health Physics (HP) Office Area - RCA Entry).

This change does not modify the functional capabilities of any critical plant radiation monitor, nor does it modify any functional aspect of the safety related portion of the RMS. This EC will migrate the legacy system hardware to a Distributed Instrumentation & Controls System Platform (DICSP) with a fiber optic network infrastructure. The use of a new, enhanced graphics package for the RMS application on the DICSP serves as a common Human Machine Interface (HMI) to help reduce the operator burden in the rapid assimilation of plant radiological data in both normal and off-normal plant conditions. The migration of critical plant radiation monitors to the DICSP from the legacy RMS computing platform significantly improves the quality, reliability and availability of radiation monitoring system information. This change will also eliminate the obsolescence issues with maintaining the legacy system. The emergency functions of (1), adequate equipment is maintained to support emergency response, and (2), equipment for assessment of radioactive releases are in use, continue to be maintained with this change.

The changes described provide assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure protection of the public health and safety; and
  • effectively use response equipment and emergency response procedures.

Thus, there is no reduction in effectiveness of the Emergency Plan.

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 6 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90, AD-LS-ALL-0002, Regulatory Correspondence, and AD-LS-ALL-0015, License Amendment Request and Changes to SLC, TRM, and TS Bases, and include the tracking number:__________________________________________________.

EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q)

Rev. 6 ATTACHMENT 5 Page 7 of 7

<< 10 CFR 50.54(q) Effectiveness Evaluation Form >>

Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4) (i.e., Emergency Action Levels and Emergency Action Level Bases). If CFAM approval is NOT required, then mark the CFAM signature block as not applicable (N/A) to indicate that signature is not required.

Preparer Name (Print): Jamey Sharlow Preparer Signature: CAS Date:

CAS Reviewer Name (Print): CAS Reviewer Signature: CAS Date:

CAS Approver (Manager, Nuclear Support Approver Signature: CAS Date:

Services) Name (Print): CAS CAS Approver (CFAM, as required) Name (Print): Approver Signature: N/A Date:

N/A If the proposed activity is a change to the E-Plan, then initiate PRRs.

If the proposed activity is a change to the E-Plan, then create two EREG General Assignments.

If required by Section 5.6, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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