BVY 03-047, Emergency Plan Implementing Procedure Changes
| ML031430269 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/14/2003 |
| From: | Tkaczyk L Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| BVY 03-047 | |
| Download: ML031430269 (30) | |
Text
Entergy Nuclear Northeast Vermont Yankee P.O. Box 0500 185 Old Ferry Road
'OtEntergy Brattleboro, VT 05302-0500
~~~~~~~~~~~~~~~~~~~Tel 802 257 5271 May 14, 2003 BVY 03-047 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Vermont Yankee Emergency Plan Implementing Procedure Changes In accordance with 10 CFR 50.54(q), enclosed are the latest changes to the following Vermont Yankee Emergency Plan Implementing Procedures including the change memos and the 10 CFR 50.54(q)
Evaluation Checklists:
OP 3536, Rev. 2 OP 3504, Rev. 36, LPC#I These changes were determined to not need prior NRC review and approval.
If you have any questions, please contact Audra Williams, Emergency Planning Coordinator, in our Brattleboro office at (802) 258-4177.
Sincerely, ENTERGY NUCLEAR NORTHEAST VERMONT YANKEE Z/7V 2 lori Tkaczyk Emergency Planning Manager Attachments cc:
USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS (no attachments)
David M. Silk, Senior Emergency Preparedness Specialist, USNRC Region I Vermont Department of Public Service
S~
~
S S
To:
E-Plan Implementing Procedure Controlled Set Holders FTom: Technical Support - DCC - Angela M. Hogan Date:
05/14/03 Re:
Entergy Vermont Yankee Emergency Plan Implementing Procedure Change 217, Instruction Sheet A new Table of Contents is included.
LPCs:
The following LPC should be incotporated into the appropriate procedures:
Proc/Rev #
LPC #
Procedure Title OP 3504/36 1
Emergency Communications REVISIONS:
The following Revs should replace the appropriate procedures:
Proc/Rev #
Procedure Title OP 3536/2 In-Plant Air Sample Analysis with Abnormal Conditions
Vermont Yankee Emergency Plan Implementing Procedures Table of Contents May 14,2003 Title Number Revision LPC Use Emergency Plan Classification and Action Level Scheme AP 3125 Rev. 19 "Reference" Emergency Comm unications OP 3504 Rev. 36 1 -"Reference" Emergency Preparedness Exercises and Drills OP 3505 Rev. 24 1
"Information" Emergency Equipment Readiness Check OP 3506 Rev. 42 1
"Reference" Emergency Radiation Exposure Control OP 3507 Rev. 30 "Reference" On-Site Medical Emergency Procedure OP 3508 Rev. 23 "Reference" Environmental Sample Collection During an Emergency OP 3509 Rev. 17 "Reference" Off-Site and Site Boundary Monitoring OP 3510 Rev. 27 "Reference" Off-Site Protective Action Recom mendations
=
OP 3511 Rev. 12
=
Reference" Evaluation of Off-Site Radiological Conditions OP 3513 Rev. 21 "Reference" Emergency Actions to Ensure Initial Accountability and Security OP 3524 Rev. 20 "Reference"
Response
Radiological Coordination OP 3525 Rev. 10 "Reference" Emergency Call-In Method OP 3531 Rev. 16 "Reference" Emergency Preparedness Organization AP 3532 Rev. 11 "Information" Post Accident Sampling of Reactor Coolant OP 3533 Rev. 6 1
"Continuous" ost Accident Sampling of Plant Stack Gaseous Releases OP 3534 Rev. 4 "Continuous" Post Accident Sampling and Analysis of Primary Containment OP 3535 Rev. 4 "Continuous" In Plant Air Sample Analysis with Abnormal Condition OP 3536 Rev. 2 "Continuous" Control Room Actions During an Emergency OP 3540 Rev. 3 "Reference" Activation of the Technical Support Center (TSC)
OP 3541 Rev. 2 "Reference" Operation of the Technical Support Center (TSC)
OP 3542 Rev. 2 "Reference" Activation of the Operations Support Center (OSC)
OP 3543 Rev. 0 "Reference" Operation of the Operations Support Center (OSC)
OP 3544 Rev. 3
=
"Reference" Activation of the Emergency Operations Facility/Recovery Center OP 3545 Rev. 2 "Reference" (EOF/RC)
Operation of the Emergency Operations Facility/Recovery Center OP 3546 Rev. 3 "Reference" (EOFRC)
Security Actions During an Emergency OP 3547 Rev. 1 1
"Reference" Emergency Plan Training OP 3712 Rev. 17.
"Information" Page 1 of 1 Table of Contents n
f
PREAPPROVED LPC FORM PART 1 - Initiation L Converted to Admin. Revision #
LPC No:
A. Procedure No.:
OP 3504 lCurrent Revision#:
36
Title:
Emergency Communications B. Description of Change:
Changed phone number of ISO on Appendix B, page 1 of 3.
C. Reason for Change: LI Result of Design Change, Minor Mod, EDCR D
LI Related ERNo.__
L Other:__
._Editorial D. Duration:
3 Permanent One Time Only I. Originator (Print/Sign/Date)
E. Surveillance Database Change? LI Yes, change submitted Z No (Use AP 0096, App. A as a reference)
F. Procedre Type:
Technical
[]ZAdmin. (AP,PP)
(Complete & attach AP 0096 App. C, F. Procedure Type:
3 Technical C] Admin. (AP,PP) unless editorial)
G. AP 0091, Risk Assessment E] Yes 3 No Audra Willi 4/28/03 H. Page(s) affected:
App. B, page of 3 C
PART 2 - Review/Approval (Refer to LPC Criteria of Apendix A)
A. Technical Verification Review (Print/Sign/Date) (Use B. Cross-Discipline Review(s) (Print/Sign/Date)
AP 0096, Appendix B as a reference)
I N/A EN/A (May perform Qualified Review) (N/A if editorial change)
C. Qualified Review (Print/Sign/Date) (Use AP 0096, D. 50.59 review completed type:
Appendix D, as a reference) 3 N/A
[L AD/Screen L Evaluation
[ N/A (N/A if editorial change)
(N/A if editorial change) 50.54(q) (EPIP only)
E. RPO Approval (Print/Sign/Date)
F.-IF-50.59 Evaluation:
N/A n3riqlA
~
<1uiV
>PORC Mtg.
Date:
G. Plant Manager (Print/Sign/Date) (SPs only)
N/A H. Training: (Required for Admin Procedures, unless editorial) 3 N/A I. Effective Date:
5/14/03 CDS Initials VYAPF 0097.01 AP 0097 Rev. 3 Page I of I
I
10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):
OP 3504, Rev. 36, LPC#1, Emergency Communications A.
Screening Evaluation Could the proposed change affect our ability to meet the following standards of 10CFR50.47(b):
(1)
Assignment of Emergency Response Organization responsibilities (2)
Assignment of on-shift Emergency Response Organization personnel (3)
Arrangements for Emergency Response Support and Resources (4)
Emergency Classification and Action levels, including facility system and effluent parameters (5)
Notification Methods and Procedures (6)
Emergency Communications among principal response organizations and the public (7)
Public Education and Information (8)
Adequacy of Emergencyacilities and Equipment (9)
Adequacy of Accident Assessment methods, systems and equipment (10)
Plume exposure pathway EPZ protective actions (11)
Emergency Worker Radiological Exposure Control (12)
Medical Services for contaminated injured individuals (13)
Recovery and Reentry Plans (14)
Emergency response periodic drills and exercises (15)
Radiological Emergency Response Training (16)
Plan development, review and distribution Il-YES l
NOl x
x x
x x
-_ - __ x _ _
x x
x x
x VYAPF 3532.01 AP 3532 Rev. 11 Page 1 of 3 Based on a review of the following questions, deternine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.
A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.
A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.
10 CFR 50.5 4(q) Evaluation Checklist (Continued)
- 2.
Could the change affect our ability to meet the following requirements of Appendix E to OCFR50 (I)
Section IV. A - Organization (2)
Section IV. B - Assessment Actions (3)
Section IV. C - Activation of Emergency Organizations (4)
Section IV. D -Notification Procedures (5)
Section IV. E - Emergency Facilities and Equipment (6)
Section IV. F - Training (7)
Section IV. G - Maintaining Emergency Preparedness (8)
Section IV. H - Recovery YES NO x
x x
x x
x x
x B.
Effectiveness Determination For applicable item 10CFR50 N/A of Section A above, this change LI DOES Z DOES NOT decrease the effectiveness of the Emergency Plan and 3 DOES LI DOES NOT continue to meet the stated applicable standard or requirement.
BASIS FOR ANSWER:
VYAPF 3532.01 AP 3532 Rev. 11 Page 2 of 3 For each applicable (i.e., a yes" answer specified) standard to I OCFR50.47(b) and Appendix E to 10CFR50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.
A facsimile of the evaluation form may be used as needed and attached to this checklist.
This change was editorial for a phone number change.
r 10 CFR 50.54(q) EvaluationChecklist (Continued)
C.
Conclusion (Fill out appropriate information)
Z The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 1 OCFR50.47(b) and the requirements of Appendix E to 1 OCFR50.-
LII The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of l OCFR50.47(b) and the requirements of Appendix E to IOCFR5O. The following course of action is recommended:
L]
Revise proposed changes to meet applicable standards and requirements.
[]
Cancel the proposed changes.
g Process proposed changes for NRC approval prior to implementation in accordance with 10CFR50.54(q).
D.
Impact on Other Documents (TRM, Tech Specs)
Keywords used in search:_
S This change does not affect any other documents.
ktJ LI This change does affect other documents.
Document(s) affected:_
Section(s) affected:_
E.
Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR-information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.
Keywords used in UFSAR search:_
Additional Comments:
Prepared By: Chrissy Cantv Date:
_ /_
(Print/Sii)
Reviewed By: Audra Williams OQUtUf (OU&aM Date: 4/28/03 (Emergency Plan Coordinator) (Print/Sign)
VYAPF3532.01 AP 3532 Rev. 11 Page 3 of 3
VERMONT YANKEE NUCLEAR POWER STATION OP 3504 REVISION 36 EMERGENCY COMMUNICATIONS USE CLASSIFICATION: REFERENCE lImplementation Statement: N/A Issue Date:
04/02/03 OP 3504 Rev. 36 Page 1 of 23 LPC Effective Affected Pages No.
Date Afce ae 1
05/14/03 App. B pg. 1 of 3
=~~~~~
. ~ ~ ~ ~ ~~~~~~
1
.1 I
APPENDIX B
~. I OFF-SITE EMERGENCY TELEPHONE NUMBER LIST (In Alphabetical Order)
American Nuclear Insurers (ANI)
AT&T (NOAA radio phone lines to Ames Hill)
Brattleboro Memorial Hospital Emergency Room (Ref. OP 3508)
CAN - Operations Manager (Ref. OP 3531) to verify operator and callback #'s TELEPHONE NUMBER 860-561-3433 800-413-5410 (prompt 4) 802-257-8222 800-992-2331 800-552-4226 or 877-786-8478 800-739-9023(in-dial) 800-794-5826in-dial) 518-862-0987 (Adniin.)
Central Vermont Communications (Ref. OP 3531) 800-696-6474 802-775-8400 (pager)
Consultation:
Dave E. Drum, MD, Radiation Safety Officer 617-732-5656 Page 11161 (Ref. OP 3508) 617-323-7700 5939 Voice Mail Department of Energy (DOE) Radiological Assistance, Brookhaven Lab Framatome ANP, Marlborough, MA (Main Switchboard)
(Ref. OP 3504, OP 3510, OP 3531)
Framatome ANP Pagers (Ref. OP 3531)
Franklin Medical Center (Ref. OP 3508)
GE Emergeiicy Support Assistance INPO Main Switchboard Emergency Network Telephone ac-T ISO - New England (Ref. OP 3504, OP 3506)
Keene Dispatch (Ref. OP 3506)
Maine Yankee - Wiscasset (Ref. OP 3504) 631-344-2200 508-229-2100 800-366-2337 413-772-0211 408-971-1038 770-644-8000 800-321-0614 -
413-5354303 603-352-1100 (Primary) 603-352-1291 (Backup) 207-882-6321 Appendix B OP 3504 Rev. 36 Page 1 of 3 LPC# 1
REVISED PROCEDURE CONTROL FORM V
?ART 1 - Initiation A. Procedure No.
New Revision Title OP 3536 No. 2 In-Plant Air Sample Analysis With Abnormal Conditions l B. Review Criteria: [ Partial
[]Editorial C. Periodic Review Cycle:
X 2 Year (Event Driven)
Z Complete l
]N/A D. List DIs & LPCs: N/A E. Description and Reasons for Procedure/Changes:
- Added text to control the need for future Applicability Determinations.
- idlef OJXit i iCF
- -_rfcd qp~CIAX a CL-'irA, (~Lik&wLu~ hi &$lCjjc,S iotn e f eo-C b D DP4SSS F.
Originator Name:
(App. A was used as references to create this revision, App. C is Telephone completed and attached unless Part.B above is "Editorial".)
Extension:
(Print/sign/date) Audra Williams 1 1/6/03 x4177 PART 2 - Reviews A. Walk-Through Validation: Fl Required Z N/A B. Technical Verification Reviewer F] N/A (App!B useas' reference)
E] Field Walk-Through (Print/Sign/Date)
L] Table-Top LI Simulator ValidationL c
k / /
C. Cross-Discipline Reviews:
l N/A Department Name Signature Date Rad Protection I 1 0
/-(G0
_3 I~
.I P. 50.59 Rcview Per AP 6002,-Preparing 50.59 Evaluations --
L N/A -
^
~
-~
X L] 50.59 AD previously performed and documented in the text of this procedure and is still applicable.
50.59 Applicability Determination completed and attached; 50.59 Screening NOT required.
El 50.59 Review Screening completed and attached, 50.59 Evaluation NOT required.
L 50.59 Evaluation completed and attached.
E. QUALIFIED REVIEWER: Use App. D as a reference (May perform 50.59 Applicability Determination)
(Part 2.D)
(Print/Sign/Date)
AuAdxti L%UAhtamS
§ Add lWJJ 2' IO.03 F.
IGINATOR: Te Comments Resolved
[e-verify All DIs & LPCs Considered
[itSetor Final Type (CDS or STC (SPs only)) InitialDate a LJ.f 1/n
/n3 ErProofread after Final Type (Print/Sign/Date) Audr.VII lilt-mS _A 45/. 03 VYAPF0096.01 AP 0096 Rev. 3 Page l of 2
.11 I
PART 3 - Training/Notification Requirements I A. Indicate training or notifications required to implement procedure: (Required for Administrative Procedures)
LI Include in formal training (TCR submitted):
l E-Mail notification:
[]Crew Briefings:
PART 4-PORC Plant Operation Review Committee:
] Required 3 N/A Meeting No:
PORC Secretary:
Date:
Plant Manager:
PART 5 - Approval A. Responsible Procedure Owner: (P Signature/Date 7
]
II B. Plant Manager (Print/Sign!Dafe) (For SPs Only) k /AV C. Special Instructions:
N/A Li Approved for Training Issue on DATE: 514 03 a Submit Surveillance Database Change per AP 4000
[ Other:
PART 6 - Issuance Procedure Change No.: Sl 7 Date procedure issued:
5/iq/o 3 Notes:
VYAPF 0096.01 AP 0096 Rev. 3 Page 2 of 2 C] Other:
M3N/A-
APPENDIX C CROSS-DISCIPLINE REVIEW CHECEIST Required to be completed for new procedures, procedure revisions, and LPCs unless they are designated as Editorial.
Procedure Number/Revision OP 3536. Rev. I Reviewer/Date (Print) Audra Williams 1/6/03 APPLICABLE Appendix C AP 0096 Rev. 3 Page 1 of 3 GENERAL REVIEW GUIDELINES/SPECIAL REVIEW REOUIREMENTS The Cross-Discipline Review Guidelines below constitute minimum review requirements; other reviews may apply.
Determination of reviews should focus on changes made to a procedure and the potential impact of those changes on the affected group. Changes that are minimally or noninpacting do not need review by the potentially affected group.
If change impact is unclear, the procedure should be routed to the potentially affected group for review.
New or revised Administrative or Program Procedures that significantly impact other departments, shall be reviewed by the appropriate Superintendent or Senior Manager. The PAA maintains a list of these Administrative and Program Procedures.
ALL noneditorial changes to Special Process procedures (WP, NE, heat treating, etc.), including Vendor Procedures that address Special Processes, shall be reviewed by. a Welding Engineer (welding procedures) or a NDE Level In certified in the method addressed by the procedure (nondestructive examination procedures), AND the Quality Assurance Manager, AND submitted to the Authorized Nuclear Inservice Inspector (ANII) prior to use.
A "YES" indicates that a Cross Discipline Review shall be done by the indicated Departnent. Document the review on VYAPF 0096.01, VYAPF 0097.01, or VYAPF 0097.02, as applicable.
Chemistry:
Potentially affects condensate, feedwater, or reactor water chemistry, or chemistry instruments.
Procedures that implement the requirements of the VY Environmental Program.
(see PP 7603, Appendix A)
Produces/affects effluents or effluent monitoring (VY/QA 01-0 15).
Affects NPDES limits or method of compliance.
X Maintenance (Mech, Elec, I&C):
Requires Maintenance personnel to perform activities, such as performance of maintenance procedures, installation of M&TE, lifting -and landing of leads and connectors.
X Operations:
Changed requirements for entry into a Limiting Condition for Operation (LCO) or -
significantly changes duration of LCO.
Requires Operations alignment/restoration of systems or components.
Specifies surveillance or post maintenance testing by Operations.
X EOP/SAG Coordinator:
Procedures that have the potential to affect the EOPs/SAGs.
X
=
YES NO
APPENDIX C (Continued)
APPLICABLE YES NO Quality Assurance:
Changes to procedures that implement the requirements of the VOQAM. (see PP 7802, Appendix B)
New procedures that have a potential for reduction of VOQAM commitments.
Obtain and attach a I OCFR50.54(a)(3) evaluation.
X Radiation Protection:
Involves work in contaminated areas and high radiation areas.
Involves work that breaches contaminated systems or components.
Changes in radwaste or hazardous waste generation.
X Emergency Plan Coordinator:
Emergency Plan Implementing Procedures.
Obtain and attach a 10CFR5O.54(q) Evaluation.
Affects Emergency Plan personnel, facilities or equipment.
X Softvare Quality Assurance Adninistrator Procedures that define how software is developed.
X Reactor Engineering:
Could affect core reactivity, thermal power, reactor heat balance, or fuel integrity.
Involves refueling operations.
x Systems/ProjectDesign Engineering:
Maintenance Rule in-scope systems unavailability time.
Involves infrequently performed test or evolution.
Changed requirements for entry into a Limiting Condition fo'r'Operation (LCO) or' significantly changes duration of LCO.
Significant changes in system test or operation methodology.
X Appendix J Coordinator:
Changes that affect App. J leakrates or containment boundaries, or boundary valve manipulation.
X Appendix R Coordinator:
7*
Appendix R implementing procedures.
X Environmental Qualification (EQ) Coordinator:
e hange in EQ test methodology or component lifetime.
Potentially affects area EQ component environment.
X Fire Protection Coordinator (FPC):
Fire Protection procedures.
Affects fire loading Affects fire barrier integrity.
Affects fire protection systems or component functionality.
X IST Program Coordinator:
Inservice Testing Program implementing procedures.
All surveillance procedures.
X ISI Program Coordinator:
Inservice Inspection Program implementing procedures.
X Appendix C AP 0096 Rev. 3 Page 2 of 3
p APPENDIX C (Continued)
APPLICABLE
-T Appendix C AP 0096 Rev. 3 Page 3 of 3 Setpoint Coordinator:
Changes that impact setpoints, as-found/as-left tolerances, M&TE or testing methodology.
X Nuclear & PRA Potentially affects IPEEE or ORAM Sentinel Risk Models.
Potentially affects plant SSCs reliability.
Potentially affects Nuclear or Radiological Safety Analysis.
X Security:
Proceures that implement the requirements of the VY Physical Security and Training and Qualification Plans.
Changes that have a potential for reduction of the VY Physical Security and Training and Qualification Plan commitments.
Obtain and attach a I OCFR50.54(P) Evaluation.
X YES NO
AiPLICABIL I
.I-A..
~~~~APPLICABILITY DETERMINATION Activity/Document Number:
OP 3536 Revision Number:
2 sfitle:
In-Plant Air Sample Analysis With Abnormal Conditions Provide or attach a brief description of activities (section 6.3 of RM):
Added text to control the need for future Applicability Determinations.
Address the questions below for all aspects of the activity. If the answer is "YES" for any portion of the activity, apply the identified process to that portion of the activity. It is not unusual to have more than one process apply to a given activity. For example, a change to a door that is a fire door, a security door and a secondary containment door would require an evaluation to the Fire Protection license condition, IOCFR50.54 (p) and a 50.59 screen. See Section 4 of the "50.59 Resource Manual" (RM) for additional guidance.
I.
Does the proposed activity involve a change to the:
Section 4.2.1 of the RM
- 1. Technical Specifications or Operating License (1 OCFR50.90)? Note that stand-alone changes to the TS Bases are evaluated in (If YES process per AP 0063) accordance with 10CFR50.59 per AP 0063.
0 NO E] YES
- 2.
Quality Assurance Plan, related implementing procedures (If YES contact QA for identified in PP 7802 or facility changes (I OCFR50.54(a))?
0D NO El YES I OCFR50.54(a)(3) assessment)
- 3.
Security Plan, related implementing procedures or facility changes (If YES contact Security for (10CFR50.54(p))?
ED NO E YES IOCFR50.54(p) assessment)
- 4.
Emergency Plan, related implementing procedures or facility (If YES contact E-Plan for changes (I OCFR50.54(q))?
El NO ED YES IOCFR50.54(q) assessment per AP 3532)
- 5.
IST Program Plan, related implementing procedures or facility changes (IOCFR50.55a(f))?
- 6.
ISI Program Plan, related implementing procedures or facility changes ( OCFR50.55a(g))?
N3 NO YES J
I
[OEINO El YES (If YES, and a deviation from the code requirement is required, contact Licensing to ensure applicable NRC approval is obtained per AP 0058) ------- ------- -
. I (If YES, and a deviation from the code requirement is required, contact Licensing to ensure applicable NRC anroval is obtained ner AP 005 8) - - -
- 7.
Fire protection program, related implementing procedures or (If YES provide an evaluation that facility changes (License Condition 3.F)?
0D NO El YES satisfies License Condition 3.F )
VYAPF 6002.03 AP 6002 Rev; 8 Page 1 of 3
- 11.
Does the proposed activity involve:
Section 4.2.2 of the RM
- 1. Maintenance which restores SSCs to their original condition.
0] NO []YES (If YES perform maintenance in accordance with plant procedures (e.g.
- 2.
A temporary alteration supporting maintenance that will be in effect during at-power operations for 90 days or less that has been (If YES process in accordance with (or will be) evaluated under I0CFR50.65(a)(4) prior to 0D NO a YES AP 0091.)
implementation?
111.
Does the proposed activity involve a change to the UFSAR (including Section 4.2.3 of the RM documents incorporated by reference) excluded from the requirement to perform a 50.59 Review (NEI 96-07 or NEI 98-03)?
0 NO ED YES (If YES, process FSAR change per AP 6036 "FSAR Revision Process".
Include basis for excluding 10CFR50.59 evaluation below.)
IV.
Does the proposed activity involve a change to the:
Section 4.2.4 of the RM
- 1. Managerial or administrative procedures governing the conduct of Facility operations, maintenance and training (subject to the control of IOCFR50, Appendix B) (RM section 4.2.4). Some procedures (If YES process per procedure change may be VOQAM implementing procedures requiring evaluation process per procedurePchange per 0CFR50.54(aX3) (prompted above). Also, Maintenance process (e.g. AP 0095, AP 0096, procedure changes that include changes to Design Information, not
))
evaluated under a design change process, shall be evaluated in accordance with 10CFR50.59 ED NO El YES
- 2.
Regulatory commitment where changing commitment is not (IfYES process per AP 0055 covered by another regulation based change process (NEI 99-04)? 0 NO O YES "Regulatory Commitment Management".)
V.
Does the activity impact other plant specific programs (e.g., The ODCM and PCLRTP controlled per TS 6.7 and the PCP controlled per (If YES process per the procedure(s) for TRM Section 6 ) which are controlled by regulations, the Operating the appropriate activity.)
License, the Technical Specifications or TRM ?
0 NO E YES VI.
Is the activity covered by any other specific regulatory change process not discussed above that would preclude the need to evaluate under IOCFR50.59 ?.(e.g., IOCFR50.46 for changes to ECCS models and PCT changes. iOCFR50.12 for Exemption Reauests. etc)
W NO YES (IfiYES document below and process per applicable regulatory requirements.)
VII Does the activity require a 50.59 Screen based on the following Generic NRC correspondence? GL 95-02 for performing Analog-to-Digital upgrades, IEB 80-10 for Contamination of non-radioactive systems, IEC 80-18 for changes to radioactive waste systems and GL 91-18 for (If YES complete 50.59 Screen for the compensatory actions including using manual actions in-lieu of subject activity.)
automatic actions or use-as-is dispositions affecting the FSAR. GL 95-02 assessments need to look at both system and component level failures (ER20000558_01)
ENO El YES VYAPF 6002.03 AP 6002-Rev. 8 Page 2 of 3
"7" All aspects of the activity are controlled by one or more of the processes above, therefore a 50.59 Screen is not required. If checked, provide any additional comments below and sign and date below.
71 Any portion of the activity is not controlled by one or more of the processes above, therefore a 50.59 Screen or 50.59 Evaluation
,--s required. If, checked, provide any additional comments below, sign and date below and complete 50.59 Screen for identified activities.
Additional Applicability Considerations:
Applicability Signoffs:
Preparer..
Reviewer Audra Williams i Qkl2ll&
JL L/jf Date:
(Print name) gn)
- Ln4 A7TmaCzCkI Xii-Date:
I / 06 / 03 VYAPF 6002.03 AP 6002 Rev. 8 Page 3 of 3
,P a
/01
10 CFR 50.54(q) Evaluation Checklist List of Emergency Plan Section(s)/Emergency Plan Implementing Procedure(s) or any other document to be evaluated. (Include Title and Revision No.):
OP 3536, Rev 2, In-Plant Air Sample Analysis With Abnormal Conditions A. Screening Evaluation Based on a review of the following questions, determine if the change has the potential to affect our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.
A "YES" answer to any part of the questions requires that a written evaluation be done to determine whether the effectiveness of the Emergency Plan was decreased as specified in Section B of this checklist.
A "NO" answer to all questions requires no written evaluation as specified in Section B of this checklist.
- 1.
Could the proposed change affect our ability to meet the following standards of 10 CFR 50.47(b):
(1) Assignment of Emergency Response Organization responsibilities YES NO (2) Assignment of on-shift Emergency Response Organization personnel YES NO (3) Arrangements for Emergency Response Support and Resources YES NO (4) Emergency Classification and Action levels, including facility system and effluent parameters YES NO (5) Notification Methods and Procedures YES NO (6) Emergency Communications among principal response organizations and the public YES NO (7) Public Education and Information YES NO (8) Adequacy of Emergency Facilities and Equipment YES NO (9) Adequacy of Accident Assessment methods, systems and equipment YES NO (10) Plume e EPZ protective actions YES NO (11)
Emergency Worker Radiological Exposure Control YES NO (12) Medical Services for contaminated injured individuals YES NO (13) Recovery and Reentry Plans YES NO (14) Emergency response periodic drills and exercises YES NO (15) Radiological Emergency Response Training YES NO (16) Plan development, review and distribution YES NO VYAPF 3532.01 AP 3532 Rev. 10 Page of 3 RT No. 10.E06.171
10 CFR 50.54 (q) Evaluation Checklist (Continued) l 2.
Could the change affect our ability to meet the following requirements of Appendix E to 10 CFR 50.
(1)Section IV. A - Organization YES NO (2)Section IV. B - Assessment Actions (3)Section IV. C - Activation of Emergency Organizations (4)Section IV. D -
Notification Procedures (5)Section IV. E -
Emergency Facilities and Equipment (6)Section IV. F -
Training (7)Section IV. G -
Maintaining Emergency Preparedness (8)Section IV. H -
Recovery YES NO YES NO YES NO YES NO YES NO YES NO YES NO B. Effectiveness Determination For applicable item 10 CFR 50 N/A of Section A above, this change DOES NOT decrease the effectiveness of the Emergency Plan and DOES continue to meet the stated applicable standard or requirement.
BASIS FOR ANSWER:
Added a statement to control the need of an Applicability Determination. iie-UQQA-~e~r~c AI!Ac~.
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VYAPF 3532.01 AP 3532 Rev. 10 Page 2 of 3 For each applicable (i.e., a "yes" answer specified) standard to 10 CFR 50.47(b) and Appendix E to 10 CFR 50 identified from Section A above, complete the evaluation form below to determine whether the change decreases the effectiveness of the Emergency Plan and whether it continues to meet the stated applicable standard or requirement.
A facsimile of the evaluation form may be used as needed and attached to this checklist.
10 CFR 50.54 (q) Evaluation Checklist (Continued)
C. Conclusion (Fill out appropriate information)
El The changes made do not decrease the effectiveness of the Emergency Plan and continue to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.
O The changes made do decrease the effectiveness of the Emergency Plan and decrease our ability to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.
The following course of action is recommended:
o Revise proposed changes to meet applicable standards and requirements.
O Cancel the proposed changes.
o Process proposed changes for NRC approval prior to implementation in accordance with 10 CFR 50.54(q).
D. Impact on Other Documents (TRM, Tech Specs)
Keywords used in search:
[Z This change does not affect any other documents.
o This change does affect other documents.
Document (s) affected:_
Section(s) affected:_
E. Impact on the Updated FSAR Use AP 6036 to determine if the proposed E-Plan change modifies existing UFSAR information or requires the addition of new UFSAR information and initiate UFSAR change(s) as required.
Keywords used in UFSAR search:
Additional Comments:
f~~~~~~~~~~~~~~~~~~~~~
Prepared By:
Reviewed By:
Audra Williams
(
/
(Prin>gn-Xi (Emergency Pla Coordinator) (Printeign)
Date:
1/6/03 Date:
VYAPF 3532.01 AP 3532 Rev. 10 Page 3 of 3
VERMONT YANKEE NUCLEAR POWER STATION OP 3536 REVISION 2 IN-PLANT AIR SAM1PLE ANALYSIS WITH ABNORMAL CONDITIONS USE CLASSIFICATION: CONTINUOUS Implementation Statement: N/A Issue Date:
05/14/2003 OP 3536 Rev. 2 Page 1 of 9 LPC Effective Affected Pages No.
Date I
I -
TABLE OF CONTENTS PURPOSE............
3 DISCUSSION....
3 ATIACHMENTS.............
3 REFERENCES AND COMMITMENTS............................
3 PRECAUTIONS/LIMTATIONS...
4.................
PREREQUIS1TES..................
4 PROCEDURE ~~~~~~~~~~~~~~~~............................. 4...........................
PROCEDUJRE4 FIAION MNNAL.................COND........................IONS........................
OP 3536 Rev. 2 Page 2 of 9
PURPOSE To outline the special procedures necessary to handle aii samples, perform analyses and interpret results during post accident conditions.
DISCUSSION During post accident conditions, system samples may be highly radioactive. Because of the potentially high radiation levels, these samples require special handling. This procedure outlines the special handling required. The RP Superintendent is responsible for implementation of this procedure.
During certain postulated accidents, the availability of on-site counting equipment may be compromised. In these instances, post accident samples may be counted at remote counting facilities. A determination will be made by the Operations Support Center Coordinator's Assistant, in conjunction with the Radiological Assistant at the Emergency Operations Facility/Recovery Center, as to the most appropriate altemative laboratory facility.
VYOPF 3536.01, Sample Accountability Log shall be utilized from the onset of emergency sampling and analysis to control the location of all emergency samples.
In accordance with AP 6002, Preparing 50.59 Evaluations, the results of an Applicability Determination (AD) has determined that an AD is not required for future changes provided the scope of the procedure or program is not revised to include a different type of activity. The basis for this conclusion is that this document is an Emergency Implementing Procedure and is subject to CFR50.54(q) to determine if the changes decrease the effectiveness of the Emergency Plan and if they have the potential to affect our ability to meet the standards of 10CFR50.47(b) and the requirements of 10CFR50 Appendix E.
ATTACHMENTS
- 1.
VYOPF 3536.01 Sample Accountability Log REFERENCES AND COMMITMENTS
- 1.
Technical Specifications and Site Documents
- a.
None
- 2.
Codes, Standards, and Regulations
- a.
NTREG 0737, Sec. H.B.3
- 3.
Commitments
- a.
None OP 3536 Rev. 2 Page 3 of 9
- 4.
Supplemental References
- a.
VYDPF 0530.02, Emergency Air Sample Analysis Using Portable Dose Rate K) 0 Instruments, Report #43
- b.
VYAPF 0645.01, Evaluation of PASS High Activity Correction Factor
- c.
DP 2631, Radiochemical Instrumentation
- d.
OP 4533, Airborne Radioactivity Concentration Determination
- e.
DP 4562, Calibration and Use of the SAM-2
- f.
DP 4585, Control of the RP Multichannel Analyzer
- g.
AP 6807, Collection, Temporary Storage and Retrieval of QA Records PRECAUTIONS/LIMITATIONS
- 1.
During sampling, communications with the OSC or RP Checkpoint should be maintained using either a portable radio or a Gai-Tronics.
PREREQUISITES
- 1.
Obtain post accident sampling equipment and tools.
- 2.
Obtain a dose rate meter.
- 3.
Dose commitment limits have been established and should be adhered to for all Post Accident Sampling. Consult with the OSC Coordinator for specific instructions.
- 4.
The duty RP Supervisor shall evaluate the need for respiratory protection and evaluate whether or not extremity dosimetry and high range pocket dosimeters should be wom during sampling.
PROCEDURE INITIJALS
- 1.
Charcoal cartridges should be purged of noble gases for 1 minute prior to counting.
- a.
Run the air sampler with charcoal cartridge for 1 minute in a low airbome activity location.
RP Tech.
- 2.
Ensure the sample is properly wrapped to minimize the potential for contaminating counting equipment.
RP Tech.
- 3.
Log the sample identifying information onto VYOPF 3536.01.
RP Tech.
OP 3536 Rev. 2 Page 4 of 9
INlIALS
- 4.
Analyze the sampie and quantify the airbome exposure hazard.
The preferred order of analysis is as follows:
- a.
HpGe Isotopic Analysis:
- 1)
Count samples, ensuring that dead time is <10%.
RP Tech.
- 2)
If counter dead time is >10%, count the sample at extended distances.
a)
Open the shield top of the 10% HpGe.
b)
Using the rod and holder, suspend the sample above the detector at a distance (minimum distance is 1 foot) that will give a I counter dead time of <20%.
RP Tech.
RP Tech.
c)
Measure the distance from the sample to the top of the detector.
d =
feet d)
RP Tech.
Count the sample using the Lo Vol Air Sample Filter/Charcoal geometry.
- RP Tech.
e)
Calculate the Off Contact Geometry Correction Factor as follows:
Off Contact Geometry CF = 17d2 Where d= the off contact distance between sample and detector, as measured in FEET.
CF=
RP Tech.
OP 3536 Rev. 2 Page 5 of 9 CAUTION If general area dose rates in the counting room exceeds 5 mR/hr, the use of the MCA at extended distance with the shield top removed is prohibited (LAI-417B).
- 3)
Complete VYOPF 4533.01.
a)
If the sample was counted in an extended geometry, correct the results obtained by multiplying by the Off Contact Geometry CF calculated in step 4.a.2)e).
- b.
Stabilized Assay Monitor (SAM)-H Iodine 131 Analysis
- 1)
Perform pre-operational checks and determine the background count rate as per DP 4562.
- 2)
Position the sample in the counter and count for a minimum of 1 minute.
- 3)
If the net count rate is greater than 100,000 cpm:
a) obtain a new sample with less air volume, or b) assay the sample using portable dose rate meters as per step 4.c.
OP 3536 Rev. 2 Page 6 of 9 INlITIALS RP Tech.
RP Tech.
CAUTION The SAM-II is a single channel analyzer "windowed-in" on the 364 KEV peak from I-131. Therefore, this monitor can only be used to assay for 1-131 activity; it will not quantify any other isotopes.
RP Tech.
RP Tech.
RP Tech.
RP Tech.
I - --- - -
INITIALS
- 4)
Calculate the airborne I-131 levels as follows:
a)
Airborne 1-131 exposure rate I-131 mRlhr =
0.056 (net cpm)
(Efficiency, c/d)(Volume, Liters) 0.056 (
net cpm)
I-131 mR/hr=
(
c/d) (
liters)
I-131 mR/hr =
RP Tech.
b)
If needed, I-13 1 airborne activity concentration 1-131 gCi/cc =
4.5E-10 (net cpm)
(Efficiency, c/d)(Volume, Liters) 1-131 gCicc =
RP Tech.
- 5)
Complete VYOPF 4533.01.
- c.
Portable Dose Rate Instrumentation
- 1)
Obtain a dose rate reading (in mR/hr) at 3 feet off contact with the sample.
RP Tech.
-Dose Rate=
mR/hr RP Tech.
- 2)
If a filter/cartridge sample, calculate the airborne activity levels as follows:
a)
Internal exposure rate, mRem/hr =
Volume =
ml Internal Exposure Rate 6E10 (mR/hr)
(Sample Volume, ml) mRem/hr RP Tech.
OP 3536 Rev. 2 Page 7 of 9
EITALS b)
If needed, airborne concentration, [tCi/cc =
1179 (mR/hr)
(Sample Volume, ml)
Airborne Concentration = ___
Cicc RP Tech.
- 3)
If a Marinelli gas sample, calculate the airborne activity levels as follows:
RP Tech.
a)
Deep Dose Exposure Rate due to Airborne Semi-Infinite Cloud, mRem/hr =
2E10 (mR/hr)
(Sample Volume, ml)
Volume =
ml DDE Rate =
mRem/hr RP Tech.
b)
If needed, airborne concentration, pCi/cc =
2920 (mR/hr)
(Sample Volume, ml)
Airborne Concentration =
-JCi/cc RP Tech.
- 4)
Complete VYOPF 4533.01.
RP Tech.
- 5.
Reporting Analysis Results
- a.
If the sample was a charcoal sample, and the 1-131 activity concentration determined in step 4 is 21E-6 p.Ci/cc I-13 1:
a) determine the need to resample and verify results using silver zeolite cartridges.
RP Tech.
- b.
Update VYOPF 3536.01, as needed.
RP Tech.
- c.
Route completed VYOPF 4533.01 to the RP Supervisor or OSC Coordinator.
RP Tech.
OP 3536 Rev. 2 Page 8 of 9
FINAL CONDITIONS
- 1.
Submit all forms for review and filing as per AP 6807.
OP 3536 Rev. 2 Page 9 of 9
SAMPLE ACCOUNTABILITY LOG Sample Location Identification (Update after each movement)
Date Time Initials
-~~
L VYOPF-3536.01 OP 3536 Rev. 2 Page 1 of 1