ML021980212
| ML021980212 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/05/2002 |
| From: | Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| OP-1905.003, Rev. 008-01-0 | |
| Download: ML021980212 (11) | |
Text
Arkansas Nuclear One - Administrative Services Document Control Friday, July 05, 2002 Document Update Notification COPYHOLDER NO: 103 TO: ANO-NRC (EMERGENCY RESPONSE COORD.) - WASHINGTON ADDRESS: OS-DOC CNTRL DESK MAIL STOP OP1 17 WASHINGTON DC 20555-DC DOCUMENTNO: OP-1905.003 TITLE: RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPING OF RC REVISION NO: 008-01-0 CHANGE NO: PC-01 SUBJECT- PERMANENT CHANGE (PC)
Z 4( If this box is checked, please sign, date, and return within 5 days.
..... ANO- 1Docket 50-313 This Q ANO-2 Docket 50-368 Signature Date SIGNATURE CONFIRMS UPDATE HAS BEEN MADE RETURN TO:
ATTN: DOCUMENT CONTROL ARKANSAS NUCLEAR ONE 1448 SR 333 RUSSELLVILLE, AR 72801 U46
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: Rad Protection Requirements for Post Accident DOCUMENT NO. CHA-GE NO.
Sampling of RC 1905.003 008-01-0 WORK PLAN EXP. DATE TC EXP. DATE N/A N/A SET # SAFETY-RELATED IPTE
-...0YES, [NO ['YES [9NO TEMP ALT r-EYES NNO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DAT -E TIM E FORM LE:
IT FORM No. CHANGE NO.
VERIFICATION- COVER SHEET 1000.006A 050-00-0 I
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE Page 1 TITLE:RAD PROTECTION REQUIREMENTS FOR POST ACCIDENT DOCUMENT NO. CHANGE NO.
SAMPLING OF RC 1905.003 008-01-0 "AFFECTEDUNIT: PROCEDURE ELECTRONIC DOCUMENT SAFETY-RELATED Z UNIT 1. UNIT 2_ El WORK PLAN, EXP. DATE [ YES !- NO TYPE OF CHANGE:
El NEW [ PC El TC F-- DELETION
[:1 REVISION El EZ EXP. DATE:
DOES THIS DOCUMENT:
- 1. Supersede or replace another procedure? El YES 0NO (IfYES, complete 1000.006B for deleted procedure.) (0CAN058107)
- 2. Alter or delete an existing regulatory commitment? [1 YES [NO (IfYES, coordinate with Licensing before Implementing.) (0CNA128509)(0CAN049803)
- 3. Require a 50.59 review per LI-101? (See also 1000.006, Attachment 15) El YES 0 NO (If50.59 evaluation, OSRC review required.)
- 4. Cause the MTCL to be untrue? (See Step 8.5 for details.) EYES ONO (IfYES, complete 1000.009A) (1CAN108904, OCAN099001, 0CNA128509, OCAN049803)
- 5. Create an Intent Change? EYES ONO (IfYES, Standard Approval Process required.)
- 6. Implement or change IPTE requirements? E7 YES C9 NO (IfYES, complete 1000.143A. OSRC review required.)
- 7. Implement or change a Temporary Alteration? EYES ONO (IfYES, then OSRC review required.)
Was the Master Electronic File used as the source document? 0YES ENO INTERIM APPROVAL PROCESS STANDARD APPROVAL PROCESS ORIGINATOR SIGNATURE: (Includes review of.13) DATE: O AT Sl ludesreview of Att. 13) DAT,/:
Print and Sign name: 7 PHONE #: Print and Sign name: Ron Schwartz PHONE #: 7992 SUPERVISOR APPROVAL: DATE: INDEP NT REVIEWER:ý
- DATE:
AA SRO UNIT TWO:** DATE: QUALITY: " DATE:
Interim approval allowed for non-intent changes requiring no UNIT SURVEILLANCE COORDINATOR (0CNA049803): DATE:
50.59 evaluation that are stopping work in progress. ...... _ ._................__ _ _ _
Standard Approval required for intent changes or changes SECT LEDER* DATE:
requiring a 50.59 evaluation. 1Ve &"- /,T "0z
- Ifchange not required to support work in progress, QUALFrY ASSURANCE: DATE:
Department Head must sign.
- If both units are affected by change, both SRO signatures OTHER SECTION LEADERS: DATE:
are required. (SRO signature required for safety related procedures only.) OTHER SECTION LEADERS: DATE:
OTHER SECTION LEADERS: DATE:
OTHER SECTION LEADERS: DATE:
OS.ICHAIRMAN/T*P..NLQAL REVIEWER(0CNA049312) DATE: OTHER SECTION LEADERS: DATE:
RIN _ L: IV D .Date: OTHER SECTION LEADERS: D R,QWRI EFFCTIVE DATE: I :rpta*l.do OTHER SECTION LEADERS: DATE:
FORM TITIE: FORM NO. CHANGE NO.
PROCEDUREWORK PLAN APPROVAL REQUEST 1000.006B 051-00-0
ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: Rad Protection Requirements for Post Accident DOCUMENT NO. CHANGE NO.
Sampling of RC 1905.003 008-01-0 29PROCEDURE l]WORK PLAN, EXP. DATE PAGE 1 OF E- ELECTRONIC DOCUMENT TYPE OF CHANGE:
[E NEW 0 PC El TC El DELETION El REVISION El EZ EXP. DATE:_____
A=I I=t'-TIr*!*lP'~
f;'1 M t-NI*1 DESCRIPTION OF CHANGE: (For each change made, include sufficient detail to describe (include step # if reason for the change.)
applicable) Corrected reference to procedure "High Activity in RCS" - procedure name reference is correct 3.1.6 but the number reference was incorrect - "2203.001" changed to "2203.020" 3.1.8 Added ITS reference for ANO-1 TS 5.5.3 3.2.4 Corrected reference to procedure "High Activity in RCS" - procedure name reference is correct but the number reference was incorrect - "2203.001" changed to "2203.020" N/A These changes do not require a 50.59 Review because:
"* Changes Correcting references to procedure titles, numbers, sections or steps of another procedure do not require a 50.59 review (OP-1000.006, Attachment 15, Item 5)
"* Changes adding references In the reference section or In the body of the procedure do not require a 50.59 Review (OP-1000.006, Attachment 15, Item 10)
FORM TITLE: . FORM NO. CHANGE NO.
I DESCRIPTION OF CHANGE 1000.0068 050-00-0
PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 1 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-01-0 1.0 PURPOSE The purpose of this procedure is to specify radiological protection requirements to be followed when obtaining a post-accident reactor coolant liquid sample.
2.0 SCOPE This procedure applies to post accident sampling of the Unit One and Unit Two reactor coolant system with less than or equal to 5% clad failure for the determination of failed fuel for emergency classification determination. This procedure also applies to sampling of the reactor coolant system, containment sump and containment air during any failed fuel level to determine the extent of the reactor core damage.
3.0 REFERENCES
3.1 REFERENCES
USED IN DEVELOPING THIS PROCEDURE:
3.1.1 ANO Emergency Plan 3.1.2 ANO's EAL Bases Document 3.1.3 1607.001, "Reactor Coolant System Sampling" 3.1.4 2607.001, "Unit 2 Reactor Coolant System Sampling" 3.1.5 1203.019, "High Activity in Reactor Coolant" 3.1.6 2203.020, "High Activity in RCS" 3.1.7 LIR LOO-0005, Dose Assessment for RCS sampling during Fuel Cladding failure.
3.1.8 ANO-l Technical Specifications, 5.5.3 "Post Accident Sampling"
3.2 REFERENCES
USED IN CONJUNCTION WITH THIS PROCEDURE:
3.2.1 1607.001, "Reactor Coolant System Sampling" 3.2.2 2607.001, "Unit 2 Reactor Coolant System Sampling" 3.2.3 1203.019, "High Activity in Reactor Coolant" 3.2.4 2203.020, "High Activity in RCS" 3.2.5 1903.033, "Protective Action Guidelines for Rescue/Repair &
Damage Control Teams" 3.3 RELATED ANO PROCEDURES:
3.3.1 1903.033, "Protective Action Guidelines for Rescue/Repair &
Damage Control Teams"
PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 2 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-01 3.4 REFERENCE TO NRC COMMITMENTS:
3.4.1 0CNA08005 (P-16724), Develop, implement, and maintain the capability for classifying fuel damage events at the Alert level threshold. This capability may utilize the normal sampling system or correlate normal sample system dose rates to coolant concentrations. Section 5.1.
3.4.2 0CNA08005 (P-16725), Develop, implement, and maintain contingency plans for obtaining and analyzing highly radioactive samples of reactor coolant, the containment sump, and containment atmosphere. The contingency plans do not have to be demonstrated. Because these are contingency plans, the staff concludes that, in accordance with 10 CFR 50.47 and Appendix E to 10 CFR Part 50 for emergency plans, these contingency plans must be available to be used by the licensee during an accident; however, these contingency plans do not have to be carried out in emergency plan drills or exercises. Complete procedure 4.0 RESPONSIBILITY AND AUTHORITY 4.1 The Manager, Radiation Protection is responsible for the overall control and implementation of this procedure.
4.2 The Radiation Protection Supervisors are responsible for directing the Health Physics Technicians that carry out the provisions of this procedure.
5.0 INSTRUCTIONS NOTE For the purpose of this procedure, post accident sampling conditions exist when plant indications show or there is reason to believe that Reactor Coolant System 1-131 activity is equal to or exceeds 10 uCi/gm.
[5.1 Post Accident Sampling For Emergency Action Level Classification]
CAUTION Post accident sampling for *5% clad failure will be performed via the normal sampling system. Due to elevated activities in the RCS, samples returned to the auxiliary building sump may cause airborne conditions in the auxiliary building. Also, an increase in radioactive effluents from the plant may occur during this evolution.
5.1.1 Chemistry will align the normal sampling system in accordance with procedure 1607.001 or 2607.001 for the affected unit, Unit 1 or Unit 2, respectively.
5.1.2 Continuous Radiation Protection coverage is required during recirculation and sampling.
5.1.3 WHEN the required flush time is complete, THEN Radiation Protection shall perform the following:
PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 3 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-01-0 A. Determine the dose rate at 12 inches (30 cm) from the designated reactor coolant system sample pipe. See Attachment 2.
- 1. Unit One - SA-229, located overhead in the hallway on the south wall, elevation 354' (Attachment 2, Figure 1).
- 2. Unit Two - 2TCD-19, located inside door 230, overhead in the hallway room 2065, elevation 354' (Attachment 2, Figure 2).
5.1.4 Report the dose reading to the affected Control Room. The Control Room will determine and report the degree of clad failure to Chemistry personnel.
5.1.5 IF the dose rate indicates >5% clad failure, or operations does not request RCS sampling.
THEN go to step 5.1.11.
5.1.6 IF the dose rate indicates :5% clad failure and operations request an RCS sample, THEN go to step 5.1.7.
5.1.7 Ensure primary sample hood ventilation is operable and in use during post accident sampling if applicable.
5.1.8 Determine radiological protection requirements for sampling activities using the expected radiological conditions given in Attachment 1:
A. Electronic dosimeter alarm set points:
dose rate - 6500 mrem/hr, dose - 100 mrem B. Air Sampling C. Respiratory protection D. Anti-contamination protection E. Multiple dosimetry F. Use of shielding 5.1.9 Brief Chemistry personnel on the expected radiological conditions and associated controls prior to performing sampling activities.
5.1.10 Allow Chemistry to perform sampling in accordance with the appropriate procedure.
PROC/WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 4 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-01-0 5.1.11 Request Chemistry to secure from sampling.
A. Sample lines should be flushed, if possible, to reduce radiation levels.
B. Perform post-sampling radiological surveys to confirm area conditions.
5.2 Post-Accident Sampling WARNING Worst case accident of 100 percent failed fuel would result in an anticipated specific activity of ten curies per milliliter of reactor coolant.
Post-accident sampling may be performed in the primary sample room or other areas of the plant using normal or evaluated sample points.
Normally this type of sampling will not be performed in the early phase of an accident, but would rather be performed days or even months after the event.
Following is a list of actions that must be taken and/or considered prior to obtaining and analyzing any sample.
5.2.1 Perform a pre-job briefing in accordance with procedure 1903.033, "Protective Action Guidelines for Rescue/Repair and Damage Control Teams".
5.2.2 Radiological Considerations A. Continuous Radiation Protection coverage is required during any re-circulation and sampling.
B. Upon establishment of recirculation or sample flow, Radiation Protection will monitor doserates.
C. Determine radiological protection requirements based upon expected conditions to address the following:
"* Electronic dosimeter alarm set points
"* Air Sampling
"* Respiratory protection
"* Anti-contamination protection
"* Multiple dosimetry
- Use of shielding
PROC./WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 5 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-01-0 D. Consider Self-Contained Breathing Apparatus (SCBA) respiratory protection to be worn by Nuclear Chemists and Health Physics technicians when taking and analyzing samples.
5.2.3 Ventilation Considerations A. Consider ventilation needs during sampling.
B. Ensure sample hoods are in service (if applicable).
C. Ensure Auxiliary Building ventilation and monitoring system is operable and in service.
5.2.4 Sample Considerations A. Pre-determine storage and disposal sites of used and unused portions of the sample.
B. Consider returning sample to the containment building if possible.
C Stationary lead glass shielding is to be used as appropriate D. Transfer sample immediately to the sample pig and secure lid.
E. Perform sample preparations in the sample hood.
5.2.5 Chemistry will perform sampling and analysis using normal procedures for line-up and analysis or evaluated sampling along with the precautions developed in the previous steps.
6.0 ATTACHMENTS AND FORMS 6.1 ATTACHMENTS 6.1.1 Attachment 1 - "Estimated Radiation Levels for 5% Fuel Cladding Failure".
6.1.2 Attachment 2 - "Survey Points" 6.2 FORMS None
PROC.JWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 6 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-01-0 ATTACHMENT 1 Estimated Radiation Levels for 5% Fuel Cladding Failure Assumptions:
- Fuel cladding failure does not exceed 5%.
- Source term consists of iodine and noble gas isotopes.
- Source term specific activity at 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> post accident is approximately 8.35+03 gCi/ml (Unit 1) and 1.24E+04 gCi/ml (Unit 2).
- Individual performing sampling will maintain whole body approximately 1.5 feet from sample and extremities approximately 0.25 feet from sample when drawing sample, and will maintain whole body approximately 2 feet from sample and extremities approximately 1 foot from sample when analyzing sample.
- Sample times: collect sample, 0.5 min., analyze sample 3.0 min.
Radiation levels Dose rates (mrem/hr) at the primary sample hood(s) as given in LIR LOO-0005 for the body locations given above:
SDE-ME (mrem/hr) DDE (mrem/hr) SDE-WB (mrem/hr)
Unit 1 (5%CF) 14669 5751 6049 Unit 2 (5%CF) 17593 6438 6595 Estimated doses to collect sample:
Unit 1 DDE 0.5 min. x 5751 mrem/hr. = 48 mrem S DE -ME 0.5 min. x 14669 mrem/hr. = 122 mrem S DE -WB 0.5 min x 6049 mrem/hr. = 50 mrem Unit 2 DDE 0.5 min. x 6438 mrem/hr. = 54 mrem SDE-ME 0.5 min. x 17593 mrem/hr. = 147 mrem SDE-WB 0.5 min x 6595 mrem/hr. = 55 mrem Estimated contact dose rate for 1:1000 dilution of maximum 5% clad failure sample:
Unit 1 - 73 mrem/hr Unit 2 - 100 mrem/hr
PROC./WORK PLAN N
O. PROCEDURE
/WORK PLAN TITLE: PAGE: 7 of 7 1905.003 RAD PROTECTION REQUIREMENTS FOR POST-ACCIDENT SAMPLING OF RC CHANGE: 008-00-0 ATTACHMENT 2 Survey Points Unit I Elev Post Accident Sampling Survey Point SA-229, 30 cm reading At Location: Elevation 354 Hallway at south wall, 12 feet In overhead. Pipe exits the wall from the UNPPR.
Survey Point, 30 cm -
- Figure 1 - Unit 1 Elev. 354 Survey Point Figure 2 - Unit 2, Elev. 354 Survey Point