RA-24-0062, 10 CFR 50 .54(q) Evaluation
ML24064A200 | |
Person / Time | |
---|---|
Site: | Harris |
Issue date: | 03/04/2024 |
From: | Gunter W Duke Energy Progress |
To: | Office of Nuclear Reactor Regulation, Document Control Desk |
References | |
RA-24-0062 | |
Download: ML24064A200 (1) | |
Text
(_~ DUKE William Gunter Nuclear 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)
March 4, 2024 Serial : RA-24-0062
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) Review Form for a revision to the Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Emergency Action Level (EAL) Technical Basis Document. CSD-EP - HNP-0101 - 01, "EAL Technical Basis Document," Revision 5, was issued on February 22, 2024. A revision to a previous 10 CFR 50.54( q) Review Form completed for CSD - EP-HNP - 0101-01,
Revision 4, issued on December 12, 2023, which was submitted to the NRC on January 8, 2024 (reference Agencywide Documents Access and Management System (ADAMS) Accession number ML24009A106), and a revision to a previous 10 CFR 50.54(q) Review Fo rm completed for EP-HNP-OSSA, "Harris On-Shift Staffing Analysis, " Revision 1, issued on December 14, 2023, which was submitted to the NRC on January 4, 2024 (reference ADAMS Accession number ML24004A243), are included in this submittal.
This submittal contains no regulatory commitments. Please refer any questions regarding this submittal to Sarah McDaniel at (984) 229-2002.
Sincerely,
William Gunter
Enclosure:
10 CFR 50.54(q) Review Form for CSD-EP-HNP -0101-01, Revision 5 10 CFR 50.54(q) Review Form for CSD-EP-HNP-0101-01, Revision 4 10 CFR 50.54(q) Review Form for EP-HNP-OSSA, Revision 1
cc: P. Boguszewski, NRC Senior Resident Inspector, HNP M. Mahoney, NRC Project Manager, HNP NRC Regional Administrator, Region II Document Control Desk Serial: RA-24-0062 Enclosure
ENCLOSURE
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1
DOCKET NO. 50 -400/RENEWED LICENSE NUMBER NPF-63
10 CFR 50.54(q) REVIEW FORM FOR CSD-EP-HNP-0101- 01, REVISION 5
10 CFR 50.54(q) REVIEW FORM FOR CSD-EP-HNP-0101- 01, REVISION 4
10 CFR 50.54(q) REVIEW FORM FOR EP-HNP-OSSA, REVISION 1
(75 PAGES PLUS COVER)
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 1 of 10
<< 10 CFR 50.54(q) Review Form >>
Section I: 10 CFR 50.54(q) Review Number: (EREG #): I 02504297 Applicable Sites and Applicability Determination # (5AD)
BNP I I I I I CNS HNP 02504275
MNS I I I I I ONS RNP Document #, EC #, or Revision # or N/A N/A Document or Activity Title CSD-EP-HNP-0101- 01 005 EAL Technical Basis Document
Section II: Identify/Describe All Proposed Activities/Changes 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 (Use attachments, or continue additional pages as necessary): Continue to Section III.
Activity/Changes:
CSD-EP-HNP-0101- 01, EAL Technical Basis Document, provides explanation and rationale for each Emergency Action Level (EAL) for the Harris Nuclear Plant (HNP).
Revision 005 corrects inadvertent changes to the document that were introduced during processing of Revision 004. These changes include:
- Updating the revision summary and revision number.
- Reinserting abbreviation definitions that were inadvertently deleted.
- Removing an abbreviation definition that was inadvertently added.
- Correcting bold formatting that was inadvertently added.
- Correcting text box formatting that was partially obscuring the associated text.
Change Section or Step Change From Change to 1 Throughout Old revision summary. Updated revision summary identifying the changes made from the document revision request.
2 Throughout Old revision number (004) New revision number (005) 3 5.2 N/A Inserted:
1st column: "CHRRM" 2nd column: "Containment High Range Radiation Monitors" 4 5.2 N/A Inserted:
1st column: "HNP" 2nd column: "Harris Nuclear Plant" EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 2 of 10
<< 10 CFR 50.54(q) Review Form >>
Change Section or Step Change From Change to 5 5.2 N/A Inserted:
1st column: "RAB" 2nd column: "Reactor Auxiliary Building" 6 5.2 "RNP Deleted Robinson Nuclear Plant" 7 5.2 N/A Inserted:
1st column: "TIC" 2nd column: "Thermally Induced Current" 8 6.0, HNP to NEI N/A Inserted:
99- 01 Rev. 6 EAL column: "HU1.1" cross-reference IC column: "HU1" table Example EAL column: "1" 9 Att. 1, RA1.4 4. AD-EP-HNP-0106, HNP Site Specific 4. AD-EP-HNP-0106, HNP Site Specific Basis, OSC Support OSC Support Reference 4 (The word "Support" is in Bold font.) (The word "Support" is no longer bolded.
No text change.)
10 Att. 1, RS1.3 4. AD-EP-HNP-0106, HNP Site Specific 4. AD-EP-HNP-0106, HNP Site Specific Basis, OSC Support OSC Support Reference 4 (The word "Support" is in Bold font.) (The word "Support" is no longer bolded.
No text change.)
11 Att. 2, Fig. 1 In bottom right of figure, the text box The text box containing the words containing the words "Closed Cooling "Closed Cooling Water System" was Water System" was formatted so that reformatted so that all words are visible.
the words "Water System" were only No text change.
partially visible
Section III: Description and Review of Licensing Basis Affected by the Proposed activity or Change:
List all emergency plan sections that were reviewed for this activity by number and title.
IF THE ACTIVITY IN ITS ENTIRETY IS AN EMERGENCY PLAN CHANGE, EAL CHANGE OR EAL BASIS CHANGE, Enter Licensing Basis affected by the change and continue to Section VI.
Licensing Basis for NEI 99- 01 Rev 6 EALs
Letter from U.S. Nuclear Regulatory Commission to Duke Energy, "Shearon Harris Nuclear Power Plant Unit 1 -
Issuance of Amendment [149] to Adopt Emergency Action Level Scheme Pursuant to NEI 99- 01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors," dated April 13, 2016 (ADAMS Accession No. ML16057A838).
License Amendment 149 was implemented in EP-EAL, Emergency Actions Levels, Revision 17.
Letter from U.S. Nuclear Regulatory Commission to Duke Energy, "Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Brunswick Steam Electric plant,
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 3 of 10
<< 10 CFR 50.54(q) Review Form >>
Units 1 and 2; Shearon Harris Nuclear Power Plant, Unit 1; and H.B. Robinson Steam Electric Plant, Unit No. 2 -
Issuance of Amendments [172 for HNP] to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness Frequently Asked Questions 2015- 013, 2015- 014, and 2016- 002 (EPID L-2018-LLA-0174)," dated July 1, 2019 (ADAMS Accession No. ML19058A632).
Letter from U.S. Nuclear Regulatory Commission to Duke Energy, "Shearon Harris Nuclear Power Plant Unit 1 -
Issuance of Amendment No. 173 Regarding Emergency Plan Emergency Action Level Scheme Change (EPID L-2018-LLA-0216)," dated July 18, 2019 (ADAMS Accession No. ML19108A173).
License Amendments 172 and 173 were implemented in EP-EAL, Emergency Actions Levels, Revision 20.
Current EALs
CSD-EP-HNP-0101- 01, EAL Technical Basis Document, Revision 004
Licensing Basis
- EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 0
- EP-HNP-EPLAN-ANNEX, Duke Energy Harris Emergency Plan Annex, Revision 0
Current Emergency Plan
- EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Section D - Emergency Classification System
- EP-HNP-EPLAN-ANNEX, Duke Energy Harris Emergency Plan Annex, Revision 1, Section D - Emergency Classification System
The differences in the approved and the current revision of the Emergency Plan and EALs 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. 9
ATTACHMENT 2 Page 4 of 10
<< 10 CFR 50.54(q) Review Form >>
Section IV: Ability to Maintain the Emergency Plan.
Answer the following questions related to impact on the ability to maintain the Emergency Plan. Continue to Section V.
- 1. Do any of the elements of the proposed activity change information or intent contained in the Yes Emergency Plan? No
- 2. Do any elements of the proposed activity change the process or capability for alerting or notifying Yes the public as described in the FEMA-approved Alert and Notification System Design Report? No
- 3. Do any elements of the proposed activity change the Evacuation Time Estimate results? Yes No
- 4. Do any elements of the proposed activity change the On-Shift Staffing Analysis results? Yes No
- 5. Does the Proposed activity require a change to the Emergency Plan Programmatic Description? Yes No
If Question 5 was answered yes, and the document being reviewed is NOT the Emergency Plan, then exit this review until the Emergency Plan change is complete or the proposed change is modified to not change the Emergency Plan Programmatic Description.
Section IV conclusion:
If questions 1-5 in Section IV marked NO, then complete Section V.
If any question 1-5 of Section IV marked yes, then continue at Section VI.
Section V: Maintaining the Emergency Plan Conclusion.
The questions in Section IV do not represent the total of all conditions that may cause a change to or impact the ability to maintain the emergency plan. Originator and reviewer signatures in Section XIV document that a review of all elements of the proposed change have been considered for their impact on the ability to maintain the emergency plan and their potential to change the emergency plan.
- 1. Provide a brief conclusion below that describes how the conditions, as described in the emergency plan, are maintained with this activity.
- 2. Select the box below when the review completes all actions for all elements of the activity and no 10CFR50.54 screening or evaluation is required for any element. Continue to Section XIV.
I have completed a review of this activity in accordance with 10CFR50.54(q)(2) and determined that the effectiveness of the emergency plan is maintained. This activity does not make any changes to the emergency plan. No further actions are required to screen or evaluate this activity in accordance with 10CFR50.54(q)(3).
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 5 of 10
<< 10 CFR 50.54(q) Review Form >>
Section VI: Activity Previously Reviewed?
Is this activity fully bounded by an NRC approved 10CFR50.90 submittal or Alert and Notification System Design Report?
Yes 10 CFR 50.54(q) Evaluation is not required.
Identify bounding source document below and continue to Section XIV.
No Continue to Section VII.
If PARTIALLY, identify bounding source document and list changes bounded by the approved 10 CFR 50.90 or Alert and Notification System Design Report below.
Partially Changes not bound by the approved 10 CFR 50.90 or Alert and Notification System Design Report (i.e., part requiring further review). Continue the review in Section VII.
Bounding source document and list of bounded changes:
Section VII: Editorial Changes Yes All Activities/Changes identified in Section II are editorial/typographical changes such as formatting, paragraph numbering, spelling, or punctuation that does not change intent.
No None of the Activities/Changes listed in Section II are editorial/typographical changes. Continue to Section VIII.
Partially Some Activities/Changes are editorial/typographical.
If Yes is checked, Identify the activities/changes listed in Section II that are editorial/typographical changes and provide justification below. Continue to Section XII.
If Partially is checked, Identify the activities/changes listed in Section II that are editorial/typographical changes and provide justification below. Continue to Section VIII for changes not identified as editorial.
Justification:
The proposed changes below are defined as editorial in accordance with AD-EP-ALL-0602, Emergency Plan Change Screening and Effectiveness Evaluations 10 CFR 50.54(Q), and do not change the intent of the guidance as written.
Proposed change 1 updates the revision summary. Updating the revision summary based on the new revision is editorial because it makes no changes to the intent of the guidance.
Proposed change 2 updates the revision number from 004 to 005 for the EAL Technical Basis Document. Updating the revision number is editorial because it makes no changes to the intent of the guidance.
Proposed changes 9 and 10 remove bold formatting that was inadvertently added during processing of Revision 004without making any changes to the text. Correcting formatting without changes to the text is editorial because it does not make any changes to the intent, purpose, or order of the guidance.
Proposed change 11corrects the formatting of a text box in the lower right of the image that was partially obscuring the associated text. No changes were made to the text contained in the text box. Correcting formatting without changes to the text is editorial because it does not make any changes to the intent, purpose, or order of the guidance.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 6 of 10
<< 10 CFR 50.54(q) Review Form >>
Section VIII: Emergency Planning Element and Function Screen (Utilize Reg Guide 1.219 and Attachment 1, Additional Regulatory Guidance References for additional assistance)
Does any of Proposed Activities/Changes Identified in Section I impact any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II? If yes check appropriate bo x.
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.
4 10 CFR 50.47(b)(4) Emergency Classification System RS 4a A standard scheme of emergency classification and action levels is in use. (Requires V/V (Attachment 3) and final approval of Screen and Evaluation by EP CFAM) 5 10 CFR 50.47(b)(5) Notification Methods and Procedures RS Procedures for notification of State and local governmental agencies are capable of alerting them of 5a 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 public within the plume exposure pathway.
The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and 5c Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA -approved ANS design report and supporting FEMA approval letter 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).
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 RS 9a Methods, systems, and equipment for assessment of radioactive releases are in use.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 7 of 10
<< 10 CFR 50.54(q) Review Form >>
10 10 CFR 50.47(b) (10) Protective Response RS 10a A range of public PARs is available for implementation during emergencies.
Evacuation time estimates for the population located in the plume exposure pathway EPZ are 10b available to support the formulation of PARs and have been provided to State and local governmental authorities.
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.
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.
Section VIII: Conclusion
If any Section VIII criteria are checked, document the basis for conclusion below for any changes that are more than editorial, however not impacted by any of the identified criteria in Section VIII and continue the 50.54(q) Review in Section IX.
If no Section VIIIcriteri a are checked, 10CFR50.54(q)(3) Evaluation is NOT required. Document justification below for any changes that are more than editorial and continue to Section XIV.
Justification for changes that are more than editorial, however, not impacted by any of the identified criteria in Section VIII:
Proposed changes 3, 4, 5, and 7 reinsert abbreviation definitions that were inadvertently deleted during processing of Revision 004. These changes are more than editorial; however, these changes can be made because they do not change the intent of the guidance as written.
Proposed change 6 deletes an abbreviation definition that was inadvertently added during processing of Revision 004. This change is more than editorial; however, this change can be made because it does not change the intent of the guidance as written.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 8 of 10
<< 10 CFR 50.54(q) Review Form >>
Proposed change 8 reinserts the "HU1.1" HNP EAL to NEI 99- 01, Rev 6, cross-reference into the cross-reference table. This cross-reference was inadvertently deleted during processing of Revision 004. This change is more than editorial; however, this change can be made because it does not change the intent of the guidance.
The proposed changes above can be made because these changes return the document to its state prior to the processing errors introduced when implementing Revision 004. These changes do not affect the EAL scheme or affect the timeliness or accuracy of emergency declarations.
Section IX: Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change Copy each emergency planning standard, function and program element affected by the proposed change that was identified as applicable in Section VIII. Continue to Section X.
List affected Emergency Planning Standards, Functions, and Program Elements:
Section X: Describe How the Proposed Change Complies with Relevant Emergency Preparedness Regulation(s) and Previous Commitment(s) Made to the NRC 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). Address each Planning Standard identified in Section IX. Continue to Section XI.
Justification:
Section XI: Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions Address each function identified in Section IX. Continue to Section XII.
Justification:
Section XII: 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 reduction in Yes effectiveness)? No
- 3. Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No Section XII: Conclusion Questions 1, 2 and 3 are answered YES, complete step below to create a General CAS assignment, and then continue on to Section XIV and implement change(s).
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 9 of 10
<< 10 CFR 50.54(q) Review Form >>
General CAS assignment created-Licensing submit changes in accordance with 10 CFR 50.4(b)(5)(ii) within 30 days of change implementation I I Questions 1 or 2 or 3 are answered NO, complete Sections XIII and Section XIV.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 10 of 10
<< 10 CFR 50.54(q) Review Form >>
Section XIII: Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change be submitted to the NRC for prior approval?
Yes If No, reject the proposed change, or modify the proposed change and perform a new evaluation. No Continue to Section XIV for this evaluation.
If YES, 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:___________________________________. Complete Section XIV.
Section XIV: Signatures:
EP CFAM Final Approval is required for changes affecting Program Element 4a of Section VIII. 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.Section XIV as applicable.
Preparer Name (Print): Preparer Signature: Date:
David Bell See NAS See NAS Reviewer Name (Print): Reviewer Signature: Date:
Sarah McDaniel See NAS See NAS Approver Name (Print): Approver Signature: Date:
William Gunter See NAS See NAS Approver (EP CFAM, as required) Name (Print): Approver Signature: Date:
N/A N/A N/A
QA RECORD
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 1 of 42
<< 10 CFR 50.54(q) Review Form >>
Section I: 10 CFR 50.54(q) Review Number: (EREG #): 02490584 02504846 Applicable Sites and Applicability Determination # (5AD)
BNP I I I I I CNS HNP 02490554
MNS I I I I I ONS RNP Document #, EC #, or Revision # or N/A N/A Document or Activity Title CSD-EP-HNP-0101- 01 4 EAL Technical Basis Document
Section II: Identify/Describe All Proposed Activities/Changes 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 (Use attachments, or continue additional pages as necessary): Continue to Section III.
This is a revised 50.54(q) review. Changes to the original 50.54(q) review can be identified by:
- Additions to this revised 50.54(q) review will appear in Bold and Italicized format.
- Deletions to this revised 50.54q) review will appear in struck through format.
CSD-EP-HNP-0101- 01 is the Emergency Action Level (EAL) technical basis document for Harris Nuclear Plant (HNP).
Changes include:
- Updated revision summary and revision number.
- Various reference updates and formatting changes.
- Updated EAL SU5.1 basis definitions of Reactor Coolant System (RCS) leakage as a result of revised Technical Specifications (TSs) related to reactor coolant system operational leakage and the definition of the term "LEAKAGE" based on Technical Specifications Task Force (TSTF) Traveler TSTF -554, Revision 1, "Revise Reactor Coolant Leakage Requirements."
Change Section or Step Change From Change to 1 Throughout Old revision summary. Updated revision summary identifying the changes made from the document revision request.
2 Throughout CSD-EP-HNP-0101 Old revision CSD-EP-HNP-0101 New revision number (003) number (004) 3 Throughout Old page numbers and Table of Updated page numbers and Table of Contents Contents 4 Throughout PEP-110, Emergency Classification and AD-EP-ALL-0101, Emergency Protective Action Recommendations Classification, and AD-EP-ALL-0109, Offsite Protective Action Recommendations EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 2 of 42
<< 10 CFR 50.54(q) Review Form >>
Change Section or Step Change From Change to 5 Throughout Shearon Harris Nuclear Power Plant O/S Dose Calc Manual, Shearon Harris Offsite Dose Calculation Manual Nuclear Power Plant Off-site Dose (ODCM) Calculation Manual (ODCM) 6 Throughout EP-EALCALC-HNP-1401, HNP CSD-EP-HNP-0101-04, EAL Calculation Radiological Effluent EAL Values - Radiological Effluent EAL Values 7 Throughout AOP-20, Loss of RCS Inventory or AOP-020, Loss of RCS Inventory or Residual Heat Removal While Residual Heat Removal While Shutdown Shutdown
8 Throughout AOP-20, Loss of RCS Inventory or AOP-020-BD, Loss of RCS Inventory or Residual Heat Removal While Residual Heat Removal While Shutdown Shutdown - Basis Document 9 Throughout AOP-21, Seismic Disturbances AOP-021, Seismic Disturbances 10 Throughout PEP-342, Core Damage Assessment AD-EP-PWR-0206, Core Damage Assessment During An Emergency 11 Throughout AOP-16, Excessive Primary Plant AOP-016, Excessive Primary Plant Leakage Leakage 12 Throughout judgement judgment 13 Throughout OP-125, Hydrogen Monitoring System OP-125, Hydrogen Monitoring System (HSM) (HMS) 14 Throughout Old formatting throughout document Updated formatting throughout document in accordance with AD-DC-ALL-0301, Development and Maintenance of Controlled Supporting Documents. Changes include:
- Changing outline and substep bullets from "A.", "B", "C", to "1.", "2.", "3."
- Placing periods "." after step numbers
- Bolding step numbers
- Adding section continuation headers
- Removing underline from substep numbers
- Reformatting attachment titles so that they are below the attachment number
- Reformatting fonts
(Formatting changes only. No change to text)
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 3 of 42
<< 10 CFR 50.54(q) Review Form >>
Change Section or Step Change From Change to 15 2.6, Operating 1 Power Operations (Reformatted into table format only. No Mode definitions Keff 0.99 and reactor thermal power > change to text.)
5% and average coolant temperature 350ºF 1 P~rQ~tiQfJS; Keff ~ 0. 99 and reactor thermal power >5% and average coolant temperature 2 Startup ~ 350° f 2 ~
Keff 0.99 and reactor thermal power Ken :2!: 0.99 and reactor thermal power :S: 5% average COOiant temperature 5% average coolant temperature ~350° F 3 Hot standby 350ºF Ken < 0.99 and average coolant temperature~ 35QOF 3 Hot Standby 4 Hot Shutdown K~ < 0.99 and average coolant temperature 350°F > T avg > 200°F (exduding Keff < 0.99 and average coolant decay hea l) 5 ~
temperature 350ºF Keff < 0.99 and average coolant temperat ure Tavg :S: 200"F 4 Hot Shutdown 6 Refueling Ken < 0.95 and average coolant temperature T -a s 140°F; fuel in the reactor Keff < 0.99 and average coolant vessel wittl tne vessel head closure bolts less tnan flllly tenSioned or with the head removed temperature 350ºF > Tavg > 200 ºF D Defueled (excluding decay heat) All reactor fuel removed from reactor pressure vessel (full core off load during refUeling or extended outage) 5 Cold Shutdown Keff < 0.99 and average coolant temperature Tavg 200ºF 6 Refueling Keff < 0.95 and average coolant temperature Tavg 140°F; fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed D Defueled All reactor fuel removed from reactor pressure vessel (full core off load during refueling or extended outage) 16 4.1.9 4.1.9 PRO-NGGC-0201, NGG 4.1.9 AD-DC-ALL-0202, Writer's Manual Procedure Writer's Guide for Procedures and Work Instructions 17 4.2 4.2.1 PEP-110, Emergency 4.2.1 AD-EP-ALL-0101, Emergency Classification and Protective Action Classification Recommendations 4.2.2 AD-EP-ALL-0109, Offsite 4.2.2 NEI 99- 01 Rev. 6 to HNP EAL Protective Action Recommendations Comparison Matrix 4.2.3 NEI 99- 01 Rev. 6 to HNP EAL 4.2.3 HNP EAL Matrix Comparison Matrix 4.2.4 HNP EAL Matrix 18 5.1 See Enclosure 1 (Numbered Definitions only. No change to text.)
See Enclosure 2 19 5.2 See Enclosure 3 (Reformatted Abbreviations/Acronyms to table format only. No change to text.) --
See Enclosure 4 EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
ATTACHMENT 2 Page 4 of 42
<< 10 CFR 50.54(q) Review Form >>
Change Section or Step Change From Change to 20 7.0 7.1 Attachment 1, Emergency Action Attachment 1, EAL Bases Level Technical Bases Attachment 2, Fission Product Barrier 7.2 Attachment 2, Fission Product Loss/Potential Loss Matrix and Bases Barrier Matrix and Basis Attachment 3, Safe Operation &
7.3 Attachment 3, Safe Operation & Shutdown Room/Areas Tables R-3/H-2 Shutdown Areas Tables R-3/H-2 Bases Bases 21 Att. 1, RA1.4 PEP-270, Activation and Operation of AD-EP-ALL-0103, Activation and Basis, the Emergency Operations Facility and Operation of the Emergency Operations Paragraph 1 PEP-330, Radiological Consequences Facility, AD-EP-ALL-0204, Distribution of provide guidance for emergency or Potassium Iodide Tablets in the Event of Att. 1, RS1.3 post-accident radiological a Radioiodine Release, AD-EP-ALL-Basis, environmental monitoring (ref. 1, 2). 0205, Emergency Exposure Controls, Paragraph 1 AD-EP-HNP-0106, HNP Site-Specific OSC Support, AD-EP-HNP-0203, HNP Att. 1, RG1.3 Site-Specific Field Monitoring, AD-RP-Basis, ALL-2000, Preparation and Management Paragraph 1 of Radiation Work Permits (RWP), and AD-RP-ALL-4010, Internal Dose Assessment provides guidance for emergency or post-accident radiological environmental monitoring (ref. 1 - 7).
22 Att. 1, RA1.4 1. PEP-270, Activation and Operation of 1. AD-EP-ALL-0103, Activation and Basis the Emergency Operations Facility Operation of the Emergency Operations Reference(s) 2. PEP-330, Radiological Facility Consequences 2. AD-EP-ALL-0204, Distribution of
- 3. NEI 99- 01 AA1 Potassium Iodide Tablets in the Event of a Radioiodine Release,
- 3. AD-EP-ALL-0205, Emergency Exposure Controls
- 5. AD-EP-HNP-0203, HNP Site-Specific Field Monitoring
- 6. AD-RP-ALL-2000, Preparation and Management of Radiation Work Permits (RWP)
- 7. AD-RP-ALL-4010, Internal Dose Assessment
- 8. NEI 99-01 AA1 EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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<< 10 CFR 50.54(q) Review Form >>
Change Section or Step Change From Change to 23 Att. 1, RS1.3 1. PEP-270, Activation and Operation of 1. AD-EP-ALL-0103, Activation and Basis the Emergency Operations Facility Operation of the Emergency Operations Reference(s) 2. PEP-330, Radiological Facility Consequences 2. AD-EP-ALL-0204, Distribution of
- 3. NEI 99- 01 AS1 Potassium Iodide Tablets in the Event of a Radioiodine Release,
- 3. AD-EP-ALL-0205, Emergency Exposure Controls
- 5. AD-EP-HNP-0203, HNP Site-Specific Field Monitoring
- 6. AD-RP-ALL-2000, Preparation and Management of Radiation Work Permits (RWP)
- 7. AD-RP-ALL-4010, Internal Dose Assessment
- 8. NEI 99-01 AS1 24 Att. 1, RG1.3 1. PEP-270, Activation and Operation of 1. AD-EP-ALL-0103, Activation and Basis the Emergency Operations Facility Operation of the Emergency Operations Reference(s) 2. PEP-330, Radiological Facility Consequences 2. AD-EP-ALL-0204, Distribution of
- 3. NEI 99- 01 AG1 Potassium Iodide Tablets in the Event of a Radioiodine Release,
- 3. AD-EP-ALL-0205, Emergency Exposure Controls
- 5. AD-EP-HNP-0203, HNP Site-Specific Field Monitoring
- 6. AD-RP-ALL-2000, Preparation and Management of Radiation Work Permits (RWP)
- 7. AD-RP-ALL-4010, Internal Dose Assessment
- 8. NEI 99-01 AG1 EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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<< 10 CFR 50.54(q) Review Form >>
Change Section or Step Change From Change to 25 Att. 1, SU5.1 Identified Leakage: Identified Leakage:
Basis, a. Leakage (except controlled leakage) a. Leakage, such as that from pump Paragraph 2 into closed systems, such as pump seal seals or valve packing (except controlled or valve packing leaks that are captured leakage), that is captured and conducted and conducted to a sump or collecting to a sump or collecting tank, or tank, or b. Leakage into the containment
- b. Leakage into the containment atmosphere from sources that are both atmosphere from sources that are both specifically located and known to not specifically located or known either not interfere with the operation of leakage to interfere with the operation of detection systems, or leakage detection systems or not to be c. RCS leakage through a steam pressure boundary leakage, or generator to the Secondary Coolant
- c. RCS leakage through a steam System (primary-to-secondary leakage).
generator to the Secondary Coolant Unidentified Leakage:
System (primary-to-secondary leakage). All leakage which is not identified Unidentified Leakage: leakage or controlled leakage.
All leakage which is not identified (Controlled leakage is that seal water Leakage or controlled leakage. flow supplied to the reactor coolant (Controlled leakage is that seal water pump seals.)
flow supplied to the reactor coolant Pressure Boundary Leakage:
pump seals.) Leakage (except primary-to-secondary Pressure Boundary Leakage: leakage) through a fault in a RCS Leakage (except primary-to-secondary component body, pipe wall, or vessel leakage) through a non-isolable fault inwall. Leakage past seals, packing, and a RCS component body, pipe wall, or gaskets is not pressure boundary vessel wall. leakage.
26 Att. 1, SU5.1 The first and second EAL conditions are The first and second EAL conditions are Basis, focused on a loss of mass from the focused on a loss of mass from the RCS Paragraph 6 RCS due to "unidentified leakage", due to "unidentified leakage", "pressure "pressure boundary leakage" or boundary leakage" or "identified "identified leakage" (as these leakage leakage" (as these leakage types are types are defined in the plant Technical defined in the plant Technical Specifications). The third condition Specifications). The third condition addresses an RCS mass loss caused addresses an RCS mass loss caused by by an UNISOLABLE leak through an a leak through an interfacing system.
interfacing system. These conditions These conditions thus apply to leakage thus apply to leakage into the into the containment, a secondary-side containment, a secondary-side system system (e.g., steam generator tube (e.g., steam generator tube leakage) or leakage) or a location outside of a location outside of containment. containment.
................................................................2nd column: "Abnormal Operating
.................... Abnormal Operating Procedure" Procedure 28 5.2 CHRRM Deleted Containment High Range Radiation Monitors EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Change Section or Step Change From Change to 29 5.2 HNP Deleted
................................... Harris Nuclear Plant 30 5.2 RAB Deleted
.......................... Reactor Auxiliary Building 31 5.2 N/A Added:
1st column: "RNP" 2nd column: "Robinson Nuclear Plant" 32 5.2 N/A Added:
1st column: "RPV" 2nd column: "Reactor Pressure Vessel" 33 5.2 TIC Deleted
........................... Thermally Induced Current 34 6.0 EAL column: "HU1.1" Deleted IC column: "HU1" Example EAL column: "1"
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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<< 10 CFR 50.54(q) Review Form >>
Section III: Description and Review of Licensing Basis Affected by the Proposed activity or Change:
List all emergency plan sections that were reviewed for this activity by number and title.
IF THE ACTIVITY IN ITS ENTIRETY IS AN EMERGENCY PLAN CHANGE, EAL CHANGE OR EAL BASIS CHANGE, Enter Licensing Basis affected by the change and continue to Section VI.
Licensing Basis for NEI 99 -01 Rev 6 EALs
Letter from U.S. Nuclear Regulatory Commission to Duke Energy, "Shearon Harris Nuclear Power Plant Unit 1 -
Issuance of Amendment [149] to Adopt Emergency Action Level Scheme Pursuant to NEI 99- 01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors," dated April 13, 2016 (ADAMS Accession No. ML16057A838).
License Amendment 149 was implemented in EP-EAL, Emergency Actions Levels, Revision 17.
Letter from U.S. Nuclear Regulatory Commission to Duke Energy, "Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Brunswick Steam Electric plant, Units 1 and 2; Shearon Harris Nuclear Power Plant, Unit 1; and H.B. Robinson Steam Electric Plant, Unit No. 2 -
Issuance of Amendments [172 for HNP] to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness Frequently Asked Questions 2015- 013, 2015- 014, and 2016- 002 (EPID L-2018-LLA-0174)," dated July 1, 2019 (ADAMS Accession No. ML19058A632).
Letter from U.S. Nuclear Regulatory Commission to Duke Energy, "Shearon Harris Nuclear Power Plant Unit 1 -
Issuance of Amendment No. 173 Regarding Emergency Plan Emergency Action Level Scheme Change (EPID L-2018-LLA-0216)," dated July 18, 2019 (ADAMS Accession No. ML19108A173).
License Amendments 172 and 173 were implemented in EP-EAL, Emergency Actions Levels, Revision 20.
Current EALs
Harris Nuclear Plant EAL Technical Basis Document, CSD-EP-HNP-0101- 01, Revision 003
Licensing Basis
- EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 0
- EP-HNP-EPLAN-ANNEX, Duke Energy Harris Emergency Plan Annex, Revision 0
Current Emergency Plan
- EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Section D - Emergency Classification System
- EP-HNP-EPLAN-ANNEX, Duke Energy Harris Emergency Plan Annex, Revision 1, Section D - Emergency Classification System
The differences in the approved and the current revision of the Emergency Plan and EALs 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. 9
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Section IV: Ability to Maintain the Emergency Plan.
Answer the following questions related to impact on the ability to maintain the Emergency Plan. Continue to Section V.
- 1. Do any of the elements of the proposed activity change information or intent contained in the Yes Emergency Plan? No
- 2. Do any elements of the proposed activity change the process or capability for alerting or notifying Yes the public as described in the FEMA-approved Alert and Notification System Design Report? No
- 3. Do any elements of the proposed activity change the Evacuation Time Estimate results? Yes No
- 4. Do any elements of the proposed activity change the On-Shift Staffing Analysis results? Yes No
- 5. Does the Proposed activity require a change to the Emergency Plan Programmatic Description? Yes No
If Question 5 was answered yes, and the document being reviewed is NOT the Emergency Plan, then exit this review until the Emergency Plan change is complete or the proposed change is modified to not change the Emergency Plan Programmatic Description.
Section IV conclusion:
If questions 1-5 in Section IV marked NO, then complete Section V.
If any question 1-5 of Section IV marked yes, then continue at Section VI.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section V: Maintaining the Emergency Plan Conclusion.
The questions in Section IV do not represent the total of all conditions that may cause a change to or impact the ability to maintain the emergency plan. Originator and reviewer signatures in Section XIV document that a review of all elements of the proposed change have been considered for their impact on the ability to maintain the emergency plan and their potential to change the emergency plan.
- 1. Provide a brief conclusion below that describes how the conditions, as described in the emergency plan, are maintained with this activity.
- 2. Select the box below when the review completes all actions for all elements of the activity and no 10CFR50.54 screening or evaluation is required for any element. Continue to Section XIV.
I have completed a review of this activity in accordance with 10CFR50.54(q)(2) and determined that the effectiveness of the emergency plan is maintained. This activity does not make any changes to the emergency plan. No further actions are required to screen or evaluate this activity in accordance with 10CFR50.54(q)(3).
Conclusion:
Section VI: Activity Previously Reviewed?
Is this activity fully bounded by an NRC approved 10CFR50.90 submittal or Alert and Notification System Design Report?
Yes 10 CFR 50.54(q) Evaluation is not required.
Identify bounding source document below and continue to Section XIV.
No Continue to Section VII.
If PARTIALLY, identify bounding source document and list changes bounded by the approved 10 CFR 50.90 or Alert and Notification System Design Report below.
Partially Changes not bound by the approved 10 CFR 50.90 or Alert and Notification System Design Report (i.e., part requiring further review). Continue the review in Section VII.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section VII: Editorial Changes Yes All Activities/Changes identified in Section II are editorial/typographical changes such as formatting, paragraph numbering, spelling, or punctuation that does not change intent.
No None of the Activities/Changes listed in Section II are editorial/typographical changes. Continue to Section VIII.
Partially Some Activities/Changes are editorial/typographical.
If Yes is checked, Identify the activities/changes listed in Section II that are editorial/typographical changes and provide justification below. Continue to Section XII.
If Partially is checked, Identify the activities/changes listed in Section II that are editorial/typographical changes and provide justification below. Continue to Section VIII for changes not identified as editorial.
Justification:
The proposed changes below are defined as editorial in accordance with AD-EP-ALL-0602, Emergency Plan Change Screening and Effectiveness Evaluations 10 CFR 50.54(Q), and do not change the intent of the steps as written.
Proposed change 1 updates revision summary. Updating revision summary based on revision is editorial because it makes no changes to intent of the guidance.
Proposed change 2 updates revision number from 3 to 4 for EAL Technical Basis Document. Updating revision number is editorial because it makes no changes to intent of the guidance.
Proposed change 3 updates page numbers and the Table of Contents. Updating page numbers and the Table of Contents is editorial because it makes no changes to intent of the guidance.
Proposed changes 4 - 11, 16, 17, and 21 - 24 update references to procedures and correct references that are no longer applicable. Updating references to procedures and correcting references that are no longer applicable is editorial because it makes no changes to intent of the guidance.
Proposed change 12 corrects a misspelled word. Correcting misspelled words is editorial because it makes no changes to intent of the guidance.
Proposed change 13 corrects a typographical error in the system abbreviation. Correcting typographical errors is editorial because it makes no changes to intent of the guidance.
Proposed changes 14, 15, 18, and 19 are formatting changes only to comply with the guidance of AD-DC-ALL- 0301, Development and Maintenance of Controlled Supporting Documents. These changes include:
- Changing outline and substep bullets from "A.", "B", "C", to "1.", "2.", "3."
- Adding numbering to Definitions
- Reformatting items into table-style format
- Placing periods "." after step numbers
- Bolding step numbers
- Adding section continuation headers
- Removing underline from substep numbers
- Reformatting attachment titles so that they are below the attachment number
- Reformatting fonts EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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These changes make no change to intent, purpose, or order of the document steps. These formatting changes are editorial because there is no change to intent, purpose, or order of the document steps.
Proposed change 20 corrects the titles of Attachments 1, 2, and 3 to correspond to the titles used for these items in CSD-EP-ALL-0101- 02, EAL Wallchart (Both Hot and Cold). Correcting references to steps, pages, attachments, forms, documents, tables, exhibits, and procedures is editorial because it makes no changes to intent of the guidance.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section VIII: Emergency Planning Element and Function Screen (Utilize Reg Guide 1.219 and Attachment 1, Additional Regulatory Guidance References for additional assistance)
Does any of Proposed Activities/Changes Identified in Section I impact any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II? If yes check appropriate 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 onshift 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.
4 10 CFR 50.47(b)(4) Emergency Classification System RS 4a A standard scheme of emergency classification and action levels is in use. (Requires V/V (Attachment 3) and final approval of Screen and Evaluation by EP CFAM) 5 10 CFR 50.47(b)(5) Notification Methods and Procedures RS Procedures for notification of State and local governmental agencies are capable of alerting them of 5a 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 public within the plume exposure pathway.
The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and 5c Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA -approved ANS design report and supporting FEMA approval letter 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).
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 RS 9a Methods, systems, and equipment for assessment of radioactive releases are in use.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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10 10 CFR 50.47(b) (10) Protective Response RS 10a A range of public PARs is available for implementation during emergencies.
Evacuation time estimates for the population located in the plume exposure pathway EPZ are 10b available to support the formulation of PARs and have been provided to State and local governmental authorities.
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.
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.
Section VIII: Conclusion
If any Section VIII criteria are checked, document the basis for conclusion below for any changes that are more than editorial, however not impacted by any of the identified criteria in Section VIII and continue the 50.54(q) Review in Section IX.
If no Section VIIIcriteria are checked, 10CFR50.54(q)(3) Evaluation is NOT required. Document justification below for any changes that are more than editorial and continue to Section XIV.
Proposed change 27 corrects the abbreviation for "Abnormal Operating Procedure" from "AP" to "AOP".
This change is more than editorial; however, this change can be made because it does not change the intent of the guidance as written.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Proposed changes 28, 29, 30, and 33delete abbreviation definitions from Section 5.2. This section serves as a reference to the reader for various abbreviations and acronyms used throughout the document and does not provide EAL basis guidance. These changes were inadvertently introduced during processing of Revision 004 by the Procedure Automation System (PAS) software and were noted after approval of the previous 10 CFR 50.54(q) evaluation and issuance of the new revision. These changes are more than editorial; however, these changes can be made because they do not change the intent of the guidance as written.
Proposed changes 31 and 32add abbreviation definitions to Section 5.2. This section serves as a reference to the reader for various abbreviations and acronyms used throughout the document and does not provide EAL basis guidance. These changes were inadvertently introduced during processing of Revision 004 by the Procedure Automation System (PAS) software and were noted after approval of the previous 10 CFR 50.54(q) evaluation and issuance of the new revision. These changes are more than editorial; however, these changes can be made because they do not change the intent of the guidance as written.
Proposed change 34deletes the HNP EAL -to-NEI 99-01 Rev. 6 EAL cross-reference for HU1.1 in Section 6.0. This section serves as a cross-reference to facilitate association and location of a HNP EAL within the NEI 99- 01 IC/EAL identification scheme and does not provide EAL basis guidance. This change was inadvertently introduced during processing of Revision 004 by the Procedure Automation System (PAS) software and was noted after approval of the previous 10 CFR 50.54(q) evaluation and issuance of the new revision. This change is more than editorial; however, this change can be made because it does not change the intent of the guidance as written.
The proposed changes above can be made because these changes do not affect the EAL scheme or affect the timeliness or accuracy of emergency declarations.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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<< 10 CFR 50.54(q) Review Form >>
Section IX: Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change Copy each emergency planning standard, function and program element affected by the proposed change that was identified as applicable in Section VIII. Continue to Section X.
Planning Standard
A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.
Function
(1) A standard scheme of emergency classification and action levels is in use.
Supporting requirements from Appendix E, IV to 10 CFR Part 50
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, including emergency action levels that are to be used as criteria for determining the need for notification and participation of local and State agencies, the Commission, and other Federal agencies, and the emergency action levels that are to be used for determining when and what type of protective measures should be considered within and outside the site boundary to protect health and safety. The emergency action levels shall be based on in-plant conditions and instrumentation in addition to onsite and offsite monitoring. By June 20, 2012, for nuclear power reactor licensees, these action levels must include hostile action that may adversely affect the nuclear power plant. The initial emergency action levels shall be discussed and agreed on by the applicant or licensee and state and local governmental authorities, and approved by the NRC. Thereafter, emergency action levels shall be reviewed with the State and local governmental authorities on an annual basis.
- 2. A licensee desiring to change its entire emergency action level scheme shall submit an application for an amendment to its license and receive NRC approval before implementing the change. Licensees shall follow the change process in § 50.54(q) for all other emergency action level changes.
C. Activation of Emergency Organization
- 1. The entire spectrum of emergency conditions that involve the alerting or activating of progressively larger segments of the total emergency organization shall be described. The communication steps to be taken to alert or activate emergency personnel under each class of emergency shall be described. Emergency action levels (based not only on onsite and offsite radiation monitoring information but also on readings from a number of sensors that indicate a potential emergency, such as the pressure in containment and the response of the Emergency Core Cooling System) for notification of offsite agencies shall be described. The existence, but not the details, of a message authentication scheme shall be noted for such agencies. The emergency classes defined shall include: (1) Notification of unusual events, (2) alert, (3) site area emergency, and (4) general emergency. These classes are further discussed in NUREG- 0654/FEMA-REP-1.
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- 2. By June 20, 2012, nuclear power reactor licensees shall establish and maintain the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level has been exceeded and shall promptly declare the emergency condition as soon as possible following identification of the appropriate emergency classification level.
Licensees shall not construe these criteria as a grace period to attempt to restore plant conditions to avoid declaring an emergency action due to an emergency action level that has been exceeded. Licensees shall not construe these criteria as preventing implementation of response actions deemed by the licensee to be necessary to protect public health and safety provided that any delay in declaration does not deny the State and local authorities the opportunity to implement measures necessary to protect the public health and safety.
Informing criteria from Section II.D of NUREG -0654 Rev. 2
D. A standard emergency classification and action level scheme is established and maintained.
The scheme provides detailed EALs for each of the four ECLs in Section IV.C.1 of Appendix E to 10 CFR Part 50.
D.1.a The EALs are developed using guidance provided or endorsed by the NRC that is applicable to the reactor design.
D.1.b The initial emergency classification and action level scheme is discussed and agreed to by the licensee and OROs, and approved by the NRC. Thereafter, the scheme is reviewed with OROs on an annual basis.
D.2 The capability to assess, classify, and declare the emergency condition within 15 minutes after the availability of indications to NPP operators that an EAL has been met or exceeded is described.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section X: Describe How the Proposed Change Complies with Relevant Emergency Preparedness Regulation(s) and Previous Commitment(s) Made to the NRC 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). Address each Planning Standard identified in Section IX. Continue to Section XI.
Proposed change 25:
Proposed change is being made to update EAL SU5.1 basis definitions for identified, unidentified, and pressure boundary leakage. Paragraph 2 was originally written based on Harris Nuclear Plant Technical Specifications (TSs) Definitions section 1.1, as referenced at the end of the EAL basis (ref.1). This reference has been updated in Amendment No. 198 to Renewed Facility Operating License No. DPR-63 for the Harris Nuclear Plant, Unit No. 1. The amendment revises the TSs related to reactor coolant system operational leakage and the definition of the term "LEAKAGE" based on Technical Specifications Task Force (TSTF) Traveler TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements."
Paragraph 2, part 1, changes:
From:
Identified Leakage:
- a. Leakage (except controlled leakage) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located or known either not to interfere with the operation of leakage detection systems or not to be pressure boundary leakage, or
- c. RCS leakage through a steam generator to the Secondary Coolant System (primary-to-secondary leakage).
To:
Identified Leakage:
- a. Leakage, such as that from pump seals or valve packing (except controlled leakage), that is captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems, or
- c. RCS leakage through a steam generator to the Secondary Coolant System (primary-to-secondary leakage).
Revises the Identified Leakage definition to not exclude Pressure Boundary Leakage. The change tothe definition of identified leakage applies to leakage from an RCS component that would be released directly into the containment atmosphere, where the leakage would be detectable by the RCS leakage detection systems. The revised definition of identifiedleakage removes the existing exclusion of leakage known to be pressure boundary leakage. Therefore, all RCS leakage that is specifically located and known to not interfere with the operation of leakage detection systems would be considered identified leakage, regardless of the source of leakage. Not excluding Pressure Boundary Leakage provides a clearer definition of identified leakage.
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Paragraph 2, part 2: No changes.
Paragraph 2, part 3, changes:
From:
Pressure Boundary Leakage:
Leakage (except primary-to-secondary leakage) through a non-isolable fault in a RCS component body, pipe wall, or vessel wall.
To:
Pressure Boundary Leakage:
Leakage (except primary-to-secondary leakage) through a fault in a RCS component body, pipe wall, or vessel wall. Leakage past seals, packing, and gaskets is not pressure boundary leakage.
Revises the defined term "leakage" to remove the term "non-isolable" from the definition of Pressure Boundary Leakage and added "Leakage past seals, packing, and gaskets is not pressure boundary leakage".
From NRC Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements," the word "unisolable" [the terms "unisolable" and "non-isolable" are used interchangeably herein] has been interpreted inconsistently in the definition of pressure boundary leakage. In some interpretations, it has been considered a means of emphasizing that the leakage fault is in the base material of the pressure boundary and, therefore, the leakage cannot be stopped by adjusting packing or seals. In such a case, the fault represents degradation of the pressure boundary material that could result in a loss of structural integrity. Another interpretation is that leakage through a fault in portions of the pressure boundary that can be separated from the RCS by an isolation device (typically an installed valve) need not be considered as pressure boundary leakage once the isolation device is performing its isolation function. This would allow certain small sections of the Reactor Coolant Pressure Boundary (RCPB) between the outermost two valves to be removed from consideration as RCPB leakage when the inner valve is closed. Regardless of the interpretation, deletion of the word "unisolable" does not alter the fundamental meaning that pressure boundary leakage represents degradation that could ultimately result in a loss of structural integrity. Therefore, removing the term "unisolable" provides a clearer definition of pressure boundary leakage.
The additional sentence "Leakage past seals, packing, and gaskets is not pressure boundary leakage." is consistent with the definition and was added for emphasis. Definition is clear that pressure boundary leakage is leakage through a fault in an RCS component body, pipe wall, or vessel wall. The additional reminder to exclude leakage from seals, packing, and gaskets which are not RCS component bodies, pipe walls, or vessel walls is an enhancement with no change to the intent of the definition.
The revised second paragraph, part 1, supports the 2nd EAL condition, "RCS identified leakage > 25 gpm for 15 min." and the revised second paragraph, part 3, supports the 1st EAL condition, "RCS unidentified or pressure boundary leakage > 10 gpm for 15 min.". These proposed changes remain consistent with the approved EAL scheme as described in the 6th paragraph of HNP EAL bases:
The first and second EAL conditions are focused on a loss of mass from the RCS due to "unidentified leakage", "pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications).
These proposed changes remain consistent with NEI 99- 01, Rev 6, EAL scheme for this EAL:
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EAL #1 and EAL #2 are focused on a loss of mass from the RCS due to "unidentified leakage",
"pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications).
These proposed changes continue to support the first and second EAL conditions, because the definitions continue to be leakage types that are defined in the plant Technical Specifications.
The leakage definitions updated for this EAL are consistent with the overall EAL scheme development guidance in NEI 99- 01, Rev. 6. The proposed change maintains the licensees capability to assess, classify, and declare an emergency condition within 15 minutes of the availability of indications. The classification of the event would NOT be different from that approved by the NRC in the site-specific application referenced in Part II. Implementation of the change will maintain the accuracy and timeliness of a classification following an RCS leak. The meaning or intent of the basis of the approved EAL is unchanged.
Proposed change 25 can be made because the change continues to be aligned with approved EAL basis and NEI 99- 01, Rev. 6, EAL scheme.
Proposed change 25 continues to comply with 10 CFR 50.47(b)(4) because the change continues to ensure a standard emergency classification and action level scheme, the basis of which include facility system and effluent parameters, is in use by Harris Nuclear Plant (HNP).
Proposed change 25 continues to comply with 10 CFR Part 50, Appendix E, IV.C.2, because HNP has established and maintains the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level has been exceeded. This change continues to ensure HNP will promptly declare the emergency condition as soon as possible following identification of the appropriate emergency classification level.
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Proposed change 26:
Proposed change is being made to update EAL SU5.1 basis discussion for identified, unidentified, and pressure boundary leakage. Paragraph 6 was originally written based on Harris Nuclear Plant Technical Specifications (TSs) Definitions section 1.1, as referenced at the end of the EAL basis (ref.1). This reference has been updated in Amendment No. 198 to Renewed Facility Operating License No. DPR-63 for the Harris Nuclear Plant, Unit No. 1. The amendment revises the TSs related to reactor coolant system operational leakage and the definition of the term "LEAKAGE" based on Technical Specifications Task Force (TSTF) Traveler TSTF -554, Revision 1, "Revise Reactor Coolant Leakage Requirements."
Paragraph 6 changes:
From:
The first and second EAL conditions are focused on a loss of mass from the RCS due to "unidentified leakage", "pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications). The third condition addresses an RCS mass loss caused by an UNISOLABLE leak through an interfacing system. These conditions thus apply to leakage into the containment, a secondary side system (e.g., steam generator tube leakage) or a location outside of containment.
To:
The first and second EAL conditions are focused on a loss of mass from the RCS due to "unidentified leakage", "pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications). The third condition addresses an RCS mass loss caused by a leak through an interfacing system. These conditions thus apply to leakage into the containment, a secondary side system (e.g., steam generator tube leakage) or a location outside of containment.
Revises the paragraph to remove the term "unisolable" from the discussion of the basis for the third EAL condition.
From NRC Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements," the word "unisolable" has been interpreted inconsistently in the definition of pressure boundary leakage. In some interpretations, it has been considered a means of emphasizing that the leakage fault is in the base material of the pressure boundary and, therefore, the leakage cannot be stopped by adjusting packing or seals. In such a case, the fault represents degradation of the pressure boundary material that could result in a loss of structural integrity. Another interpretation is that leakage through a fault in portions of the pressure boundary that can be separated from the RCS by an isolation device (typically an installed valve) need not be considered as pressure boundary leakage once the isolation device is performing its isolation function.
This would allow certain small sections of the Reactor Coolant Pressure Boundary (RCPB) between the outermost two valves to be removed from consideration as RCPB leakage when the inner valve is closed.
Regardless of the interpretation, deletion of the word "unisolable" does not alter the fundamental meaning that pressure boundary leakage represents degradation that could ultimately result in a loss of structural integrity. Therefore, removing the term "unisolable" brings the discussion into alignment with the revised definition of "pressure boundary leakage" as noted in Proposed Change 3 above.
Proposed change 26 can be made because the change continues to be aligned with approved EAL basis and NEI 99- 01, Rev. 6, EAL scheme.
Proposed change 26 continues to comply with 10 CFR 50.47(b)(4) because the change continues to ensure a standard emergency classification and action level scheme, the basis of which include facility system and effluent parameters, is in use by Harris Nuclear Plant (HNP).
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Proposed change 26 continues to comply with 10 CFR Part 50, Appendix E, IV.C.2, because HNP has established and maintains the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level has been exceeded. This change continues to ensure HNP will promptly declare the emergency condition as soon as possible following identification of the appropriate emergency classification level.
Section XI: Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions Address each function identified in Section IX. Continue to Section XII.
Proposed change 25:
Proposed change is being made to update EAL SU5.1 basis definitions for identified, unidentified, and pressure boundary leakage. Paragraph 2 was originally written based on Harris Nuclear Plant Technical Specifications (TSs) Definitions section 1.1, as referenced at the end of the EAL basis (ref.1). This reference has been updated in Amendment No. 198 to Renewed Facility Operating License No. DPR-63 for the Harris Nuclear Plant, Unit No. 1. The amendment revises the TSs related to reactor coolant system operational leakage and the definition of the term "LEAKAGE" based on Technical Specifications Task Force (TSTF) Traveler TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements."
Paragraph 2, part 1, changes:
From:
Identified Leakage:
- a. Leakage (except controlled leakage) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located or known either not to interfere with the operation of leakage detection systems or not to be pressure boundary leakage, or
- c. RCS leakage through a steam generator to the Secondary Coolant System (primary-to-secondary leakage).
To:
Identified Leakage:
- a. Leakage, such as that from pump seals or valve packing (except controlled leakage), that is captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems, or
- c. RCS leakage through a steam generator to the Secondary Coolant System (primary-to-secondary leakage).
Revises the Identified Leakage definition to not exclude Pressure Boundary Leakage. The change tothe definition of identified leakage applies to leakage from an RCS component that would be released directly into the containment atmosphere, where the leakage would be detectable by the RCS leakage detection systems. The revised definition of identifiedleakage removes the existing exclusion of leakage known to be pressure boundary leakage. Therefore, all RCS leakage that is specifically located and known to not interfere with the operation of leakage detection systems would be considered identified leakage, regardless of the source of leakage. Not excluding Pressure Boundary Leakage provides a clearer definition of identified leakage.
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Paragraph 2, part 2: No changes.
Paragraph 2, part 3, changes:
From:
Pressure Boundary Leakage:
Leakage (except primary-to-secondary leakage) through a non-isolable fault in a RCS component body, pipe wall, or vessel wall.
To:
Pressure Boundary Leakage:
Leakage (except primary-to-secondary leakage) through a fault in a RCS component body, pipe wall, or vessel wall. Leakage past seals, packing, and gaskets is not pressure boundary leakage.
Revises the defined term "leakage" to remove the term "non-isolable" from the definition of Pressure Boundary Leakage and added "Leakage past seals, packing, and gaskets is not pressure boundary leakage".
From NRC Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements," the word "unisolable" [the terms "unisolable" and "non-isolable" are used interchangeably herein] has been interpreted inconsistently in the definition of pressure boundary leakage. In some interpretations, it has been considered a means of emphasizing that the leakage fault is in the base material of the pressure boundary and, therefore, the leakage cannot be stopped by adjusting packing or seals. In such a case, the fault represents degradation of the pressure boundary material that could result in a loss of structural integrity. Another interpretation is that leakage through a fault in portions of the pressure boundary that can be separated from the RCS by an isolation device (typically an installed valve) need not be considered as pressure boundary leakage once the isolation device is performing its isolation function. This would allow certain small sections of the Reactor Coolant Pressure Boundary (RCPB) between the outermost two valves to be removed from consideration as RCPB leakage when the inner valve is closed. Regardless of the interpretation, deletion of the word "unisolable" does not alter the fundamental meaning that pressure boundary leakage represents degradation that could ultimately result in a loss of structural integrity. Therefore, removing the term "unisolable" provides a clearer definition of pressure boundary leakage.
The additional sentence "Leakage past seals, packing, and gaskets is not pressure boundary leakage." is consistent with the definition and was added for emphasis. Definition is clear that pressure boundary leakage is leakage through a fault in an RCS component body, pipe wall, or vessel wall. The additional reminder to exclude leakage from seals, packing, and gaskets which are not RCS component bodies, pipe walls, or vessel walls is an enhancement with no change to the intent of the definition.
The revised second paragraph, part 1, supports the 2nd EAL condition, "RCS identified leakage > 25 gpm for 15 min." and the revised second paragraph, part 3, supports the 1st EAL condition, "RCS unidentified or pressure boundary leakage > 10 gpm for 15 min.". These proposed changes remain consistent with the approved EAL scheme as described in the 6th paragraph of HNP EAL bases:
The first and second EAL conditions are focused on a loss of mass from the RCS due to "unidentified leakage", "pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications).
These proposed changes remain consistent with NEI 99- 01, Rev 6, EAL scheme for this EAL:
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EAL #1 and EAL #2 are focused on a loss of mass from the RCS due to "unidentified leakage",
"pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications).
These proposed changes continue to support the first and second EAL conditions, because the definitions continue to be leakage types that are defined in the plant Technical Specifications.
The leakage definitions updated for this EAL are consistent with the overall EAL scheme development guidance in NEI 99- 01, Rev. 6. The proposed change maintains the licensees capability to assess, classify, and declare an emergency condition within 15 minutes of the availability of indications. The classification of the event would NOT be different from that approved by the NRC in the site-specific application referenced in Part II. Implementation of the change will maintain the accuracy and timeliness of a classification following an RCS leak. The meaning or intent of the basis of the approved EAL is unchanged.
Proposed change 25 can be made because the change continues to be aligned with approved EAL basis and NEI 99- 01, Rev. 6, EAL scheme.
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Proposed change 26:
Proposed change is being made to update EAL SU5.1 basis discussion for identified, unidentified, and pressure boundary leakage. Paragraph 6 was originally written based on Harris Nuclear Plant Technical Specifications (TSs) Definitions section 1.1, as referenced at the end of the EAL basis (ref.1). This reference has been updated in Amendment No. 198 to Renewed Facility Operating License No. DPR-63 for the Harris Nuclear Plant, Unit No. 1. The amendment revises the TSs related to reactor coolant system operational leakage and the definition of the term "LEAKAGE" based on Technical Specifications Task Force (TSTF) Traveler TSTF -554, Revision 1, "Revise Reactor Coolant Leakage Requirements."
Paragraph 6 changes:
From:
The first and second EAL conditions are focused on a loss of mass from the RCS due to "unidentified leakage", "pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications). The third condition addresses an RCS mass loss caused by an UNISOLABLE leak through an interfacing system. These conditions thus apply to leakage into the containment, a secondary side system (e.g., steam generator tube leakage) or a location outside of containment.
To:
The first and second EAL conditions are focused on a loss of mass from the RCS due to "unidentified leakage", "pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications). The third condition addresses an RCS mass loss caused by a leak through an interfacing system. These conditions thus apply to leakage into the containment, a secondary side system (e.g., steam generator tube leakage) or a location outside of containment.
Revises the paragraph to remove the term "unisolable" from the discussion of the basis for the third EAL condition.
From NRC Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements," the word "unisolable" has been interpreted inconsistently in the definition of pressure boundary leakage. In some interpretations, it has been considered a means of emphasizing that the leakage fault is in the base material of the pressure boundary and, therefore, the leakage cannot be stopped by adjusting packing or seals. In such a case, the fault represents degradation of the pressure boundary material that could result in a loss of structural integrity. Another interpretation is that leakage through a fault in portions of the pressure boundary that can be separated from the RCS by an isolation device (typically an installed valve) need not be considered as pressure boundary leakage once the isolation device is performing its isolation function.
This would allow certain small sections of the Reactor Coolant Pressure Boundary (RCPB) between the outermost two valves to be removed from consideration as RCPB leakage when the inner valve is closed.
Regardless of the interpretation, deletion of the word "unisolable" does not alter the fundamental meaning that pressure boundary leakage represents degradation that could ultimately result in a loss of structural integrity. Therefore, removing the term "unisolable" brings the discussion into alignment with the revised definition of "pressure boundary leakage" as noted in Proposed Change 3 above.
Proposed change 26 can be made because the change continues to be aligned with approved EAL basis and NEI 99- 01, Rev. 6, EAL scheme.
The proposed changes can be made because the changes continue to ensure a standard scheme of emergency classification and action levels are in use and there is no negative impact to timeliness or accuracy.
The proposed changes do not reduce the effectiveness of the Harris Nuclear Plant Emergency Plan. The change continues to provide assurance that the Emergency Response Organization has the ability and capability to:
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- 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.
The change continues to meet NRC requirements, as described in 10 CFR 50.47(b)(4) and 10 CFR 50, Appendix E as well as the requirements of the Harris Nuclear Plant Emergency Plan as written and approved.
Section XII: 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 reduction in Yes effectiveness)? No
- 3. Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No Section XII: Conclusion Questions 1, 2 and 3 are answered YES, complete step below to create a General CAS assignment, and then continue on to Section XIV and implement change(s).
General CAS assignment created-Licensing submit changes in accordance with 10 CFR I 50.4(b)(5)(ii) within 30 days of change implementation Questions 1 or 2 or 3 are answered NO, complete Sections XIII and Section XIV.
Section XIII: Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change be submitted to the NRC for prior approval?
Yes If No, reject the proposed change, or modify the proposed change and perform a new evaluation. No Continue to Section XIV for this evaluation.
If YES, 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:___________________________________. Complete Section XIV.
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Section XIV: Signatures:
EP CFAM Final Approval is required for changes affecting Program Element 4a of Section VIII. 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.Section XIV as applicable.
Preparer Name (Print): Preparer Signature: Date:
David Bell See NAS See NAS Reviewer Name (Print): Reviewer Signature: Date:
Sarah McDaniel See NAS See NAS Approver Name (Print): Approver Signature: Date:
William Gunter See NAS See NAS Approver (EP CFAM, as required) Name (Print): Approver Signature: Date:
David Thompson See NAS See NAS
QA RECORD
- Old Section 5.1
5.0 DEF INIT IO NS, ACRO N YMS & ABBRE VI ATIONS 5.1 Defi nitions (ref. 4.1.1 except as noted)
Selected terms used in Initiating Condition and Emergency Action Level st atements are set in an ca pital letters meanings as used in this documen(e.g., ALL CAPS}. t. These Toe definitions of these words are defined terms that have specific t erms are provided below.
Alert degradaEvents are in progress, or have occurredtion of the level of saf ety of the plant or a security event that involves probable l ife, which involve an actual or potential substantial
threaten ing risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be small fractions of th e EPA Protective Action Guide li ne exposure levels.
Contain ment Clos ure The procedurally defined actions t aken to secure containment and its associated structures,
systems, and components as a functional barrier to fission product release under shutdown conditions.
As ap plied to HNP, Containment Closure is est ab li shed when containment penetration dosure is estab li shed in accordance with Teehnical Specifications 3/ 4.9.4 (ref. 4.1.8).
Emergenc y Action Lev el ( EAL)
A pre-determined, site-specif ic, observable threshold for an Initiating Condition that, When met or exceeded, places the plan t in a given emergency classification level.
Emergency Classificat ion Lev el (ECL)
One of a set of names or titles established by the US Nuclear Regulatory Commission (NRC}
for grouping off-normal events or conditions according to (1) potential or actual effects or consequences, and (2) resulting onsit e and offsit e response actions. Toe emergency classification levels, in ascending order of severity, are:
- Unusual Event (U E}
- Alert
- Sit e Area Emergency (SAE)
- General Emergency (G E)
EPA PAGs Environment Protection Agency Protective Action Gu idelines. The EPA PAGs are expressed in t erms of dose commitment: 1 Rem TED E or 5 Rem COE Thyroid. Actual or proj ected offsite exposures in excess of the EPA PAGs requires HNP to recommend protective actions fo r the general pu blic to offsite planning agencies.
Explosi on A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical an electricareaction or overpressurizati on. A release of steam (from high energy l component fail ure (caused by short circu its, grounding, arcing, etc.) should not lines or components) or
automatica lly be considered an explosion. Such events require a post-event inspection to determine if the attributes of an explosion are present.
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- Old Section 5.1
Faulted The teITTI ap pl ied to a steam generator that has a steam leak on the secondary side of sufficient siZe to cause an uncontroll ed drop in steam generator pressure or the steam generator to become completely de pressurized.
Fire Combust ion characterized by heat and l ight. Sources of smoke sueh as sl ipp ing drive be lts or overheated electrical equipment do not constit ute fires. Observation of fl ame is preferred but is NOT required if large quant ities of smoke and heat are observed.
Fission Product Barrier Threshol d A pre-deteITTiined, site-specif ic, observable threshold indicating the loss or potent ial loss of a fi ssion product barrie r.
Flooding A cond rtion where water is entering a room or area f aster than installed equipment is capable of removal, resulti ng in a rise of water level within the room or area.
General Eme rgency Events are in prog ress or have occurred wh ieh involve a ctual or imminent substantial core degradation or melt ing with potential for loss of containment integrity or hostile actions result in an a ctual loss of physical contro l of the f acility. Releases can be reasonably expected that
to exceed EPA Protective Action Guide li ne exposure levels offsite for more than the i mmediate s ite area.
Hostage A person(s) he ld as leverage aga inst the station to ensure that demands will be met by the station.
Host il e Act ion An act toward HNP or its personnel that includes the use of violent force to destroy equipment, t ake hostages, and/or intimidate the licensee to aehieve an end. Th is includes attac k by air, land, or wat er using guns, explosives, proj ectiles, vehicles, or other devices used to del ive r destructive force. Other acts that satisfy the overall intent may be included. Hostile action should not be construed to inc lude acts of civil disobedience or f elon ious acts that are not part of a concerted attack on HNP. Non-terrorism-based EALs should be used to address such a ctivit ies (i. e., th is may include violent acts between individuals in the owner controlled area).
Hostil e Force One or mo re individua ls who are engaged in a deteITTiined assault, overtly or by stealth and deception, equipped with su it ab le weapons capable of killing, maimi ng, or causing destruction.
Imminent The traj ectory of events or conditions i s such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.
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- Old Section 5.1
lmpe de (d )
Personnel access to a room or area is hindered to an extent that extraord inary measures are necessary to fac ilit ate entry of personnel into the affected room/area (e.g., req uiring use of protective equipment, s uch as SCBAs, that is not routinely em ployed ).
Init iatin g Conditi o n (I C )
An event or condition that ali gns with the definition of one of the four emergency classifi cation levels by virtue of the potential or actua l effects or consequences.
Ma int ain Ta ke appropriate action to hold the value of an ide ntif ied parameter within specifi ed limits.
N orma l Lev e l s As appl ied to radiolog ical IC/EALs, the highest read ing in the past twenty-four hours ex clUding the current peak value.
Owner C o nt roll ed Area Th at area surround ing the Protected Area beyond Which HNP exercises access control.
Project il e An obj ect d irected toward a Nuclear Power Plant that co uld cause co ncern for its co ntinued operability, reliability, or personnel safety.
Protected Area An area Wh ich normally encompasses all controlled areas within the security protected area f ence as depicted in 5-G-0003, Site Plan (ref. 4. 1.6).
RCS Intact The RCS should be co nsidered int act when the RCS pressure boundary is in its normal condition for the co ld sh utdown mode of operation (e.g., no freeze seals or noZZle dams).
Refue li ng Pathway The reactopathway. r refueling cavity, s pent fuel pool and fuel transf er canal comprise the ref ueling
Reduced Invento ry RCS water level greater than 36 inches below the Reactor Vessel Flang e (ref. 4.1.12).
Ruptured The co ndit ion of a steam generator in Which prima ry-to-seconda ry leakage is of s ufficien t magnit ude to req uire a safety inj ection.
Res tore Ta ke the appropriat e action required to return the value of an ide ntifi ed parameter to the appli cable l imits
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- Old Section 5.1
Saf ety Sys t e m A system req uired for safe plant operation, cooling down the plant and/ or placing it in the co ld s hutdown co ndit ion, including the ECCS. These are typically systems classified as safety-related (as def ined in 10CFR50.2):
Those structures, systems and components that are relied upon to remain f unctional during and foll oWing design basis events to assure :
( 1) The integ rity of the reactor coolan t pressure bou nda ry; (2) The ca pability to shut down the reactor and maintain it in a safe shut down condrtion; (3) The capability to prevent or mitigate the consequences of accidents whi ch could result in potential offsite exposures.
Securit y C onditi o n Any security event as list ed in the approved security co ntingency plan that constitut es a threat/compr om ise to site securi ty, threat/ri sk to site personnel, or a potential degradat ion to the level of safety of the plant. A security condition does not involve a hostil e action.
Sit e Area Eme rge ncy Events are in prog ress or have occurred wh ieh involve actual or l ike ly maj or failures of plant f unctions needed for protection of the publi c or HOSTILE AC TION that results i n intentional damage or malicious acts ; 1) toward sit e personnel or equipment that could lead to the likely f ailu re of or. 2) that prevent effective access to, eq uipment needed for the protect ion of the pub li c. Any releases are not expected to result in exposu re levels wh ieh exceed EPA PAG exposure levels beyond the SITE BOUNDARY.
Sit e B ounda ry A cirde of ap proximately 2500 ft. radius from the cen ter of the co ntainment build ing (0.47 mil es)
(ref. 4. 1.13).
The rm a lly Ind uce d Curr e nt (T IC ) re l ate d to Conta inme nt H igh Ra n ge R adiati o n Mo nito rs (C HRRM) (Note 9)
A large, rapid temperature change in co ntainment can create a bri ef, sp urious electrical s ignal with in CHRRM instrumentation cables, ca using inaccurate radiat ion readings. A false-high reading ca n occur When co ntainment temperature is rapidly increased, and a false low reading can occur during rapid temperature decreases. The effect subsides When temperatures stab ilize. A false high signal can occur when there is a Loss of Coolant Accident or Mai n Steam Li ne Break With little actual dose consequence. As a result, accident co ndit ions with low rad ia tio n co nseque n ces may r esu lt i n h igh CHRRM read ings. Note : CHRRM read ings are expected to drop below 130 R/hr in approximately four minutes.
Negative Thermally Induced Current is a false low signal induced at the Containment High Range Radiat ion Mo nitors (CHRRMs) caused by rapidly decreasing containment t emperatures. The signal ca n ca use the CHRRMs to receive a 'no pulse
- alarm due to readings f all ing be low the detector's dose rat e idli ng signal. This co ndition could occur in a period following a large energy re lease (i. e. LOCA or MSLB) with low radiat ion levels (i. e. l ittle to no f ue l damage). If f uel damage radiati on levels. occurs, the CHRRMs Will disp lay the associated inc rease in
I CSD-EP-HN P-0 10 1-0 1 Rev. 003 Page 22 of 238 1
- Old Section 5.1
Unisol ab le An open or breached system line that cannot be isolated, remotely or locally.
Unp la nned expected A parameteplan t response to a transient. The cause of r change or an event that is not 1) the result of an intended the parameter Change or event evolution or 2) an may be
known or unknown.
Unusual Event Even ts are in prog ress or have occurred wh ieh ind icate a potential degradat ion of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless f urthe r degradation of SAFETY SYSTE MS occurs.
Vali d An ind icati on, report, or cond it ion, is considered to be valid When it is verif ied by (1) an instrument channel check, or (2) ind icati ons on relat ed or redundant ind icators, or (3 ) by direct observation by plant personnel, such that doubt related to the ind icator's operability, the cond ition 's existence, or the report's accuracy is removed. Imp li cit in th is definition is the need for timely assessment.
Visible Damage Damage to a SAFETY SYSTEM train that is readily observable wit hout measurements, t esting, or analysis. The visual impact of the damage is sufficien t to cause concern regarding the operabil ity or rel iab ility of the affected SAFETY SYSTEM train.
I CSD-EP-HNP-0 10 1-0 1 Rev. 003 Page 23 of 238 1
- New Section 5.1
5.0 DEF INIT IONS, ACRONYMS & ABBREV I ATIONS 5.1. Defi ni ti on s (ref. 4.1.1 ex cept as noted)
Se lected te11ns used in Init iating Condit ion and Eme rgency Act ion Level statements are set in all capit al letters (e.g., ALL CAPS). These wo rds are defined terms that have specific meanings as used in th is document. The definitions of these terms are proVided below.
- 1. Alert -Events are in prog ress, or have occurred. Which involve an actua l or potential substant ial degradation of the level of safety of th e plant or a security event that involves probable li fe threatening risK to site personnel or damage to s ite equipment because of hostile action. Any releases are expected to be small f ractions of the EPA Protective Action Gu ideline exposure levels.
- 2. Co nt ai nment Closure -The procedurally defined actions taken to secure containment and its associated structures. systems. and components as a functional barrier to fission product release under shutdown conditions.
As appl ied to HNP. Containment Closure is established when containment penetration dosure is esta bl ished in accordance with Technical Specifications 3/4.9.4 (ref. 4.1.8).
- 3. Emergency Action Lev el (EAL) - A pre-dete11nined, site-specific.
observable threshold for an Initiating Condit ion that, When met or exceeded, places the plant in a given emergency classification level.
- 4. Emerge ncy Classificatio n Level (ECL) -One of a set of names or titles estab li shed by the US Nuclear Regulatory Commission (NRC) for grou ping off-no11na1 events or condit ions according to (1) poten tial or actua l effects or consequences. and (2) result ing onsit e and offsit e response actions. The emergency classif ication levels, in ascend ing order of severity. are :
- Unusual Event (U E)
- Alert
- Site Area Emergency (SAE)
- General Emergency (G E)
- 5. EPA PAGs -Environment Prot ection Agency Prot ective Action Guide li nes. The EPA PAGs a re expressed in terms of dose commitment:
1 Rem TEDE or 5 Rem CD E Thyroid. Actual or proj ected offsite exposures in excess of the EPA PAGs requires HNP to recommend protective actions for the general publi c to offsit e plan ning agencies.
- 6. Explosion -A rapid, violent and catastro phic fail ure of a piece of equ ipment due to combustion, chemica l reaction or overpressurization. A release of steam (f rom high energy l ines or components) or an electrica l component f ailu re (caused by short circu it s, grounding, arcing, etc.)
should not automatically be considered an explos ion. Such events requ ire a post-event inspection to dete11nine if the attributes of an explosion are present.
I CSD-E P-HNP-0 10 1-0 1 Rev. 004 (D RAFT) Page 20 of 235 1
- New Section 5.1
5.1 Defini tions (continued)
- 7. Fa u lted - The tenn app li ed to a steam generator that has a steam leak on the secondary side of sufficient size to cause an uncontrolled drop in st eam generator pressure or the steam generator to become completely depressurized.
- 8. F ire - Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constit ute fires. Observation of fl ame is preferred but is NOT required if large qu antit ies of smoke and heat are observed.
- 9. F iss ion Prod uct Barr ier Threshold - A pre-<letennined, site-specific, observable threshold ind icating the loss or potential loss of a fission product barrier.
10. F lood ing - A condition where water is entering a room or area faster than install ed equipment is capable of removal, result ing in a rise of water level within the room or a rea.
- 11. Ge neral Emergency - Events are in progress or have occurred Which involve a ctual or imm inent substantial core degradation or melting With potential for loss of con tainment integrity or hostile a ctions that result in an actua l loss of physica l control of the facility. Re leases can be reasonably expected to exceed EPA Protective Action Gu idel ine exposure levels offsite for more than the immediate sit e area.
12. Hostage - A person(s) held as leverage ag ainst the stat ion to ensure that demands will be met by the station.
13. Hostil e Acti on - An act towarof violen t force to destroy equipment, t ake hostages, and/or intimidate the d HNP or its personnel that indudes the use
licensee to achieve an end. Th is includes attack by air, land, or water us ing guns. explOsives, projectiles, vehicles, or othe r deVices used to del iver destructive force. Ot her a cts that satisfy the overall intent may be inc luded. Hostile action should not be construed to include a cts of civil disobedience or felon ious acts that are not part of a concerted attack on HNP. Non-terrorism-based EALs should be used to add ress sueh activities (i. e., this may include violen t a cts between ind ividu als in the owner controlled area).
14. Hostil e Fo rce - One or more ind ividuals who are engaged in a determined assault, overtly or by stea lth and deception, equipped with su itab le weapons capable of killing, maiming, or causing destruction.
- 15. Imminent - The traj ectory of events or conditi ons is such that an EAL will be met within a relatively short period of time regardless of mit igation or co rrective actions.
I CS D-EP-HNP-0 10 1-0 1 Rev. 004 (DRAFT) Page 2 1 of 235 1
- New Section 5.1
5.1 Defini tions (continued)
- 16. lmpede( d) -Personnel access to a room or area is hindered to an extent that extraordinary measu res are necessary to facil rtat e entry of personnel into the affected room/area (e.g., requiring use of protective equipment, such as SCBAs, that is not routinely employed).
- 17. In itiat ing Co nd ition (I C) -An event or condition that aligns with the definit ion of one of the fou r emergency classif ication levels by virtue of the potential or a ctual effects or consequences.
18. Mainta in - Take approp riate action to hold the value of an identifi ed parameter wrthin specifi ed l imits.
19. No rma l Le v els - As appli ed to radiolog ica l IC/ EALs, the highest reading in the past twenty-four hours exduding the current peak va lue.
- 20. Ow ne r Contro ll e d Area -Th at area surrounding the Protected Area beyond Wh ieh HNP exercises access control.
2 1. Pr oj ectile - An obj ect directed toward a Nuclea r Power Pl ant that could cause concern fo r its continued operability, reliabilrty, or personnel safety.
- 22. Pr otected Are a -An area Wh ich normally encompasses an controll ed areas with in the security protected area fence as depicted in 5-G-0003,
Sit e Plan (ref. 4.1.6).
- 23. R CS Int ac t -The RCS should be consid ered intact When the RCS pressure bo undary is in rts normal condition for the co ld sh utdown mode of operation (e.g., no freeze seals or nozzle dams).
- 24. Refueli ng Pathway -The reactor refuel ing cavity, spent fuel pool and fuel transfer canal compri se the refueli ng pathway.
- 25. Red uced Inv ento ry -RCS water level great er than 36 inches below the Rea ctor Vessel Flange (ref. 4.1.12).
- 26. Ru ptu red primary-to-secondary -The condrtio n lea kage is of sufficof a st eam generaient magn itude to require a saf ety tor in which
inj ection.
- 27. Rest ore - Take the ap propriate a ction required to return the val ue of an identified parameter to the appl ica ble li mrts
I CSD-EP-HNP-0 10 1-0 1 Rev. 004 (DRAFT) Page 22 of 235 1
- New Section 5.1
5.1 Defi ni ti ons (continued)
- 28. Safety System - A system req uired for safe plant operation, cool ing down the plant and/or placing it in the cold shutdown condition, includ ing the ECCS. These are typically systems d assif ied as saf ety-related (as defined in 10C FR50.2):
Those structures, sy stems and components that are reli ed upon to remain functional during and following design basis events to assure:
(1) The integ rity of the reactor coolant pressure boundary ;
(2) The capa bility to shut down the reactor and maintain it in a saf e sh utdown condition; (3) The capa bility to prevent or mitig ate the consequences of accidents which could result in pot ent ial offsite exposures.
- 29. Security Cond it ion - Any security event as l isted in the ap proved securi ty contingency plan that constitut es a threaVcompromise to sit e securi ty,
threaVrisk to site pe rsonnel, or a poten tial degradation to the level of safety of the plant. A security condit ion does not involve a hostile a ction.
30. Site Area Emergency - Events are in prog ress or have occurred Wh ich involve a ctual or likely major failures of plant functions needed for protection of the publ ic or HOSTILE ACTION that results in inten tional damage or ma li cious acts ; 1) toward site personnel or equipment that could lead to the li kely f ailure of or; 2) that prevent effective access to, equipment needed for the protection of the pu bl ic. Any re leases are not ex pected to result in exposure levels Which exceed EPA PAG exposure levels beyond the SITE BOUNDARY.
- 31. Site Boundary - A circle of app roximately 2500 ft. radius from the center of the containment bu ild ing (0.47 miles ) (ref. 4.1.13).
I CS D-EP-HNP-0 10 1-0 1 Rev. 004 (DRAFT) Page 23 of 235 1
- New Section 5.1
5.1 Defi niti ons (conti nued)
32. Th ermally Ind uced Curren t (TI C) related t o Contai nment Hig h Ran ge Radi ation Mon it ors (CHRRM) (Not e 9) - A large, rapid temperature Change in containment can create a brief, spurious electrical signal within CHRRM instrumentation cables, causing inaccurate radiation reading s. A false-high reading can occur When con tainment temperature is rapidly inc reased, and a false low reading can occur during rapid temperature decreases. The effect subsides When te mperatures st abilize. A false high signal can occur When th ere is a Loss of Coolant Accident or Main St eam Li ne Break with little actual dose consequence. As a result, accident condit ions with low radiation consequences may res ult in high CHRRM reaeling s. Note: CHRRM rea dings are expected to drop below 130 R/hr in approximate ly four minutes.
Negative Thermally Induced Current is a false low signal induced at the Containm ent High Range Radiation Monitors (CHRRMs) caused by rapidly decreasing containment temperatures. The signal can cause the CHRRMs to receive a 'no pulse' alarm due to readings falling below the detector's dose rate idling signal. Th is condit ion could occur in a period foll owing a la rge energy release (i. e. LOCA or MSLB) with low rad iation levels (i. e. little to no f ue l damage ). If fuel damage occurs, the CHRRMs will disp lay the associated increase in radiation levels.
33. Unisolable remotely or locally. -An open or breaehed system li ne that cannot be isolated,
34. Unplanned - A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transien t.
The cause of the parameter change or event may be known or unknown.
35. Unusual Event -Events are in prog ress or have occurred Wh ich ind icate a potent ial degradation of the level of safety of th e plant or ind icat e a security threat to fac ility protection has been init iated. No releases of radioactive material requiring offsit e response or monitoring are expected unless further degradation of SAFETY SYSTEMS occurs.
36. Val id - An indication, report, or condition, is considered to be va li d When it is verif ied by ( 1) an instrument channel check, or (2) ind ications on related or redundant indicators, or (3) by d irect observation by plan t personnel, such that do ubt related to the ind icator's operability, the condit ion's ex istence, or the report's accuracy is removed. Implicit in th is definition is the need for timely assessment.
37. Visible Damage observable without measurements-Damage to a SA FETY SYSTEM, testing, or analysis. Th e visu al impact train that is readily of the damage is sufficient to cause concern regard ing the operability or rel iab ility of the affected SA FETY SYSTEM train.
I CSD-E P-HNP-0 10 1-0 1 Rev. 004 (D RAFT) Page 24 of 235 1
- Old Section 5.2
5.2 Ab breviat ions/Acronyms OF.............. Degrees Fahrenheit
- ......................... Degrees AC.............. Alt ernat ing Current AP......... Abnormal Operating Procedure ATWS....... An ticipated Transien t Without Scram CO E........... Committ ed Dose Equivalent CFR......... Code of Federal Regulations CHRRM............... Containment High Range Radiat ion Monitors CS FST......... Critical Safety Function St atus Tree OBA................... Design Basis Accident DC................................... Direct Current EAL................. Emergency Action Level EC................... Emergency Coordinator ECCS............. Emergency Core Cooli ng System ECL.................. Emergency Classificat ion Level EOF...... Emergency Operati ons Facil ity EOP................ Emergency Operating Procedure EPA............... Environment al Protect ion Agency ERG................. Emergency Response Gu ideline EPIP............. Emergency P lan Implementing Procedure ESF............ Eng ineered Safety Feature FAA.............................. Federal Aviat ion Administrati on FBI................................ Federal Bu reau of Investigation FEMA............. Federal Emergency Management Agency FSAR........ Final Safety Analys is Report GE........... General Emergency HNP........... Harris Nuclear Plant IC............... Init iating Condrti on IPEEE.... Ind ividual Plant Examination of External Events (Generic Letter 88-20)
ISFSI......... Inde pendent Spent Fuel storage Install ation K.ff......... Effective Neutron Mu ltiplication Factor LCO...... Limiting Conditi on of Operation LER................... Licensee Event Report LOCA............. Loss of Coolant Accident LWR...................... Light Water Reactor MPC......... Maximum Permissible Concentrati on/Multi -Purpose Canister MSIV.......... Main Steam Iso lation Valve MSL............................ Main steam Line mR, mRem, m rem, mR EM... mi Iii-Roentgen Equiva lent Man I CSO-EP-HNP-0 10 1-0 1 Rev. 003 Page 24 of 238 1
- Old Section 5.2
MW....................................... Megawatt RCS................ Reactor Coolant System NEI.................. Nu dear Energy Inst itute NESP................ National Environmental stud ies Proj ect NPP.................................. Nuclear Power Plant NRC............................. Nuclear Regulatory Commission NSSS................. Nuclear St eam Su pply System NORAD............. North American Ae rospace Defense Command (NO)UE................. Notif icati on of Unusual Event OB E...................... Operati ng Basis Earthquake OCA............................... Owner Controlled Area ODCM............. Off-site Dose Calcu lation Manual ORO.................. Off site Response Organizati on PA................................. Protected Area PAG............ Protective Action Gu ideline PRA/PSA......... Probabilistic Risk Assessment / Probab ilistic Safety Assessment PWR........... Pressurized Water Reactor PSIG................ Pounds per Squa re Inch Gauge R............................................ Roentgen RAB.......................... Reactor Auxiliary Build ing Rem, rem, REM........ Roentgen Equiva len t Man RETS................... Radiolog ical Effluent Techni cal Specif ications RPS............ Reactor Protection System RV................................. Reactor Vessel RVLI S.............. Reactor Vessel Level Ind icating System SAR............................... Saf ety Analys is Report SBGTS.......... Stand-By Gas Treatment Sy st em SBO................ Stat ion Blac kout SC BA....... Self -Contained Breath ing Ap paratus SG.................. St eam Generator SI.................................. Saf ety Inj ection SLC................. Se lected Li censee Commit ment SPDS............ Safety Parameter Display System SRO............................ Senior Reactor Operator SSF............................... Saf e Shutdown Fac ility TEDE................ Total Effective Dose Equivalent TIC.............. Thenmally Induced Current TOAF........... Top of Active Fuel TSC............. Teehnica l Support Center WOG.................... Westinghouse owners Group I CSD-EP-HNP-0 10 1-0 1 Rev. 003 Page 25 of 238 1
- New Section 5.2
5.2. Abb reviations/Acronyms
- F Degrees Fahrenhett
0 Degrees AC ALTERNATING CURRENT AOP Ab normal Operating Procedure AT-NS Anticipated Transient Without Scram COE Committed Dose Equ ivalent CFR Code of Federal Regulations CSFST Cmical Safety Function Status Tree OBA Design Basis Accident DC DI RECT CURRENT EAL Emergency Action Level EC EMERGENCY COORD INATOR ECCS Emergency Core Cooling System ECL Emergency aass ification Level EOF Emergency Operations Facility EOP Emergency Operating Procedure EPA Environmental Protection Agency ERG Emergency Response Guideli ne EPIP Emergency Plan Implementing Procedure ESF Engineered Safety Feature FAA Federal Aviation Administration FBI Federal Bureau of Investigation FEMA Federal Emergency Manageme nt Agency GE GE NERAL EMERGENCY IC INITIATI NG CO NDITION IPEEE Ind ividual Plant Examination of External Events (Generic Letter 88-20)
ISFSI Independent Spent Fuel Storage Installation Ke. Effective Neutron Mu ltiplication Factor LCO Limning Condition of Operation LER Licensee Event Report LOCA Loss of Coolant Accident LWR Light Water Reactor MPC Maximum Permissible Concentration/Multi-Purpose Can ister MSIV Main Steam Isolation Valve MS L Main Steam Line mR, mRe m, mrem, milli-Roentgen Eq uivalent Man mREM I CSD-E P-HNP -0 10 1-0 1 Rev. 004 (DRAFT ) Page 25 of 235 1
- New Section 5.2
5.2 Abb reviation s/A cronyms ( cont inued )
MW MEGAWATT RCS Reactor Coolant System NEI Nuclear Energy Institute NESP National Environ mental Studies Project NPP Nuclear Power Plant NRG Nuclear Regulatory Commission NSSS Nuclear Steam Sup ply System NORAD North American Aerospace Defense Command (NO)UE Notification of Unusual Event OBE Operating Basis Earthquake OCA Owner Controlled Area ODCM Off-sne Dose Calculation Manual ORO Offsne Response Organization PA PROTECTED AREA PAG Protective Action Guideline PRA/PSA Probabil isti c Risk Assessment / Probabil istic Safety Assessment PWR Pressurized Wate r Reactor PSIG Pounds pe r Sq uar e Inch Gauge R ROENTGE N Rem, rem, REM Roentgen Equ ivalent Man RETS Radiological Effluent Technical Specifications RN P Robinson Nuclear Plant RPS Reactor Protection System RPV Reactor Pr essure Vessel RV REACTOR VESSEL RVLIS Reactor Vessel Level Indicating System SAR Safety Analysis Report SBGTS Stand-By Gas Treatment System SBO Station Blackout SCBA Self-Contained Breathing Appar atus SG STEAM GE NERATOR SI SAFETY INJECTION SLC Sel ected Licensee Commnment SPDS Safety Parameter Display System SRO Se nior Reactor Operator SSF Safe Shutdown Facility I CSD-EP-HNP -0 101 -01 Rev. 004 (DRAFT ) Page 26 of 235 1
- New Section 5.2
5.2 Abbreviations/Acronyms ( cont inued)
TEDE Total E ffective Dose Equival ent TOAF Top of Active Fuel TSC Technical Support Cente<
UFSAR Updated Final Safety Analysis Report WOG Westinghouse Owners Group
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
Attachment 2
Page 1 of 23 10 CFR 50.54(q) Review Form
Section I: 10 CFR 50.54(q) Review Number: (EREG #): I 02503175 2478380 Applicable Sites and Applicability Determination # (5AD)
BNP I I I I I CNS HNP 02497822
MNS I I I I I ONS RNP Document #, EC #, Revision # or or N/A N/A Document or Activity Title EP-HNP-OSSA 001 Harris On-Shift Staffing Analysis
Section II: Identify/Describe All Proposed Activities/Changes 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 (Use attachments, or continue additional pages as necessary): Continue to Section III.
This is a revised 50.54(q) review. Changes to the original 50.54(q) review can be identified by:
- Additions to this revised 50.54(q) review will appear in Bold and Italicized format.
- Deletions to this revised 50.54q) review will appear in struck through format.
EP-HNP-OSSA, Harris On-Shift Staffing Analysis, provides the on shift staffing analysis regulatory basis and guidance, the staffing compliment used in the analysis, the events and tasks used during the analysis, applicable time motion studies and the analysis results for Harris Nuclear Plant. Revision 1 of EP -HNP-OSSA incorporates various updates to on-shift personnel requirements and tasks performed by the Chemistry Technician, Mechanic, and I&C Technician.
A description of each proposed change made in Revision 1 is shown in the table below.
Change # Section or Step # Changed From Changed To
1 Revision Old revision summary Updated revision Summary summary identifying the changes made in Revision 1
2 Throughout EP-HNP-OSSA: Old EP-HNP-OSSA: New revision number (000) revision number (001)
3 Section 3.4 Chemistry Technician, Removed Chemistry Mechanic, and I&C Technician, Mechanic, EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
Attachment 2
Page 2 of 23 10 CFR 50.54(q) Review Form
Change # Section or Step # Changed From Changed To
Technician were and I&C Technician from included in the bulleted the bulleted list of on-shift list of on-shift personnel personnel and their and their respective respective locations locations
4 Attachment 2, Table Line 15 Chemistry Removed line 15 1 - On-Shift Technician (CT), line 16 Chemistry Technician Positions, Analysis Mechanic (MT), and (CT), line 16 Mechanic Event # 1 - Main line 17 I&C Technician (MT), and line 17 I&C Steam Line Break (ICT) were included in Technician (ICT) from (MSLB) Table 1 with no tasks Table 1 with no tasks assigned assigned
5 Attachment 2, Table Table 2 included a Removed Other (non -
2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 that Analysis Event # 1 - that included the removed the Mechanic Main Steam Line Mechanic (MT) under (MT) and I&C Technician Break (MSLB) line 16 and I&C (ICT) with no tasks Technician (ICT) under assigned line 17 with no tasks assigned
6 Attachment 2, Line 12 contained an Line 12 contains an Analysis Event #3-action to Dispatch CT action to Dispatch CT or Reactor Coolant to perform samples per RPT2 to perform samples Pump Rotor Seizure step 1 per step 1 Tasks and Timing Line 13 action to Line 13 action to Sample Sample per AOP-32 per AOP-32 step 1 is step 1 was assigned to assigned to the RPT2.
the CT.
Previous action for the Line 45 contained an ICT to Check pressure action for the ICT to switches for MFP Check pressure reset/Drain Pumps is switches for MFP removed.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
Attachment 2
Page 3 of 23 10 CFR 50.54(q) Review Form
Change # Section or Step # Changed From Changed To
reset/Drain Pumps Previous action for the MT to Station at Turbine Line 48 contained an coastdown/ensure proper action for the MT to turning gear ops is Station at Turbine removed.
coastdown/ensure proper turning gear ops
7 Attachment 2, Table Attachment 2, Table 1 Attachment 2, Table 1 1-On-Shift Positions, contained lines for the does not include lines for Analysis Event #3-Chemistry Technician the Chemistry Technician Reactor Coolant (CT) under line 15 with (CT), Mechanic (MT),
Pump Rotor Seizure 4/8 role in Table # / and I&C Technician (ICT)
Line # column, Mechanic (MT) under line 16 with 2/16 role in Attachment 2, Table 1, Table # / Line # column, line 14 for RP Qualified and I&C Technician Individual (RPT2) has (ICT) under line 17 with 4/1 and 4/8 roles in 2/17 role in Table # / Table # / Line # column Line # column
Attachment 2, Table 1, line 14 for RP Qualified Individual (RPT2) had 4/1 role in Table # /
Line # column
8 Attachment 2, Table Table 2 included a Removed Other (non-2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 that Analysis Event # 3 - that included the removed the Mechanic Reactor Coolant Mechanic (MT) that (MT) that performed the Pump Rotor Seizure performed the Turbine Turbine Coastdown Coastdown Monitoring Monitoring task and I&C task under line 16 and Technician (ICT) that I&C Technician (ICT) performed the Check that performed the Pressure Switches task Check Pressure EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
Attachment 2
Page 4 of 23 10 CFR 50.54(q) Review Form
Change # Section or Step # Changed From Changed To
Switches task under line 17
9 Attachment 2, Table Task 8 to Sample RCS Task 8 to Sample RCS 4 - Radiation was performed by the was revised to be Protection and CT performed by the RPT2 Chemistry Analysis Event # 3 - Reactor Coolant Pump Rotor Seizure
10 Attachment 2, Line 38 contained an The action for the RPT1 to Analysis Event #6-action for the RPT1 to Notify CT for sampling Steam Generator Notify CT for sampling CVPET is removed Tube Rupture CVPET (SGTR) Tasks and The action for the CT to Timing Line 42 contained an Sample CVPET is action for the CT to removed Sample CVPET
11 Attachment 2, Table Attachment 2, Table 1 Attachment 2, Table 1 1 - On-Shift contained lines for the does not include lines for Positions, Analysis Chemistry Technician the Chemistry Technician Event #6-Steam (CT) under line 15 with (CT), Mechanic (MT),
Generator Tube a role in Table # /Line # and I&C Technician Rupture (SGTR) column as 4/8, (ICT). The CT task was Mechanic (MT) under removed with this line 16 with no tasks, change.
and I&C Technician (ICT) under line 17 with no tasks
12 Attachment 2, Table Table 2 included a Removed Other (non-2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 that Analysis Event # 6 - that included the removed the Mechanic Steam Generator Mechanic (MT) under (MT) and I&C Technician Tube Rupture line 16 and I&C (ICT) with no tasks EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
Attachment 2
Page 5 of 23 10 CFR 50.54(q) Review Form
Change # Section or Step # Changed From Changed To
(SGTR) Technician (ICT) under assigned line 17 with no tasks assigned
13 Attachment 2, Table Task 8 to Sample Task 8 to Sample 4 - Radiation CVPET was performed CVPET was removed Protection and by the CT Chemistry Analysis Event # 6 - Steam Generator Tube Rupture (SGTR)
14 Attachment 2, Table Attachment 2, Table 1 Attachment 2, Table 1 1 - On-Shift contained lines for the does not include lines for Positions, Analysis Chemistry Technician the Chemistry Technician Event #7-Large (CT) under line 15 with (CT), Mechanic (MT),
Break Loss of no tasks, Mechanic and I&C Technician Coolant Accident (MT) under line 16 with (ICT). No tasks were (LB-LOCA) no tasks, and I&C impacted based upon Technician (ICT) under this change.
line 17 with no tasks
15 Attachment 2, Table Table 2 included a Removed Other (non-2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 that Analysis Event # 7-that included the removed the Mechanic Large Break Loss of Mechanic (MT) under (MT) and I&C Technician Coolant Accident (LB - line 16 and I&C (ICT) with no tasks LOCA) Technician (ICT) under assigned line 17 with no tasks assigned
16 Attachment 2, Table Attachment 2, Table 1 Attachment 2, Table 1 1 - On-Shift contained lines for the does not include lines for Positions, Analysis Chemistry Technician the Chemistry Technician Event #9-Design (CT) under line 15 with (CT), Mechanic (MT),
no tasks, Mechanic and I&C Technician EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
Attachment 2
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Change # Section or Step # Changed From Changed To
Basis Threat (DBT) (MT) under line 16 with (ICT). No tasks were no tasks, and I&C impacted based upon Technician (ICT) under this change.
line 17 with no tasks
17 Attachment 2, Table Table 2 included a Removed Other (non-2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 th at Analysis Event # 9-that included the removed the Mechanic Design Basis Threat Mechanic (MT) under (MT) and I&C Technician (DBT) line 16 and I&C (ICT) with no tasks Technician (ICT) under assigned line 17 with no tasks assigned
18 Attachment 2, Line 31 contained an Removed the action for Analysis Event #10- action for CT to Perform CT to Perform Probable Aircraft surveillances surveillances Threat Tasks and Timing
19 Attachment 2, Table Attachment 2, Table 1 Attachment 2, Table 1 1 - On-Shift contained lines for the does not include lines for Positions, Analysis Chemistry Technician the Chemistry Technician Event #10- Probable (CT) under line 15 with (CT), Mechanic (MT),
Aircraft Threat a role in Table # /Line # and I&C Technician column as 4/8, (ICT). The CT task was Mechanic (MT) under removed with this line 16 with no tasks, change.
and I&C Technician (ICT) under line 17 with no tasks
20 Attachment 2, Table Table 2 included a Removed Other (non-2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 that Analysis Event #10- that included the removed the Mechanic EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Change # Section or Step # Changed From Changed To
Probable Aircraft Mechanic (MT) under (MT) and I&C Technician Threat line 16 and I&C (ICT) with no tasks Technician (ICT) under assigned line 17 with no tasks assigned
21 Attachment 2, Table Task 8 to Perform Task 8 to Perform 4 - Radiation Surveillances was Surveillances was Protection and performed by the CT removed Chemistry Analysis Event # 10 -
Probable Aircraft Threat
22 Attachment 2, Table Attachment 2, Table 1 Attachment 2, Table 1 1 - On-Shift contained lines for the does not include lines for Positions, Analysis Chemistry Technician the Chemistry Technician Event #11-Control (CT) under line 15 with (CT), Mechanic (MT),
Room Evacuation no tasks, Mechanic and I&C Technician Due to Fire (MT) under line 16 with (ICT). No tasks were no tasks, and I&C impacted based upon Technician (ICT) under this change.
line 17 with no tasks
23 Attachment 2, Table Table 2 included a Removed Other (non-2 - Plant Operations section for Other (non-Operations) Personnel
& Safe Shutdown Operations) Personnel section of Table 2 that Analysis Event #11-that included the removed the Mechanic Control Room Mechanic (MT) under (MT) and I&C Technician Evacuation Due to line 16 and I&C (ICT) with no tasks Fire Technician (ICT) under assigned line 17 with no tasks assigned
24 Attachment 2, - Title of Table 4 was Title of Table 4 is Table 4-Radiation Radiation Protection Radiation Protection Protection and EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Change # Section or Step # Changed From Changed To
Chemistry Analysis and Chemistry Analysis for Event #1 -
MSLB, Event# 3-RCP Rotor Seizure, Event #6-SGTR, Event#7 - LB-LOCA, Event #9 -
DBT, Event #10 -
PAT, and Event #11
- Control Room Evacuation Due to Fire.
Section III: Description and Review of Licensing Basis Affected by the Proposed activity or Change:
List all emergency plan sections that were reviewed for this activity by number and title.
IF THE ACTIVITY IN ITS ENTIRETY IS AN EMERGENCY PLAN CHANGE, EAL CHANGE OR EAL BASIS CHANGE, Enter Licensing Basis affected by the change and continue to Section VI.
Licensing Basis
- EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 0
- EP-HNP-EPLAN-ANNEX, Duke Energy Harris Emergency Plan Annex, Revision 0
Current Emergency Plans
- EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Rev 5
- EP-HNP-EPLAN-ANNEX, Duke Energy Harris Emergency Plan Annex, Rev 1
The differences in the approved and the current revision of the Emergency Plan 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. 9
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Section IV: Ability to Maintain the Emergency Plan.
Answer the following questions related to impact on the ability to maintain the Emergency Plan. Continue to Section V.
- 1. Do any of the elements of the proposed activity change information or intent Yes contained in the Emergency Plan?
No
- 2. Do any elements of the proposed activity change the process or capability for Yes alerting or notifying the public as described in the FEMA -approved Alert and Notification System Design Report? No
- 3. Do any elements of the proposed activity change the Evacuation Time Estimate Yes results?
No
- 4. Do any elements of the proposed activity change the On-Shift Staffing Analysis Yes results?
No
- 5. Does the Proposed activity require a change to the Emergency Plan Programmatic Yes Description?
No If Question 5 was answered yes, and the document being reviewed is NOT the Emergency Plan, then exit this review until the Emergency Plan change is complete or the proposed change is modified to not change the Emergency Plan Programmatic Description.
Section IV conclusion:
If questions 1-5 in Section IV marked NO, then complete Section V.
If any question 1-5 of Section IV marked yes, then continue at Section VI.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section V: Maintaining the Emergency Plan Conclusion.
The questions in Section IV do not represent the total of all conditions that may cause a change to or impact the ability to maintain the emergency plan. Originator and reviewer signatures in Section XIV document that a review of all elements of the propos ed change have been considered for their impact on the ability to maintain the emergency plan and their potential to change the emergency plan.
- 1. Provide a brief conclusion below that describes how the conditions, as described in the emergency plan, are maintained with this activity.
- 2. Select the box below when the review completes all actions for all elements of the activity and no 10CFR50.54 screening or evaluation is required for any element. Continue to Section XIV.
I have completed a review of this activity in accordance with 10CFR50.54(q)(2) and determined that the effectiveness of the emergency plan is maintained. This activity does not make any changes to the emergency plan. No further actions are required to screen or evaluate this activity in accordance with 10CFR50.54(q)(3).
Conclusion:
Section VI: Activity Previously Reviewed?
Is this activity fully bounded by an NRC approved 10CFR50.90 submittal or Alert and Notification System Design Report?
Yes 10 CFR 50.54(q) Evaluation is not required.
Identify bounding source document below and continue to Section XIV.
No Continue to Section VII.
If PARTIALLY, identify bounding source document and list changes bounded by the approved 10 CFR 50.90 or Alert and Notification System Design Report
Partially below.
Changes not bound by the approved 10 CFR 50.90 or Alert and Notification System Design Report (i.e., part requiring further review). Continue the review in Section VII.
Bounding source document and list of bounded changes:
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section VII: Editorial Changes All Activities/Changes identified in Section II are editorial/typographical changes Yes such as formatting, paragraph numbering, spelling, or punctuation that does not change intent.
No None of the Activities/Changes listed in Section II are editorial/typographical changes. Continue to Section VIII.
Partially Some Activities/Changes are editorial/typographical.
If Yes is checked, Identify the activities/changes listed in Section II that are editorial/typographical changes and provide justification below. Continue to Section XII.
If Partially is checked, Identify the activities/changes listed in Section II that are editorial/typographical changes and provide justification below. Continue to Section VIII for changes not identified as editorial.
Justification:
Change 1 updated the revision summary for the EP -HNP-OSSA, Revision 1 scope of changes.
Change 2 updated the revision number of the EP -HNP-OSSA from Revision 0 to Revision 1.
Changes 1 and 2 are defined as editorial in accordance with AD -EP-ALL-0602.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section VIII: Emergency Planning Element and Function Screen (Utilize Reg Guide 1.219 and Attachment 1, Additional Regulatory Guidance References for additional assistance)
Does any of Proposed Activities/Changes Identified in Section I impact any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II? If yes check appropriate box.
1 10 CFR 50.47(b)(1) Assignment of Responsibility (Organization Control) 1a Responsibility for emergency response is assigned.
Tponse organizatitf to rpond to amt stf continis (- stfinceith the emgency an.
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 onshift 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.
4 10 CFR 50.47(b)(4) Emergency Classification System RS A standard scheme of emergency classification and action levels is in use.
4a (Requires V/V (Attachment 3) and final approval of Screen and Evaluation by EP CFAM) 5 10 CFR 50.47(b)(5) Notification Methods and Procedures RS Procedures for notification of State and local governmental agencies are capable of 5a 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 public within the plume exposure pathway.
The public ANS meets the design requirements of FEMA-REP-10, Guide for 5c 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 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.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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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).
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 Adequate equipmesntno sut y 9 10 CFR 50.47(b)(9) Accident Assessment RS 9a Methods, systems, and equipment for assessment of radioactive releases are in use.
10 10 CFR 50.47(b) (10) Protective Response RS 10a A range of public PARs is available for implementation during emergencies.
Evacuation time estimates for the population located in the plume exposure pathway 10b EPZ are available to support the formulation of PARs and have been provided to State and local governmental authorities.
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.
Drills, exercises, and training evolutions that provide performance opportunities to 14b develop, maintain, and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.
14c Identified weaknesses are corrected.
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.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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16b Planners responsible for emergency plan development and maintenance are properly trained.
Section VIII: Conclusion ny Section VIII criteria are checked, document the basis for conclusion below for any changes that are more than editorial, however not impacted by any of the identified criteria in Section VIII and continue the 50.54(q) Review in Section IX.
If no Section VIII criteria are checked, 10CFR50.54(q)(3) Evaluation is NOT required.
Document justification below for any changes that are more than editorial and continue to Section XIV.
Justification for changes that are more than editorial, however, not impacted by any of the identified criteria in Section VIII:
Changes 4, 5, 12, 14, 15, 16, 17, 20, 22, and 23 updated various tables to remove the Chemistry Technician (CT), Mechanic (MT), and I&C Technician (ICT) positions that were shown with no tasks assigned. These changes have no impact to the onshift staffing analysis -
since the tasks for each event response were not impacted.
Section IX: Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change Copy each emergency planning standard, function and program element affected by the proposed change that was identified as applicable in Section VIII. Continue to Section X.
List affected Emergency Planning Standards, Functions, and Program Elements:
Planning Standard The regulation at 10 CFR 50.47(b)(2) states the following:
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.
Function The applicable emergency planning function identified for this planning standard:
The process ensures that onshift emergency response responsibilities are staffed and assigned.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Applicable sections of Appendix E to 10 CFR Part 50
IV.A of Appendix E to 10 CFR Part 50
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.
IV.A.9 of Appendix E to 10 CFR Part 50
By December 24, 2012, 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.
Informing Criteria from NUREG-0654
The applicable program elements describe in NUREG -0654,Section II.B state:
B.1.a - The site-specific emergency response organization (ERO) is developed. Note that while other site programs, such as operations, fire response, rescue and first aid, and security, may be controlled via other licensing documents, it is only when these personnel are assigned EP functions that they become part of this regulatory standard. Consideration is given to ensure that EP functions are not assigned to individuals who may have difficulties performing their EP function(s) simultaneously with their other assigned (non-EP) duties. Appendix E to 10 CFR Part 50 requires licensees to perform an on-shift staffing analysis to ensure on-shift staff can support the EP functions assigned, as well as other assigned duties.
B.3 - A table is developed depicting the site-specific on-shift staffing plan, as well as the ERO staffing augmentation plan. Table B -1, Emergency Response Organization (ERO) Staffing and Augmentation Plan, provides a model for licensees to consider.
Section X: Describe How the Proposed Change Complies with Re levant Emergency Preparedness Regulation(s) and Previous Commitment(s) Made to the NRC 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). Address each Planning Standard identified in Section IX. Continue to Section XI.
Justification:
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Change 6 includes updates to the Reactor Coolant Pump Rotor Seizure event tasks and timing.
The first update adds the RP technician 2 as a position available to perform a sample per AOP -
032, High RCS Activity. Plant procedural guidance allows for either a Chemistry technician or RP technician to perform sampling in accordance with AOP -032 and CRC-821, Post Accident Sampling. The RP technicians are qualified to perform this sampling activity. There is no overlap between this sampling activity and other RP functions performed by the RP technician. Therefore, this change aligns personnel responsibilities to responsibilities governed by AOP-032 and CRC-821. The second update removes an action for the I&C technician (ICT) to Check pressure switches for MFP reset/Drain Pumps. The action for the ICT to check pressure switches for MFP reset/Drain Pumps was determined to be unnecessary for the Reactor Coolant Pump Rotor Seizure event immediate response. GP -006, Normal Plant Shutdown From Power Operation to Hot Standby (Mode 1 to Mode 3), contains instructions for the ICT to check pressure switches for MFP reset/Drain Pumps, however this action may be completed after personnel have been called out to support a response to this event. The MFPs are not safety-related components and are not needed to mitigate a postulated accident.
The safety-related Auxiliary Feedwater Pumps (AFWPs) would also be available for immediate use if needed in response to this event. The third change removes an action for the mechanic (MT) to Station at Turbine coastdown/ensure proper turning gear ops. The action for the MT to station at Turbine coastdown/ensure proper turning gear ops was determined to be unnecessary for the Reactor Coolant Pump Rotor Seizure event immediate response. This action may be completed after personnel have been call ed out to support a response to this event. This action is intended to protect the turbine as an asset and does not provide any mitigating benefit to the postulated accident.
Change 7 includes updates to the on-shift positions in Table 1 for the Reactor C oolant Pump Rotor Seizure event, based upon Change 6 described above.
Change 8 includes updates to the Plant Operations & Safe Shutdown Analysis in Table 2 for the Reactor Coolant Pump Rotor Seizure event, based upon Change 6 described above.
Change 9 includes updates to the Radiation Protection and Chemistry Analysis in Table 4 for the Reactor Coolant Pump Rotor Seizure event, based upon Change 6 described above.
Change 10 includes updates to the Steam Generator Tube Rupture (SGTR) event task s and timing. The first update removes an action for the RP technician 1 to Notify CT for sampling CVPET [Condensate Vacuum Pump Effluent Treatment System]. The action for the RP technician 1 to notify CT for sampling CVPET was determined to be unnecessary for the SGTR event immediate response. The second update removes an action for the CT to Sample CVPET. The action for CT to sample the CVPET was determined to be unnecessary for the SGTR event immediate response. This sampling provides indication of t he overall primary to secondary leakage, but does not assist with determining which steam generators are intact for immediate event response, which is determined by other available indications as described in procedural guidance. EOP-E-0, Reactor Trip, steps 27 through 29 instruct EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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the operator to consider any abnormal secondary radiation monitor (main steamline radiation monitors, steam generator blowdown radiation monitor, condenser vacuum pump effluent radiation monitor, and the Turbine Building Vent Stack radiation monitor) indications/ trends, an uncontrolled steam generator level rise, and a steam generator activity sample for evaluating entry into EOP -E-3, Steam Generator Tube Rupture. EOP-E-3 contains instructions to consider any of the following conditions to identify a ruptured steam generator: main steamline radiation monitor high radiation alarms, steam generator level rising in an uncontrolled manner, and a sample from the steam generator blowdown lines with high radiation. AOP-046, Steam Generato r Tube Leak, provides guidance for determining a leaking steam generator by: individual SGBD samples, main steamline radiation monitor levels, and local surveys of SGBD lines. There are various radiation monitor indications available for detecting primary to secondary leakage.
Sampling activities for responding to a SGTR may be completed as necessary after personnel have been called out to support a response to this event without challenging any immediate emergency response activities. The CVPET sampling ac tivity may be completed if necessary after personnel have been called out to support a response to this event.
Change 11 includes updates to the on-shift positions in Table 1 for the SGTR event, based upon Change 10 described above.
Change 13 includes updates to the Radiation Protection and Chemistry Analysis in Table 4 for the SGTR event, based upon Change 10 described above.
Change 18 includes an update to the Probable Aircraft Threat event tasks and timing. The action for the CT to Perform surveillances was removed. The action for the CT to perform surveillances was determined to be unnecessary for the Probable Aircraft Threat event immediate response. AOP -038, Rapid Downpower, contains guidance for an operator to direct Chemistry to initiate surveillances required by RST -204, Reactor Coolant System Chemistry and Radiochemistry Surveillance, and RST -211, Gaseous Effluent Radiochemistry Surveillance.
However, these surveillances may be completed after personnel have been called out to support a response to this event. The Chemistry Technician is required to complete these surveillances within two to six hours following a thermal power change exceeding 15 percent of rated thermal power to meet TS 4/4.4.8, Reactor Coolant System Specific Activity. The shortest timeframe for Chemistry completing these surveillances is six hours following the event (that would involve a thermal power change exceeding 15 percent).
Change 19 includes updates to the on-shift positions in Table 1 for the Probable Aircraft Threat event, based upon Change 18 described above.
Change 21 includes updates to the Radiation Protection and Chemistry Analysis in Table 4 for the Probable Aircraft Threat event, based upon Change 18 described above.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Change 3 removed Chemistry Technician, Mechanic, and I&C Technician from the bulleted list of on-shift personnel and their respective locations in Section 3.4. Change 24 updated the title of Table 4 to remove Chemistry for various analysis events. These updates are based upon other changes to event tasks and responsibilities described under changes 6, 10, and 18 described above. The Chemistry Technician, Mechanic, and I&C Technician do not have tasks in the proposed Revision 1 of the EP -HNP-OSSA and are not required on-shift per the emergency plan, technical specifications, or the UFSAR.
The changes listed above do not change ERO staffing as required by the EP -ALL-EPLAN, Duke Energy Common Emergency Plan and the changes do not reduce on-shift staffing for ERO functions. On shift staffing responsibilities for emergency response remain unambiguously defined, and adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, therefore the changes continue to meet the requirements as identified in 10 CFR 50.47 (b)(2).
Section XI: Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions Address each function identified in Section IX. Continue to Section XII.
Justification:
Change 6 includes updates to the Reactor Coolant Pump Rotor Seizure event tasks and timing.
The first update adds the RP technician 2 as a position available to perform a sample per AOP-032, High RCS Activity. Plant procedural guidance allows for either a Chemistry technician or RP technician to perform sampling in accordance with AOP-032 and CRC-821, Post Accident Sampling. The RP technicians are qualified to perform this sampling activity. There is no overlap between this sampling activity and other RP fu nctions performed by the RP technician. Therefore, this change aligns personnel responsibilities to responsibilities governed by AOP-032 and CRC-821. The second update removes an action for the I&C technician (ICT) to Check pressure switches for MFP reset/Drain Pumps. The action for the ICT to check pressure switches for MFP reset/Drain Pumps was determined to be unnecessary for the Reactor Coolant Pump Rotor Seizure event immediate response. GP -006, Normal Plant Shutdown From Power Operation to Hot Standby (Mode 1 to Mode 3), contains instructions for the ICT to check pressure switches for MFP reset/Drain Pumps, however this action may be completed after personnel have been called out to support a response to this event. The MFPs are not safety-related components and are not needed to mitigate a postulated accident.
The safety-related Auxiliary Feedwater Pumps (AFWPs) would also be available for immediate use if needed in response to this event. The third change removes an action for the mechanic (MT) to Station at Turbine coastdown/ensure proper turning gear ops. The action for the MT to station at Turbine coastdown/ensure proper turning gear ops was determined to be unnecessary for the Reactor Coolant Pump Rotor Seizure event immediate response. This action may be completed after personnel have been called out to support a response to this event. This action is intended to protect the turbine as an asset and does not provide any mitigating benefit to the postulated accident.
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Change 7 includes updates to the on-shift positions in Table 1 for the Reactor Coolant Pump Rotor Seizure event, based upon Change 6 described above.
Change 8 includes updates to the Plant Operations & Safe Shutdown Analysis in Table 2 for the Reactor Coolant Pump Rotor Seizure event, based upon Change 6 described above.
Change 9 includes updates to the Radiation Protection and Chemistry Analysis in Table 4 for the Reactor Coolant Pump Rotor Seizure event, based upon Change 6 described above.
Change 10 includes updates to the Steam Generator Tube Rupture (SGTR) event tasks and timing. The first update removes an action for the RP technician 1 to Notify CT for sampling CVPET [Condensate Vacuum Pump Effluent Treatment System]. The action for the RP technician 1 to notify CT for sampling CVPET was determined to be unnecessary for the SGTR event immediate response. The second update removes an action for the CT to Sample CVPET. The action for CT to sample the CVPET was determined to be unnecessary for the SGTR event immediate response. This sampling provides indication of the overall primary to secondary leakage, but does not assist with determining which steam generators are intact for immediate event response, which is determined by other available indications as described in procedural guidance. EOP-E-0, Reactor Trip, steps 27 through 29 instruct the operator to consider any abnormal secondary radiation monitor (main steamline radiation monitors, steam generator blowdown radiation monitor, condenser vacuum pump effluent radiation monitor, and the Turbine Building Vent Stack radiation monitor) indications/ trends, an uncontrolled steam generator level rise, and a steam generator activity sample for evaluating entry into EOP -E-3, Steam Generator Tube Rupture. EOP-E-3 contains instructions to consider any of the following conditions to identify a ruptured steam generator: main steamline radiation monitor high radiation alarms, steam generator level rising in an uncontrolled manner, and a sample from the steam generator blowdown lines with high radiation. AOP -046, Steam Generator Tube Leak, provides guidance for determining a leaking steam generator by: individual SGBD samples, main steamline radiation monitor levels, and local surveys of SGBD lines. There are various radiation monitor indications available for detecting primary to secondary leakage.
Sampling activities for responding to a SGTR may be completed as necessary after personnel have been called out to support a response to this event without challenging any immediate emergency response activities. The CVPET sampling activity may be completed if necessary after personnel have been called out to support a response to this event.
Change 11 includes updates to the on-shift positions in Table 1 for the SGTR event, based upon Change 10 described above.
Change 13 includes updates to the Radiation Protection and Chemistry Analysis in Table 4 for the SGTR event, based upon Change 10 described above.
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Change 18 includes an update to the Probable Aircraft Threat event tasks and timing. The action for the CT to Perform surveillances was removed. The action for the CT to perform surveillances was determined to be unnecessary for the Probable Aircraft Threat event immediate response. AOP -038, Rapid Downpower, contains guidance for an operator to direct Chemistry to initiate surveillances required by RST -204, Reactor Coolant System Chemistry and Radiochemistry Surveillance, and RST -211, Gaseous Effluent Radiochemistry Surveillance.
However, these surveillances may be completed after personnel have been called out to support a response to this event. The Chemistry Technician is required to complete these surveillances within two to six hours following a thermal power change exceeding 15 percent of rated thermal power to meet TS 4/4.4.8, Reactor Coolant System Specific Activity. The shortest timeframe for Chemistry completing these surveillances is six hours following the event (that would involve a thermal power change exceeding 15 percent).
Change 19 includes updates to the on-shift positions in Table 1 for the Probable Aircraft Threat event, based upon Change 18 described above.
Change 21 includes updates to the Radiation Protection and Chemistry Analysis in Table 4 for the Probable Aircraft Threat event, based upon Change 18 described above.
Change 3 removed Chemistry Technician, Mechanic, and I&C Technician from the bulleted list of on-shift personnel and their respective locations in Section 3.4. Change 24 updated the title of Table 4 to remove Chemistry for various analysis events. These updates are based upon other changes to event tasks and responsibilities described under changes 6, 10, and 18 described above. The Chemistry Technician, Mechanic, and I&C Technician do not have tasks in the proposed Revision 1 of the EP -HNP-OSSA and are not required on-shift per the emergency plan, technical specifications, or the UFSAR.
These changes do not cause any of the major functional areas or major tasks identified in the emergency plan to be unassigned. The changes do not eliminate key positions identified in the emergency plan nor reassign the responsibilities of the eliminated positions to other key positions. The changes do not result in an ERO member being assigned duties that could be expected to be performed concurrently rather than sequentially. The changes do not reduce the effectiveness of the emergency plan as the on-shift ERO staffing complement is unaffected by these changes.
The proposed changes to HNPs On Shift Staffing Analysis continue to show the capability of implementing the site's emergency plan to address a spectrum initiating events and consequences. The key emergency response functions and tasks as described in NUREG -0654 include:
- Shutdown the reactor and maintain safe s hutdown
- Mitigate event consequences
- Determine Protective Action Recommendations (PARs) for site personnel and the public EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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- Perform firefighting
- Provide medical assistance if needed
The changes listed above do not change ERO staffing as set forth in EP -ALL-EPLAN, Duke Energy Common Emergency Plan as on-shift emergency response responsibilities are staffed and assigned. The changes do not reduce the availability of personnel relied upon in the plan.
Therefore, the changes do not reduce the effectiveness of the Duke Energy Common Emergency Plan.
These changes continue to provide assurance that the Emergency Response Organization 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.
These change(s) continue (continues) to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E as well as the requirements of the Duke Energy Sites Emergency Plans as written and approved.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section XII: 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 Yes Appendix E? No
- 2. Does the proposed change maintain the effectiveness of the emergency plan Yes (i.e., no reduction in effectiveness)? No
- 3. Does the proposed change maintain the current Emergency Action Level (EAL) Yes scheme? No Section XII: Conclusion Questions 1, 2 and 3 are answered YES, complete step below to create a General CAS assignment, and then continue on to Section XIV and implement change(s).
General CAS assignment created-Licensing submit changes in accordance with 10 CFR 50.4(b)(5)(ii) within 30 days of change implementation Questions 1 or 2 or 3 are answered NO, complete Sections XIII and Section XIV.
Section XIII: Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change be submitted to the NRC for prior approval?
Yes If No, reject the proposed change, or modify the proposed change and perform a No new evaluation. Continue to Section XIV for this evaluation.
If YES, 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:___________________________________. Complete Section XIV.
EMERGENCY PLAN CHANGE SCREENING AND AD-EP-ALL-0602 EFFECTIVENESS EVALUATIONS 10 CFR 50.54(Q) Rev. 9
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Section XIV: Signatures:
EP CFAM Final Approval is required for changes affecting Program Element 4a of Section VIII.
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.Section XIV as applicable.
Preparer Name (Print): Sarah McDaniel Preparer Signature: See NAS Date: See NAS Reviewer Name (Print): Jamey Sharlow Reviewer Signature: See NAS Date: See NAS Approver Name (Print): William Gunter Approver Signature: See NAS Date: See NAS Approver (EP CFAM, as required) Name Approver Signature: N/A Date: N/A (Print): N/A
QA RECORD