ML20027C124
| ML20027C124 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/30/1982 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A390 | List: |
| References | |
| PROC-820930-01, NUDOCS 8210120656 | |
| Download: ML20027C124 (85) | |
Text
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'l DUKE POWER COMPANY OCONEE NUCLEAR STATION IMPLEMENTING PROCEDURES t
Date Issued:
March 6, 1981 1981 Revisions:
Rev. 1, April'
(
Rev. 2, May Rev. 3, June Rev. 4, July Changed Distribution and issued new #s - September Rev. 2, October Rev. 3, October REv. 4, November Rev. 5,' December 1982 Revisions:
Rev. 1, February Rev. 2, March Rev. 3, March Rev. 4, May Rev. 5, June Rev. 6, July Rev. 7, July Rev. 8, July Rev. 9, September i 8210120556 820923 FPDR ADOCK 05000269 1'F PDR 8
J TABLE OF CONTENTS i
Emergency Telephone Numbers - (06/30/82, Rev. 7)
AP/0/A/1000/01 Event Index - (03/09/82)
AP/0/A/1000/02 Unusual Event - (03/09/82) j l
AP/0/A/1000/03 Alert - (03/09/82)
AP/0/A/1000/04 Site Area Emergency - (03/09/82)
AP '0/A/1000/05 General Emergency - (03/09/82)
AP/0/A/1000/06 Procedure _for Initiating Protective Action Guides for the General Pehlic in the Emer-gency Planning Zone - (03/09/82)
)
i AP/0/B/1000/07-Procedure for Offsite Dose Calculations
-by Control Room Personnel or Emergency Coordinator during a Loss of Coolant Accident - (02/26/82)'
)
AP/0/A/1000/08 Procedure for Response Actions for Accidents /
/N Emergencies - (10/15/81)
AP/0/A/1000/10 Procedure for Emergency Evacuation of Station Personnel - (05/05/82)
Station Directive 2.9.1 Station Assembly and Evacuation Procedure -
(04/14/82)
Statica Directive 2.9.2 Emergency Response Organization - (06/23/82)
Station Directive 5.1.3 Personal Injury Procedure - (10/19/81)
PT/0/B/2000/04 Procedure for Establishment and Inspection of the Technical Support-Center - (08/09/82)
CP/1/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)
CP/2/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)
CP/3/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)
CP/1/A/2002/04B Post Accident Liquid Sampling of the Low Pressure. Injection System (12/01/81)
CP/0/B/2003/02 Estimate of Failed Fuel Based on I-131 Concentration (08/03/82)
Revision 9 September, 1982
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Page 2 i
Table of Contents (Imolementing Procedures - Continued)
CP/1&2/A/2002/05 Post Accident Caustic Injection into the Low Pressure Injection System (01-26-81)
CP/3/A/2002/05 Post Accident Caustic Injection into the Low Pressure-Injections System (01-26-81)
CP/2/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81)
CP/3/A/2002/04B Post Accident Liquid Sampling of the Low.
Pressure Injection System (12/01/81)
CP/0/A/2004/2E Post Accident Determination of Boron Concentration Using Carminic Acid (07/09/82)
CP/0/A/2004/,3C Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter - (07/09/82)
CP/0/A/2005/2D Post Accident Determination of Gamma Isotopic Activity (07/09/82)
O(,)
CP/0/B/4003/01 Procedure for Environmental Surveillance Following a Large Unplanned Release of Gaseous Radioactivity - (01/13/82)
CP/0/B/4003/02 The Determination of Plume Direction and Stctor(s) to be Monitored Following a Large Unpla_ne Release of Gaseous Activity - (05/03/82)
HP/0/B/1009/09 Procedure for Determining the Inplant Airborne Radioiodine Concentration During Accident Conditions - (07/09/81)
HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases Through Steam Relief Valves Under Post-l Accident Conditions - (05/06/82)
HP/0/B/1009/11 Projection of Offsite Dose from the Uncon-trolled Release of Radioactive Materials Through a Unit Vent - (01/28/82)
HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release - (08/13/82)
EP/0/B/1009/13 Procedure for Implementation and Verification for the Availability of a Back-Up Source of Meteorological Data - (04/23/82) 4 4
s-s Revision 9 September, 1982
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Page 3 Table of Contents (Implementing Procedures'- Continued)
HP/0/B/1009/14 Project Offsite Dose from Releases other than Through a Vent - (01/29/82)
HP/0/B/1009/15 Procedure for Sampling and Quantifying High Level Gaseous Radioiodine and Particulate Radioactivity - (07/15/82)
HP/0/B/1009/16 Procedure for Emergency Decontamination of Personnel and Vehicles on-site and from Off-site Remote Assembly Area - (03/02/82)
IP/0/B/1601/03 Environmental Equipment Checks - (08/27/82) l i
1 i
Revision 9 September, 1982
CONTAGE. COPY O
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Form SPD-1002-1 Q
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ID No: PT/0/B/2000/04 PROCEDURE PREPARATION Change (s) % \\to Q PROCESS RECORD Y Uncorporated cc[
(2) STATION:
Oconee Nuclear Station (3) PROCEDURE TITLE:
Procedure for Establishment and Inspection of the Technica M upport Center
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(4) PREPARED BY m
(5) REVIEWED BY:
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DATE:
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Cross-Disciplinary Review By:
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(6) TEMPORARY APPROVAL (IF NECESSARY):
By:
(SRO) Date:
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By:
Date:
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(7) APPROVED BY:
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(8) MISCELLANEOUS:
1 Reviewed /g p r"-J By: # 7 M Date: //f[g>
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Reviewed / Approved By:
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PT/0/B/2000/04 Pagn 1 of 3 h
DUKE POWER COMPANY V
OCONEE NUCLEAR STATION PROCEDURE FOR ESTABLISIDIENT AND INSPECTION OF THE TECHNICAL SUPPORT CENTER 1.0 Purpose This procedure provides for the establishment of the Technical Support Center and for quarterly inspection of emergency equipment and supplies necessary to activate the Technical Support Center and specifies the in-spection frequen;y and documentation requirements.
2.0 References 2.1 Oconee Nuclear Station Emergency Plan 2.2 NUREG 0654, FEMA-REP-1, REV.1, Criteria for Preparation and Eval-nation of Radiological Emergency Plans and Preparedness in Support of Nuclear Power Plants.
Oi 3.0 Time Required 3.1 Varied / quarterly test.
4.0 Prerequisite Test 4.1 Not applicable 5.0 Test Equipment 5.1 Not applicable 6.0 Limits and. Precautions 6.1 Maintain record of all documentation for a minimum of five years.
6.2 Ascertain availability of the phone line to be checked.
l 7.0 Required Station Status l
l 7.1 Not applicable 8.0 Prerequisite System Conditions 8.1 Not applicable i
Revision 4 August, 1982 i
m PT/0/B/2000/44-rage 2 of 3
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9.0 Test Method
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9.1 All emergency supplies, equipment, and telephone numbers that would be used upon activation of the Technical Support Center are to be inspected end/or reviewed on a quarterly basis.
10.0 Data Required 10.1 Not applicable 11.0 Acceptance Criteria 11.1 Periodic quarterly inspection of supplies and emergency equipment and quarterly review of telephone directories must comply with the regulations as specified in the Oconee Nuclear Station Emergency Plan and as required by NUREG 0654.
12.0 Procedure Time /Date Name 12.1 The Emergency Preparedness Coordinator or his/her designee shall use enclosures listed in 13.0 as a guide to inspect the following emer-gency ejuipment and supplies:
gs 12.1.1
(
)
Verify all items for the Technical Support Center Telephone Communication System on Enclosure 13.2 are available and
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operational.
12.1.2 Verify that the Emergency Telephone Directories are current.
12.1.3 Verify that all supplies as designated in Enclosure 13.1 are on hand for the activation of the Technical Support Center.
12.1.4 Verify that all drawings located in the Technical Support Center are up to date.
Use 13.7 as a guide.
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12.2 The Emergency Preparedness Coordinator or his/her designee shall use enclosures listed in 13.0 as a guide for setting up the Technical Support Center during an emergency, drill, and/or exercise:
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12.2.1 Each Superintendent shall be responsible for having his emergency telephone system switched to the Technical Support Center and/or Operational Support Center.
12.2.1.1 The phones for the Technical Support Center /
Operational Support Center shall be set up according to the Check-Off List in Enclosure 13.2.
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PT/0/B/2000/04 Page 3 of 3
"'T Time /Date Name 12.2.2 Follow Check-Off List for setting up the Technical Support Center, Enclosure 13.6, to determine that equipment, sup-plies, documents, manuale, procedures are in place.
12.2.3 All supplies shall be inspected after the emergency, drill and/or exercise and replenished as necessary.
13.0 Enclosures 13.1 Inventory List Checkoff 13.2 Check-off List for Setting up the Phone System in the Technical Support Center 13.3 General Arrangement of Technical Support Center 13.4 General Arrangement of Operational Support Center 13.5 Emergency Telephone Switching Diagram 13.6 Check off List for Setting up the Technical Support Center 13.7 Drawings in the Technical Support Center e
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PT/0/B/2000/04 TECHNICAL SUPPORT CENTER INVENTORY LIST C1 ENCLOSURE 13.1 Date Name 13.1.1 24 Telephones 13.1.2 Drawings (Enclosure 13.6) 13.1.3 2 Base Station Radios (a) Battery - Check. dates and/or replace 13.1.4 Telephone Directories 25 Station Directories 5 Corporate Directories 25 Emergency Telephone Directories 1 NRC Directories 2 Local Municipal Directories 13.1.5 4 Reams Copy Machine Paper 13.1.6 1 Box Telecopier Paper 13.1.7 20 Pads (writing) 13.1.8 1 Bottle Nashua X-D 3159A Developer 13.1.9 2 Boxes Pencils
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13.1.10 4 Bottles Nashua 3100 Dry Imager 13.1.11 2 Boxes Ball Point Pens 13.1.12 17 volt hand-held light 13.1.13 2 Staplers 13.1.14 2 Boxes Staples 13.1.15 1 Box Chalk 13.1.16 1 Eraser 13.1.17 4 Grease Pencils 13.1.18 2 Logbooks 13.1.19 1 Package Rubber Bands 13.1.20 1 Box Colored Magic Markers,
13.1.21 50 Bottles KI Tablets 13.1.22 1 Box 12" Printer Paper 13.1.23 1 Box Diskettes NOTE:
Emergency supplies (minimum quantities inventoried) will be restocked after any emergency or after any drill or exercise where the Technical Support Center was activated.
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OCONEE NUCLEAR STATION-PT/0/B/2000/04 ENCLOSURE 13.2 CHECK-OFF LIST FOR SETTING UP THE PHONE SYSTEM IN THE TECHNICAL SUPPORT CENTER AND OPERATIONAL SUPPORT CENTER Date/ Time Name 13.2.1 Contact'the following members of the Emergency Response
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Organization.
Make them aware that the phone line will be switched to the Technical Support Center / Operational Support Center and that the line will be out of service for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
After everyone has been notified, switch phone lines in accordance with directions given on Enclosure 13.5.
VAX VAX S&C NRC Res. Insp.
D.R. Evaluator IB&W Environmental Communicator
. ERP Dosimetry Records l Administration I
Supp. Functions Clerical Support Performance Maintenance l
I-L&P I&E Chemistry OSC l
l Operations M.M.
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j Tech. Serv.
Station Manager f
Station H.P.
.h tStation Manager Red Phone Black Phone l
Ringdown Medical j
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i 13.2.2 Secure key from Shift Supervisor to Techiifdl Support Center i
Cabinet.
Check each phone to mak,e sure that a dial tone exists and that the line is operable -- incoming and outgoing.
I.
13.2.3 Note any problems encountered and list below action taken.
I 13.2.4 Lock telephone boxes.
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13.2.5 Return telephone systems to normal service.
Revision 4 August, 1982 l
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DUKE POWER CGdPAt1Y EfERGENCY RESP 0flSE FACILITIES PT/0/B/2000/04 OC0 flee NUCLEAR STATION
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TECHNICAL SUPPORT CENTER U:IIT 1 & 2 CO:ITROL ROOM l
Commwtication Sy. stem inetudes:
Ou,tside Line (Sodhetn Bell Stjs tem)
ONS Steltchboard N
MioAoMVe Radio 7
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TelecopieA ENS (Red Phone)
HPN (Healtit Physics - NRC1 Ringdatat Phone to Off site Agencies (State FECC, Oconee ECC,
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Pickens ECC)
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GENERAL ARRANGE.'.fEMT CCtFERE!:CE E$
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PT/0/c/20co/04 DUKE POWER COMPANY
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EMERGENCY RESPONSE FACILITIES OCONEE NUCLEAR STATION-
) 3.4 OPERATIONAL SUPPORT CENTER
- Location: Unit'#3 I & E-Shop COMMUNICATION:
ONS Switchboard
- Nuclear Microwav'e Equipment Operators 16', x 9' (Kitchen Unit 1&2
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<aTh2 areas designated as the Operational Support Center has the same ve til
' shielding as-the Control Room.
n ation and apparatus have been established. Provisions for protective clothing and breathing -
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Revision 4 t /
August, 1982
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EMERGENCY (
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ENCLOSURE 13.5 S
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Emerr.cucy Telephone Switching Diagram hiones :l'iriid 1.*IIh
'lI RJJ -7:ull' cat'c suncliEs throdii at on' set af TbC activation
- 2. Blue - Indicate switches thrown as needed in TSC To Switch All l' hones tiarked Red Or Blue To:
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- a. Ilnic 1 & 2 TSC thiou switch to the right +,
- b. Unit 3 throu..uitch to left
'4, Revision 4 August, 1982,
PT/0/B/2000/04 Page 1 of 2 OCONEE NUCLEAR STATION (b
Check-off list for setting up the Technical Support Center s
ENCLOSURE 13.6 1
Date/ Time Name 13.6.1 Set up phones - (Determine that phones' have been switched in the telephone roon) 13.6.2 Set up radio.
13.6.3 Check off list of Documents needed.
Emergency Plan & Implementing Procedures Crisis Management Plan Pickens & Oconee Emergency Plan Technical Specifications FSAR General Arrangement Drawings Emergency Planning Zone maps and nomographs Safety related structures, systems and components Station Directives
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Administrative Policy Manual Various.I&E Drawings Site Drawings Emergency Procedures i
Plant Operations Drawings Fire Plan 13.6.4 Paper & pads, pencils & pens, notebooks.
13.6.5 Set uo TSC Logbook - record names of people in Technical Support Center 13.6.6 Determine if everyone has been crlled that is a part of the emergency response organization.
13.6.7 Notification Procedures Message forms Authentication Procedures 4
PT/0/B/2000/04 Page 2 of 2 OCONEE NUCLEAR STATION
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Check-off list for setting up the Technical Support Center ENCLOSURE 13.6 (Cont'd)
Date/ Time Name Crisis Telephone Directory 13.6.8 Contact Security - make sure Security is at the Control Room entrances.
Sign people in and out at that point.
13.6.9 Set up Data Displays for information update in TSC, HPC, OSC.
Assign someone to keep the information posted.
13.6.10 VAX system on line and operable.
Plant Data system l
ODCAR system 13.6.11 Transmission of information Telecopier
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Copier 13.6.12 Drawings listed on Enclosure 13.6 taken out of cabinet and placed in TSC.
I 13.6.13 Operational Support Center Personnel in place Supplies /first aid kits available Survey instruments available Dosimetry Revision 4 August, 1982
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PT/0/B/2000/04 Page 1 of 2 DRAWINGS IN TECHNICAL SUPPORT CENTER Date/
ENCLOSURE 13.7 Name i
DRAWING NUMBER TITLE 0-1 13.7.1 Site Plan 0-2 13.7.2 General Plan 0-3 13.7.3 Plot Plan 0-5 13.7.4 General Arrangement, Plan Elevation 758 + 0 0-6 13.7.5 General Arrangement, Plan Elevation 771 + 0 0-7 13.7.6 General Arrangement, Plan Elevation 783 + 9 0-8 13.7.7 General Arrangement, Plan Elevation 796 + 6 0-9 13.7.8 General Arrangement, Plan Elevation 809 + 3 0-10 13.7.9 General Arrangement, Plan Elevation 822 + 0 0-11 13.7.10 General Arrangeme.nt, Plan Elevation 838 + 0 0-12-A 13.7.11 General Arrangement, Cross Section 0-12-B 13.7.12 General Arrangement, Cross Section 0-12B-V 13.7.13 General Arrangement, Cross Section 0-12-C 13.7.14 General Arrangement, Longitudinal Sectica 0-13 13.7.15 General Arrangement, Turbine Basement 0-14 13.7.16 General Arrangement, Turbine Mezzanine 0-15 13.7.17 General Arrangement, Turbine Operating Floor 0-16 13.7.18 General Arrangement, Auxiliary 758 + 0 0-17A 13.7.19 General Arrangement, Auxiliary 771 + 0 0-17B 13.7.20 General Arrangement, Auxiliary 771 + 0 0-18A 13.7.21 General Arrangement, Auxiliary 783 + 9 0-18B 13.7.22 General Arrangement, Auxiliary 783 + 9 0-18C 13.7.23 General Arrangement, Spent Fuel Pool 0-460 13.7.24 Unit 1 React.or Building Basement 777 + 6 0-461 s
13.7.25 Unit 1 Reactor Building Ground Floor 797 + 6 Revision 4 August, 1982
PT/0/B/2000/04
. 3.7 Page 2 cf 2 Date/
Name
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DRAWING NUMBER TITLE 0-462 13.7.26 Unit 1 Reactor Building Intermediate Floor 825 + 0 0-463 13.7.27 Unit 1 Reactor Building Operating Floor 844 + 6 0-464 13.7.28 Unit 1 Reactor Building Shielding 861 + 6 0-465 13.7.29 Unit 1 Reactor Building Sectional View North 0-466 13.7.30 Unit 1 Reactor Building Sectional View East 0-467 13.7.31 Unit 1 Reactor Building Sections 0-468 13.7.32 Unit 1 Reactor Building Accessible Areas l
0-1013 13.7.33 General Arrangement Turbine Building - Basement.
0-1014 13.7.34 General Arrangement Turbine Building - Mezzanine 0-1015 13.7.35 General Arrangement Turbine Building - Operating Floor 0-1460 13.7.36 Unit 2 Reactor Building Basement 777 + 6 0-1461 13.7.37 Unit 2 Reactor Building Ground 797 + 6
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0-1462 13.7.38 Unit 2 Reactor Building Intermediate 825 + 0 v
0-1463 13.7.39 Unit 2 Reactor Building Operating Floor 844 + 6 l
0-1464 13.7.40 Unit 2 Reactor Building Top of Shielding 861 + 6 0-1465 13.7.41-Unit 2 Reactor Building Sectional View South 0-1466 13.7.42 Unit 2 Reactor Building Sectional View East 0-1467 13.7.43 Unit 2 Reactor Building Section 0-1468 13.7.44 Unit 2 Reactor Building Accessible Areas 0-2460 13.7.45 Unit 3 Reactor Building Basement 777 + 6 0-2461 13.7.46 Unit 3 Reactor Building Ground Floor 797 + 6 0-2462 13.7.47 Unit 3 Reactor Building Intermediate Floor 825 + 0 0-2463 13.7.48 Unit 3 Reactor Building Operating Floor 844 + 6 l
0-2464 13.7.49 Unit 3 Reactor Building Top of Shielding 861 + 6 l
0-2465 13.7.50 Unit 3 Reactor Building Sectional View South l
(RV) l 0-2466 13.7.51-Unit 3 Reactor Building Sectional View East
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0-2467 13.7.52 Unit 3 Reactor Building Section Revision 4 i
August, 1982
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DURE POWER COMPANY (1)
ID No:_ CP.11M/A/2002/05 Change (s)gg,'ntcd PROCEDURE PREPARATION to Incorpor PROCESS, RECORD (2)
STATION:Jconec Nuclear Station (3) PROCEDURE TITLE: Post Accid.cpt Cnustic Iniection into the 1.ow Pressure
,lniection Svstem (4) PREPARED BY:
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DATE:
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REVIEWED BY DATE:
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Cross-Disciplinary Review By: -
N/R:
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(6) TEMPORARY APPROVAL (IF NECESSARY):
By:
(S70) Date:
By:
Date:
(7) APPROVED BY:
Date:
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(8) MISCELLANEOUS:
Reviewed / Approved By:
Date:
Reviewed / Approved By:
Date:
8'27 82-q O
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O CP/1&2/A/2002/05 DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT CAUSTIC INJECTION INTO THE LOW PRESSURE INJECTION SYSTEM i
1.0 Discussion 1.1 Purpose This procedure is to provide instruction for determining the amount' and method of caustic addition into the LPI System during a LOCA.
1.2 Principle Caustic is injected into the LPI System during a LOCA to neutralize the borated water used in the Reactor Building Emergency Spray 1
System to pH 7.0 - 8.0.
The neutralization of the boric acid with b
caustic results in the formation of the salt sodium tetraborate.
This reaction of a very weak acid with a strong base is shown below:
4H B03 + 2NaOH Na2B07 + 7H O
+
3 4
2 The neutralization will inhibit the generation of hydrogen gas and promote a higher partition factor for iodine.
Calculations for the amount of caustic required for neutralization of the borated water are dependent on:
1.
An accurate estimation of the volume of borated water being used as the core flooding coolant.
2.
The boron concentration of the core flooding coolant.
3.
One (1) lb. of caustic neutralizing seventeen (17) lb's. of H B03 to pH 7.5.
3 4
The equivalent weights of (1) lb. of-NaOH to (17) lbs. of H B03 3 have been calculated from the titration curve as referenced in 5.1.
If complete volumes of the CFT's and the BWST are used, then the I
maximum amount of caustic required for neutralization of the borated water to pH 7.5 is 2800 pounds. The 2800 pounds has been calculated
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with the following considerations:
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That both CFT's and the BWST have a total volume of 403,000 gallons with a boron concentration of 2300 ppu.
2.
That the RCS has a volume of 88,000 gallons with a boron con-centration of 1000 ppu.
The addition of 2800 pounds of caustic requires approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of actual pumping time. Considering the time required for mixing, injecting, and sampling, the pH should be adjusted to within the 7.0 - 8.0 range within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
2.0 Limits and Precautions 2.1 Adequate precaution in handling sodium hydroxide must be taken.
Personnel shall wear safety goggles, face shield, pve gloves, and a protective apron.
2.2 Contact HP before work is begun. Follow all RWP's, SRWP's, and special HP instructions.
2.3 Refer to CP/0/B/2007/01A for action to be taken in the event of a caustic spill.
3.0 Mode of ooeration 3.1 Initial Conditions 3.1.1 An emergency is in effect due to a LOCA.
3.1.2 Low Pressure Injection System in operation with the LPI pumps taking suction off the BWST.
3.1.3 Reactor Building Emergency Spray System may or may not be in operation from the-BWST through spray headers.
3.1.4 Caustic Injection System aligned in normal position per.3.
3.2 Conditions for Caustic Addition l
3.2.1 Addition of caustic will be made upon authorization from Shift Supervisor.
3.2.2 Addition of caustic shall begin within 30 minutes after switchover to recirculation mode of core cooling. Recir-culation mode is in effect when the LPI pumps' suction is isolated from the BWST and is aligned to the emergency sump.
4.0 Procedure 4.1 Take the following action prior to switchover to recirculation of core cooling.
t
/N 4.1.1 Calculate the amount of caustic required for neutralization
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of the CFT's and the RCS to pH 7.5 by completing No.'s 1, 2 and 3 in Enclosure 6.1.
NOTE:
The amount of caustic required for the neutrali-zation of tne BWST contents is calculated after switchover to recirculation mode of core cooling in Enclosure 6.1 No.s 4 and 5.
4.1.2 Contact Health Physics for coverage at the Unit 1&2 caustic mix tank, which is located on the second floor of the Auxiliary Building adjacent to the Unit I freight elevator door.
4.1.3 Obtain the following keys from Health Physics.
1.
Corridor Key 2.
Freight Elevator Key 3.
LPI Door Key: Room No. 118, 119 4.1.4 See Enclosure 6.2 for a piping sketch of the Caustic Injection System on Unit 1&2.
4.1.5 Check closed position or capped off line on the valves below before mixing caustic.
Valve No.
Valve Name
's_ /
CA-33 Caustic Mix Tank Sample LWD-267 Caustic Tank Outlet Drain CA-36 Caustic Pump Suction Tell Tale CA-37 Caustic Header to Waste Evap. Feed Tank 4.1.6 Fill caustic mix tank with demineralized water to 22.5 inch level (96 gallons) by operating valve DW-120.
4.1.7 Start caustic mix tank agitator. The agitator switch is located on the chemical addition contro,1 panel adjacent to the caustic mix tank.
4.1.8 Add the calculated amount of NaOH as found in 4.1.1 into the mix tank.
However, do not exceed 350# NaOH per mix tank. Do not add caustic flakes too rapidly, and allow agitator to operate until all flakes are dissolved.
4.1.9 Check open position en the following valves.
Valve No.
Valve Name CA-103 Caustic decire Block CA-96 Caustic Recirc Block p)
CA-97 Caustic Recirc Block l
CA-34 Caustic Mix Tank Outlet
\\/
CA-35 Caustic Pump Suction
J
[
4.2 When switchover to recirculation of core cooling has been made,
.g Operations will authorize Chemistry to begin caustic ~ addition.
4.2.1 Upon authorization, start caustic pump at maximum flow setting.
The caustic pump switch is located on the chemical addition control panel. The maximum pump capacity is approximately 2 gym.
4.2.2 The six tank is in recire. Check visually for recirc to insure pump is pumping.
4.2.3 Make valve alignment per Enclosure 6.4 to allow Caustic Injection inta the LPI on Unit 1, and per Enclosure 6.5 for injection on Unit 2.
4.2.4 Pump caustic until the caustic level reaches the bottom of the gauge glass. Turn caustic pump off. Approximately 50 minutes will be required to pump one mix tank.
4.2.5 Calculate the amount of caustic required for the neutrali--
zation of the borated water added to the core from the BWST by completing Enclosure 6.1 No.'s 4 and 5.
4.2.6 Add the above calculated amount of NaOH in several'aixes if required. Do not exceed 350# NaOH per mix tank. When approximately 50% of the required amount of caustic has been added, stop caustic pump and allow LPI Core Cooling recirculation time of I-2 hours.
NOTE:
The pump rate of 1 LPI pump is approximately 3500 gym.
4.2.7 Contact Health Physics for coverage while sampling Reactor Building Sump or LPI System. -Analyze sample for pH and ppm boron.
4.2.8 From results of sample, determine the required amount of NaOH needed to complete the neutralization to 7.0 - 8.0.
4.2.9 Repeat the necessary steps for mixing, and inject the final amount of NaOH. Allow LPI core recirculation time of 1-2 hours and sample as in 4.2.7.
4.2.10 If pH of sample is above 7.0, then report results to Shift Supervisor.
_4.2.11 If neutralization to pH 7.0 to 8.0 has not been accomplished, continue NaOH addition.
4.2.12 When neutralization has been reached, return the Caustic Injection System to normal position per Enclosure 6.3.
t i
._._..,7..
y w.,
-ve-
N 5.0 References 5.1 Quantitative Chemical k2alysis, Twelfth Edition, Hamilton and Simpson,
- p. 146.
5.2 Dwg. No. PO-110A-1 Chemical Addition and Sampling System 5.3 Dwg. No. PO-120A-1, PO-102A-2 Low Pressure Injection and Core Flooding System.
5.4 ONS Technical Specifications 6.4.1.1 6.0 Enclosures 6.1 Enclosure 6.1 - Calculations of the Amount of Caustic Required for Neutralization to pH 7.5 6.2 Enclosure 6.2 - Piping Sketch of Caustic Injection System for Unit 1 and 2 6.3 Enclosure 6.3 - Normal Valve Positions for Unit 1&2 Caustic Injection System 6.4 Enclosure 6.4 - Valve Alignment for Caustic Injection on Unit 1 6.5 Enclosure 6.5 - Valve Aligament for Caustic Injection on Unit 2 Nms<
\\,j Page 1 of 2 ENCLOSURE 6.1 CALCULATIONS OF THE AMOUNT OF CAUSTIC REQUIRED FOR NEUTRALIZATION TO pH 7.5 (1) The 2 CFT's have a total volume of 15,000 gal. Obtain the most recent baron results for the A&B CFT's during normal conditions.
Average these concentra-tions and enter the average into the equation below.
Calculate the # (lbs.
of) H B03 in the CET's:
3
(1 x 10 ) (0.175) ppa) (15,000 gal) (8.35 #/ gal)
~
- CFI H B03=
3 s
(1 x lo ) (0.175)
- CFT H B03=
3 (2) The RCS has a volume of 88,000 gal. The latest RCS boron results recorded during normal conditions is ppe. Calculate the # H B0 3 3 in the RCS:
x
)
'~'
s (1 x lo ) (0.175) 3={
ppa) (88,000 gal) (8.35 #/ gal)
- RCS H B0 3
(1 x 10s).(0.175)
- RCS H B03=
3 i
(3) Calculate the # NaOH required to adjust the borated water of the CFT's and
(
the RCS to 7.5.
3 3 3 (17# H B0 )
3 3
, (1# NaOH) (
- +
- )
i 179 H B03 i
3 i
=
9 (4) The BWST has a total volume of 388,000 gal.
The latest BWST boron results
,-~q recorded during normal conditions is ppm.
Obtain from Operations
(/)
an estimate of the volume of borated water that has been dropped from the x_.
BWST:
gal.
Calculate the # H B03 added to the core from the 3
BWST:
wm-
-, - ~
-n
-w, e.
~
w
-v-y
.~.
i
- s t
l 1
Page 2 of 2 I
t ENCLOSURE 6.1 l
Amount of Water f
- BWST H B03 = (BWST Boron Conc., ppm) (Added from BWST, mal) (8.35 #/ gal) f 3
1 x los (0.175) 1 I
,(
ppe) (
gal) (8.35 #/ gal) i 8
1 x 10 (0.175)
' j
- BWST HaB03= _
(5) Calculate the # NaOH required to adjust the borated water of the BWST to 7.5.
I I
- NaOH required = (1# NaOH) (
- BWST H B0 )
{
3 3 f
17# H B03 3
I
- NaOH required =
l t
i
[
4 I
1 h
l
^
I 2
i I
i
~
(
4 F
l l
i l
,-.c.
,,a
-,n,,
,,~.--www--
me--r-,,,,,,,,--,-..em,
- n.m v.
,g n, r n,w g-r gm s m - r, wwm,,-c,wn-,~v,--,,
.v<--
--w.
i t
j s
ENCLOSURE 6.2 l
t
)
(/
PIPING SKETCH OF CAUSTIC INJECTION SYSTEM FOR UNIT 1 AND 2 I
I i
4 I
e E sd-ine l
?
Va.d e l
i
(, as 4,* a.
~
f i
.4 k i I SnN
[ Q -97 f
+
I C4-33
- M*N k
.. p y. a.,x D<i t.x
-s,
-,7 Gwis kak f-uy i
i i
J
~
2b 4 - 3F 7; u.d =/t.P P_,,.fJi i
i r
x dd JF M-65 48-t7 t
X X
b Q' e 4 - as.
ak"1T*
l l
t W so.'+ a 1 LP ?~ r Z~<,l.*e e i a4-19' en-t R
.tLP-M l ZP"rr i
r 25 i
f
- O3
& e'
~/
X r.4.w l
I i
i I
I r.
inin. W2h fue Fssd %.ot
,,s..
o....
V i
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r 1
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k _-
ENCLOSURE 6.3 s
NORMAL VALVE POSITIONS FOR UNIT 1&2 l
CAUSTIC INJECTION SYSTEM I
Step 4.2.12 i
Normal Initial Verification !
.Vnive No.
Valve Name Position Date/ Time Date/ Time CA-33 Caustic Mix Tank Sample Closed i
LWD-267 Caustic Tank Outlet Drain Closed i
CA-34 Caustic Mix Tank Outlet Open I
CA-35 Caustic Pump Suction Open j
f CA-36 Caustic Pump Suction Tell Tale Closed CA-37 Caustic Header to Waste Evap. Feed Tank Closed CA-103 Caustic Recire Block Open f
.i CA-96 Caustic Recire Block Open f "'A-97 Caustic Recire Block Open f
e
' -a-39 Caustic to Unit #1 LP Block Closed CA-62 Caustic to Unit #1 LP Block Closed i
k" Tell Tale between CA-39 & CA-62 Closed i
LP-51 Caustic Addition Open I
CA-98 Caustic to Unit #2 LP Block Closed r
CA-63 Caustic to Unit #2 LP Block Closed k
!" Tell Tale between CA-98 & CA-63 Closed
-2LP-51 Caustic Addition Open i
i 1
l l
l
i i
-.. ~
Q ENCLOSURE 6.4 VALVE ALIGNMENT FOR CAUSTIC INJECTION ON UNIT 1
- Vnive No.
Valve Name Position Initial CA-98 Caustic to Unit #2 LP Block Closed
~
-'CA-63 Caustic to Unit #2 LP Block Closed f
k" Tell Tale between CA-39 & CA-62 Closed CA-39 Caustic to Unit #1 LP Block Open CA-62 Caustic to Unit #1 LP Block Open LP-51 Caustic Addition Open CA-103 Caustic Recire Block Closed
-CA-97 Caustic Recire Block Closed CA-96 Caustic Recire Block Closed
)
0
+
b k
i r
l i
i 4
- e...
h ENCLOSURE 6.5 VALVE ALIGNMENT FOR CAUSTIC INJECTION ON UNIT 2 Valve No.
Valve Name Position Initial CA-39 Caustic to Unit #1 LP Block Closed i
l CA-62 Caustic to Unit #1 LP Block Closed k" Tell Tale between CA-98 & CA-63 Closed CA-98 Caustic to Unit #2 LP Block Open CA-63 Caustic to Unit #2 LP Block Open 2LP-51 Caustic Addition Open CA-103 Caustic Recire Block Closed CA-97 Caustic Recire Block Closed CA-96 Caustic Recire Block Closed O'
J l
a l
{
i I
t
~1
g", '
01.0idY Form SPD-1002-1 a-
_ p.
l
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(
DUKE POWER Collt'ANY (l) 1 11 No:,Crf,7/,Af2co7, fog.
PROCEDURE PREPARATION Cli.uine (n)fg _to PROCESS RECORD
/ L incorporated (2) STATION:
Oconee N clear Station A
(3)_ PROCEDURE TITLE: Post Accident Caustic lidection into t he 1.ow Prenripyc _
Injection System (4). PREPARED EY:
/.
DATE:
/# I *' 5'O (5) REVIEWED BY:
DATE:
[
_8_!
Cross-Disciplinary Review By: [l7b(*.[ g,e:
N/R:
^
3,,7
/
(6) TEMPORARY APPROVAL (IF NECESSARY):
By:
(SR0)
Date:,,
Sy:
Date:
(7) APPROVED BY:
l g.
11 ate:j M
)
(S) MISCELLANECUS:
Reviewed / Approved By:
Date:
' Reviewed / Approved By:
Date:_
( 77 t'z.
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(
kh-m\\ )2.~11 kv
1.
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\\s_s' CP/3/A/2002/05 l
t DUKE POWER COMPANY j
OCONEE NUCLEAR STATION POST ACCIDENT
?
CAUSTIC INJECTION INTO THE LOW PRESSURE INJECTION SYSTEM
+
i 1.0 Discussion 1.1 Purpose i
This procedure is to provide instruction for determining the amount and method of caustic addition into the LPI System during a LOCA.
i 1.2 Principle I
Caustic is injected into the LPI Systes during a' LOCA to neutralize
[
f the borated water used in the Reactor Bailding Emergency Spray
(
System to pH 7.0 - 8.0.
The neutraliration of the boric acid with caustic results in the formation of the salt sodium tetraborate.
[
This reaction of a very weak acid with a strong base is shown below:
4H B03 + 2NaOH + Na2 4B07 + 7H O
[
3 2
\\
The neutralization will inhibit the generation of hydrogen gas and i
promote a higher partition factor for iodine.
l 1
Calculations for the amount of caustic required for neutralization of the. borated water are dependent on:
~
t 1.
An accurate estimation of the volume of borated water being used as the core flooding coolant.
2.
The baron concentration of the core flooding coolant.
3.
One (1) lb. of caustic neutralizing seventeen (17) lbs. of l
H B03 to pH 7.5.
f 3
i The equivalent weights of (1) lb. of NaOH to (17) lbs. of H B0 been calculated from the titration curve as referenced in 5.1.
3 3 have t
If complete volumes of the CFT's and the BWST are used, then the maximum amount of caustic required for neutralization of the borated I
'~')
water to pH 7.5 is 2800 pounds. The 2800 pounds has been calculated l
)-
with the following considerations:
i i
t
...., -,.., _. _.. ~
.,-.m
,~
Ih 1.
That both CFT's and the BWST have a total volume of 403,000 I
gallons with a boron concentration of 2300 ppe.
2.
That the RCS has a volume of 88,000 gallons with a boron con-f centration of 1000 ppa.
The addition of 2800 pounds of caustic requires approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of actual pumping time. Considering the time required for i
mixing, injecting, and sampling, the pH should be adjusted to within the 7.0 - 8.0 range within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
t l
2.0 Limits and Precautions i
2.1 Adequate precaution in handling sodium hydroxide must be taken.
i Personnel shall wear safety goggles, face shield, pve gloves, _ and a protective apron.
l 2.2 Contact HP before work is begun. Follow all RWP's, SRWP's, and special HP instructions.
2.3 Refer to CP/0/B/2007/01A for action to be taken in the event of a caustic spill.
3.0 Mode of Operation (h
t'
)
3.1 Initial Conditions 3.1.1 An emergency is in effect due to a LOCA.
3.1.2 Low Pressure Injection System in operation with the LPI pumps taking suction off the BWST.
l 3.1.3 Reactor Building Emergency Spray System may or may not be in operation from the BWST through spray headers.
t 3.1.4 Caustic Injection System aligned in normal position per
,.3.
3.2 Conditions for Caustic Addition 3.2.1 Addition of caustic will be made upon authorization from Shift Supervisor.
3.2.2 -
Addition of caustic shall begin within 30 minutes after switchover to recirculation mode of core cooling.
Recir-culation mode is in effect when the LPI pumps' suction is isolated from the BWST and is aligned to the emergency sump.
l 4.0 Procedure m
)
4.1 Take the following action prior to switchover to recir:ulation of core ccoling.
l l
3
.~
\\
\\s,,/-
4.1.1 Calculate the amount of caustic required for neutralization of the CFT's and the RCS to pH 7.5 by. completing No.'s 1, t
2 and 3 in Enclosure 6.1.
NOTE:
The amount of caustic required for the neutrali-zation of the BWST contents is calculated after i
switchover to recirculation mode of core cooling in Enclosure 6.1 No.'s 4 and 5.
4.1.2 Contact Health Physics for coverage at the Unit 3 caustic i
mix tank, which is located on the first floor of the Auxiliary Building at the Unit 3 BAMT.
1 i
4.1.3 Obtain the following keys from Health Physics.
[
1.
Corridor Key 2.
Freight Elevator Key l
3.
3RIA-36 Key for area on Auxiliary Building 'econd floor where valves 3CA-39, 3CA-58, 3CA-62 and 3LP-51 are located.
t 4.1.4 See Enclosure 6.2 for a piping sketch of the Caustic Injection System on Unit 3.
I 4.1.5 Check closed position or capped off line on the valves gs\\
below before mixing caustic.
.g%.)
p Valve No.
Valve Name I
3CA-33 Caustic Mix Tank Sample 3LVD-267 Caustic Tank Outlet Drain
~
3CA-36 Caustic Pump Suction Tell Tale 4.1.6 Fill caustic mix tank with demineralized water to 22.5
. +
inch level (96 gallons) by operating valve 3DW-120.
4.1.7 Start caustic mix tank agitator. The agitator switch is located on the chemical addition control panel at the Unit 3 BAMT.
4.1.8 Add the calculated amount of Na0H as found in 4.1.1 into the mix tank. However, do not exceed 350# NaOH per mix I
tank. Do not add caustic flakes too rapidly, and allow j
agitator to operate until all flakes are dissolved.
i 4.1.9 Check open position on the following valves.
t Valve No.
Valve Name f
i 3CA-103 Caustic Recire Block l
(g 3CA-96 Caustic Recire Block i
j 3CA-97 Caustic Recirc Block l
N- /
Caustic' Mix Tank Outlet 3CA-35 Caustic Pump Suction t
s.
4-
+
.~
t
~ "
.( N) i
\\s_,/
4.2 When switchover to recirculation of core cooling has been made, Operations will authorize Chemistry to begin caustic addition.
4.2.1 Upon authorization, start caustic pump at maximum flow setting.
The caustic pump switch is located on the chemical addition control panel. The maximum pump capacity is approximately 2 gpa.
i 4.2.2 The mix tank is in recire.
Check visually for recire to i
+
insure pump is pumping.
4.2.3 Make valve alignment per Enclosure 6.4 to allow Caustic Injection into the LPI on Unit 3.
4.2.4 Pump caustic until the caustic level reaches the bottom of
[
the gauge glass. Turn caustic pur.p off. Approximately 50 i
minutes will be required to pump one mix tank.
j i
4.2.5 Calculate the amount of caustic required for the neutrali-l zation of the borated water added to the core from the BWST by completing Enclosure 6.1 No.'s 4 and 5.
+
4.2.6 Add the above calculated amount of NaOH in several mixes if required. Do not exceed 350# NaOH per six tank. When I
-s approximately 50* of the required amount of caustic has
)
been added, stop caustic pump and allow LPI Core Cooling g
N- /
recirculation time of I-2 hours.
t NOTE:
The pump rate of 1 LPI pump is approximately i
3500 gpa.
4.2.7_
Contact Health Physics for coverage while sampling Reactor Building Sump or LPI System. Analyze sample for pH and i
ppm baron.
i 4.2.8 From results of seeple, determine the required amount of f
NaOH needed to complete the neutralization to 7.0 - 8.0.
4.2.9 Repeat the necessary steps for mixing, and inject the final amount of NaOH. Allow LPI core recirculation time i
of I-2 hours and sample as in 4.2.7.
4.2.10 If pH of sample is above 7.0, then' report results to Shift
[
Supervisor.
4.2.11 If neutralization to pH 7.0 to 8.0 has not been accomplished, f
continue NaOH addition.
j:
4.2.12 When neutralization has been reached, return the Caustic l
Injection System to normal position per Enclosure 6.3.
[
(/
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- [
f t
t
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5 i:
r f
i i
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5.0 References i
t t
5.1 Quantitative Chemical Analvsis, Twelfth Edition, Hamilton and Simpson,
- p. 146.
j 5.2 Dws. No. PO-110A-3 Chemical Addition and Sampling System l;
5.3 Dwg. No. PO-102A-3 Low Pressure Injection and Core Flooding System.
5.4 ONS Technical Specifications 6.4.1.1 i
6.0 Enclosures 6.1 Enclosure 6.1 - Calculations of the Amount of Caustic Required for i
i Neutralization to pH 7.5 i
6.2 Enclosure 6.2 - Piping Sketch of Caustic Injection System for Unit 3.
{
6.3 Enclosure 6.3 - Normal Valve Positions for Unit 3 Caustic Injection System j
6.4 Enclosure 6.4 - Valve Alignment for Caustic Injection on Unit 3 i
i
+
l i
t i
t 1
I i
t i
6 i
s t
t
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,_-e.~wy m,,m,,,
.,,.,%..m.re,.
,.. -.. ww.
.w vp
+-
.9M 7-
~
Page 1 of 2 f
ENCLOSURE 6.1 I
CALCULATIONS OF THE AMOUNT OF CAUSTIC REQUIRED FOR NEUTRALIZATION To pH 7.5 l
(1) The 2 CFT's have a total volume of 15,000 gal.
Obtain the most recent boron results for the A&B CFT's during normal conditions. Average these concentra-l tions and enter the average into the equation below. Calculate the # (1bs.
of; fi 30 3 3 in the CFT's:
herase Boron Conc., pa) Woh M m) M # gad
'f
- CFT H B03=
3 8
(1 x 10 ) (0.175) i i
- CFT H B03={
PPs) (15,000 gal) (8.35 #/ gal) 3 (1 x 10s) (0.175) i
- CIT H B03=
4 3
i (2) The RCS has a volume of 88,000 gal. The latest RCS boron results recorded
}
during normal conditions is
_ ppe.
Calculate the # H B0 3 3 in the
)
RCS*-
O i
- RCS H B0 -
I*
3 3 (1 x 10s) (0.175)
I
- RCS H B03=(
nm) (88,000 gaO (8.35 # gaO 3
s (1 x lo ) (0.175)
I
- RCS H B03=
3 l
(3) Calculate the # NaOH required to adjust the borated water of the CFT's and the RCS to 7.5.
1
3 3 3 t
(17# H B0 )
[
3 3
, (1# NaOH) (
- +
- )
[
17# H B0 3 3
=
4 I
(4) The BWST has a total volume of 388,000 gal. The latest BWST boron results 3
recorded'during normal conditions is ppm.
Obtain from Operations
)
an estimate of the volume of borated water that has been dropped from the Nd BWST:
gal. Calculate the # H B03 added to the core from the 3
BWST:
l
,r.
. s a.
r
[
- l...- -
L l
h t
Page 2 of 2 4
ENCLOSURE 6.1 i
i Amount of Water
)
- BWST H 803 = (BWST Baron Conc., pos) (Added from BWST. sal) (S.35 #/ tal) f 3
1 x 10s (0.175)
{
t
(
PPe) (
gal) (8.35 #/ gal)
=
1 x 10 (0.175) 8
- BWST H 903=
~
3 I
(5) Calculate the # NaOH required to adjust the borated water of the BWST to l
l 7.5.
- NaOH required = (1# NaOH) (
- BWST H B0 )
4 3 3 17# H B03 3
i
- NaOH required =
i i
l 4
l 1
j.
I i
4 L
F 2
i r
1 i
8 i
i i
e h'
I i
-}
}
...a..
_ _ _. _ _ _ _ _.... _ _. _...... _ _.. _. _. _ _. _.... _. _... _ _.. _ _. _....... _ _ _... ~. _ _ _...,
F
['
i ENCLOSURE 6.2 l
t PIPING SKETCH OF CAUSTIC INJECTION g
INJECTION SYSTE!f FOR UNIT 3
}
3 D u - I a.=
v.. + c l
[
f d A m.2 dis.
l Mix T
Ta n k.
[ JC d - 97 l
r JLub-913
- s.,
X sea-v.
x x
x bu 3two-141 3 04 'II i
o Te 4-N i+y h/a.t4a.
l 3 c.A - 14 l 4 4 k.
)(sea-3r i
i 3c.4-35 T kn;+ 3 LP?. p i
5 %4..
i Pre 3es.19 sea - sz.
ZLP-S~l I gy y x
M-O zu -us X f 'c' - n a
~,., g O
M t
j
~
1 l
c,
^
' h ENCLOSURE 6.3 i
NORMAL VALVE POSITIONS FOR UNIT 3 CAUSTIC INJECTION SYSTEM
'f Step 4.2.12 Normal Initial Verification.
}
Vnive No.-
Valve Name Position Date/ Time Date/ Time f
-Caustic Mix Tank Sample Closed
' 3DiD-267 Caustic Tank Outlet Drain Closed f
3CA-34 Caustic Mix Tank Outlet Open
^3CA-35 Caustic Pump Suction Open l
I 3CA-36 Caustic Pump Suction Tell Tale Closed
{
3CA-103 Caustic Recire Block Open h
1 3CA-96 Caustic Recire Block Open 3CA-97 Caustic Recire Block Open f
CA-39 Caustic to Unit #3 LP Block Closed i
}
l
,-62 Caustic to Unit #3 LP Block Closed i
]
3CA-58 k" Tell Tale between 3CA-39 & 3CA-62 Closed 3LP-51 Caustic Addition Open k
i I
i b
1
}
t I
l l
t 1,
t i
2 f
i i
t k
I I
4' i
..~
-. -. -.., -...,.. -...... _ --....-.-....-~ -..
.,,_ _...,.,_, -...~,-., -
-.,aa.
r
(
' ENCLOSURE 6.4 VALVE ALIGNMENT FOR CAUSTIC INJECTION ON UNIT 3 i
I Valve No.
Valve Name Position Initial t
3CA-58 k" Tell Tale between 3CA-39 & 3CA-62 Closed j
.3CA-39 Caustic to Unit #3 LP Block Open 3CA-62 Caustic to Unit #3 LP Block Open i
3LP-51 Caustic Addition Open t
.1 3CA-103 Caustic Recire Block Closed 3CA-97 Caustic Recire Block Closed 3CA Caustic Recirc Block Closed s
f; I
+
i t
I k
i v
l i
f r
l i
i f
i b
,,,,u w
y
-,,.y.
c==or.q,,..w-.--,4,
...,,+,-,.mwem.-%,-,w er
,w w.w w.w,,w - e rw
,--.,+,p+#
CONIROL COPY O
mow 0**
Q Form SPD-1002-1 DUKE POWER COMPANY (1)
ID No: CP/0/B/2003/02 PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Estimate of Fr.iled Fuel Based on I-131 Concentration l
(4) PREPARED BY:
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DATE:
8b/7 L (5) REVIEWED BY:
DATE:
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Cross-Disciplinary Review By:
,w (6) TEMPORARY APPROVAL (IF NECESSARY):
p By:
(SRO) Date:
By:
m Date:
(7) APPROVED BY: l Date:
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(8) MISCELLANEOUS:
Reviewed / Approved By:
Date:
Reviewed / Approved By:
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CP/0/B/2003/02 e
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DUKE POWER COMPANY t
OCONEE NUCLEAR STATION-j ESTIMATE OF FAILED RIEL BASED ON I-131 CONCENTRATION t
t i
1.0 Purpose
'l This procedure describes the method for calculating the number of failed i
fuel pins and the percent failed fuel for four fuel conditions using the t
I-131 concentration (in pCi/el) in the Reactor Coolant System (RCS).
'l i
2.0 Limits and Precautions 2.1 The numbers obtained by using this procedure are at best, estimates
- only, i
2.2 All formulas quoted are based upon equilibrium full power core j
If fuel damage is suspected to have occurred during times of-1 C
reduced power or near the time of significant power change, the core l
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I-131 inventory must be adjusted by using Enclosure 10.2.
This is i
the correction factor Y.
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l 2.3 All values given are normalized to volumes of coolant at normal reactor coolant system pressure and temperature. To correct for other RCS system temperatures or RCS sample temperatures, use
- 0.1.
This is the correction factor X.
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2.4 The decay of Te-131 to I-131 has been neglected as insignificant in this analysis.
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2.5 Iodine spiking may occur after a shutdown or significant power
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4 -
change. Data from other nuclear power plants have shown that the
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iodine spiking process has been observed to occur during a period of E
1 to 3 days after the change or shutdown. However, the spike seems i
l to peak during the period from 4 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the change.
1-131 concentrations can increase by a ' factor of 2 to 25 above the equilibrium levels during these times, although an increase over a factor of 10 is unusual and would only Le seen at a shutdown. ' Increases by a factor of 2 to 3 are typical for a significant power decrease -(i.e.,
100% to 50% power).
Do not misinterpret this temporary' change for i
~
fuel failure if there is no other evidence of fuel damage.
Other evidence of fuel damage can be constituted by any indication of inadequate core cooling, loose parts indication, high incore thermo-l lf couple indication, etc.
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2.6 If estimates for fuel failure are needed for fuel conditions other
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than those' covered by the four cases described below, or if more accurate fuel failure data is'needed, see Section 7.0 of this pro-g cedure.
2.7 The following four cases cover a very board range of core conditions.
Choose the one that best suits the existing conditions.
}
t 2.8. Follow up as necessary with Babcock and Wilcox site managers depending.
on tha plant situation.
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i 3.0 case I - Normal Operation 3.1 Initial Conditions 3.1.1 The conditions which pertain to Case I - Normal operation are as follows:
i 3.1.1.1 Normal reactor operation at any power or shutdown with no unusual conditions prior to shutdown.
Adequate core cooling has been maintained.
i 3.2 Procedure
}
l 3.2.1 If 3.1.1 describes the core conditions, use the follcwing formulas to calculate the range of failed fuel values.
j Evaluate correction factors X and Y by using Enclosures 10.1
(
and 10.2.
3.2.1.1 (Measured I-131 concentration pCi/ml)(X)(Y)
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=
!i 3.5 x 10~3 pCi/ml
= Number of failed pins (Max. expected and best estimate) f 3.2.1.2 (Measured I-131 concentration pCi/al)(X)(Y)
=
5 pCi/ml 4.9 x 10~3
= Number of failed pins (Min. expected)
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3.2.1.3 (Measured I-131 concentration pCi/ml)(X)(Y)
=
t 1.8 pCi/al t
= Percent failed fuel (Max. expected and best estimate) i 3.2.1.4 (Measured I-131 concentration pCi/ml)(X)(Y) l
=
t
(
2.5 pCi/ml l
~~-
= Percent failed fuel (Min. expected) i
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NOTE:
Values for I-131 concentration in pCi/al for Oconee at normal operating-i 3 and conditions are between 1.0 x 10 pCi/al.
l 5.0 x 10~1 4.0 Case II - Macroscopic Clad Damage
)
4.1 Initial Conditions 4.1.1 The conditions which pertain to Case II - Macroscopic clad j
damage are as follows i
4.1.1.1 Normal reactor operation at any power, or shutdown-where some mechanical clad failure (i.e., a loose
[
part monitor indication) or a flow induced i
failure is suspected. The core has adequate cooling and no significant fuel overtemperature is observed.
l 4.2 Procedure
-l 4.2.1 If 4.1.1 best describes the core conditions, use the j
following formulas to calculate the range of failed fuel i
values. Evaluate correction factors X and Y by using 0.1 and 10.2.
[
4.2.1.1 (Measured I-131 concentration pCi/al)(X)(Y)
=
pCi/ml l
5.5 x 102
= Number of failed pins (Max. expected)
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4.2.1.2 (Measured I-131 concentration pCi/ml)(X)(Y)
=
16.5 x 102 pCi/al
= Number of failed pins (Best estimate) l 4.2.1.3 (Measured I-131 concentration pCi/ml)(X)(Y)
=
27.4 x 102 pCi/ml I
= Number of-failed pins (Min. expected)
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4.2.1.4 (Measured I-131 concentration pCi/ml)(X)(Y)
=
t 27.9 pCi/ml
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= Percent failed fuel (Max. expected) i 5
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l 4.2.1.5 (Measured I-131 concentration pCi/al)(X)(Y) =
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s 83.7 pCi/a1 j
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= Percent failed fuel.(Best estincte)
I 4.2.1.6 (Measured I-131 concentration pCi/al)(X)(Y)
=
f
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139.5 pCi/ml I
= Percent failed fuel (Min. expected)
}
l 5.0 Case III - Severe Fuel Overtemperature
.j 5.1 Initial Conditions 5.1.1 The conditions which pertain to Case III - Severe Fuel.
Overtemperature are as follows:
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5.1.1.1 TMI type accident where there has been an abnormal shutdown and it is suspected that the fuel has been at least partially uncovered for a period of time greater than a few minutes. Voiding in the core is detected by high incore thermocouple readings and loss of margin to saturation. Fuel clad oxidation is-detected by excess hydrogen in
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the containment or in the reactor coolant sample; I
however, no fuel melting is suspected.
a 5.2 Procedure l
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5.2.1 If 5.1.1 best describes the core conditions, use the following formulas to calculate.the range of failed fuel values. Evaluate correction factors X and Y by using Enclosures 10.1 and 10.2.-
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l 5.2.1.1 (Measured I-131 concentration pCi/ml)(X)(Y)
=
2.4 pCi/al
= Number of failed pins (Max. expected) f f
5.2.1.2 (Measured I-131 concentration pCi/ml)(X)(Y)
=
1 2.9 pCi/al l
= Number of failed pins (Best estimate) 5.2.1.3 (Messured I-131 concentration pCi/ml)(X)(Y)
=
'~
-3.2 pCi/ml
= Number of failed pins (Min. expected) i
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5.2.1.4 (Measured I-131 con entration pCi/ml)(X)(Y)
=
1255 pCi/al
= Percent failed fuel (Max. expected) l 5.2.1.5 (Measured I-131 concentration pCi/ml)(X)(Y).
l
=
l 1535 pCi/ml i
= Percent failed fuel (Best estimate) 1 i
5.2.1.6 (Measured I-131 concentration pCi/al)(X)(Y)
=
)
1675 pCi/ml
= Percent failed fuel (Min. expected) 6.0 Case IV - Fuel Melting l
1 6.1 Initial Conditions i
6.1.1 The cotiditions which pertain to Case IV - Fuel Melting, are
[
as follows:
l 6.1.1.1 Severe accident where there has been an abnormal
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shutdown and the core is uncovered for a long period of time.
Incore thermocouple temperature readings are above 2300*F for a long period of time. Fuel melting is suspected (i.e., fuel temp-1 erature exceeds 5000'F) and is verified by the in-I ability to operate the incore instrumentation i
system properly.
1 f
6.2 Procedure 6.2.1 If 6.1.1 best describes the core conditions, use the f
following formulas to caluclate the failed fuel values.
Evaluate correction factors X and Y by cafag Enclosures 10.1. and 10.2.
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6.2.1.1 (Measured I-131 concentration pCi/ml)(X)(Y)
=
5.5 pCi/ml l
= Number of failed pins (Best estimate)
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6.2.1.2 (Measured I-131 concentration pCi/ml)(X)(Y)
=
2790 pCi/mi O
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= Percent of failed fuel (Best estimate) l
+
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7.0 Case V - Other Fuel Conditions s
7.1 If fuel conditions other than those described above exist, or if a more detailed failed fuel estinatica is desired for either coergency i
or normal operation, contact the appropriate B&W Site Managers or the Crisis Management Center for assistance.
l 8.0 Data Disposition 8.1 When plant conditions dictate that the Technical Support Center (TSC) is not necessary to the Safe Operation of ONS:
j 8.1.1 Deliver Enclosures 10.4 - 10.7 to the Station Chemist in the Technical Services Building.
Deliver a copy to the Primary Chemistry Supervisor.
~
8.2 When plant conditions, addressed in the Emergency Plan, dictate that the TSC be manned:
l 8.2.1 Deliver Enclosures 10.4 - 10.7 to the Station Chemist in the TSC. Deliver a copy of Enclosures 10.4 - 10.7 to the Power Chemistry Supervisor in the Operational I
Support Center (OSC).
i 9.0 References 9.1 Letter of 4/14/82 from R. Michael Glover to C. C. Jennings,
Subject:
" Failed Fuel Estimating" 9.2 ONS Emergency Plan,Section II.D i
9.3 MNS Administrative Procedure AP/0/A/5500/33 i
10.0 Enclosures 10.1 Density Correction Factor, (X)
I 10.2 Core I-131 Inventory Correction Factor, (Y) t 10.3 Examples i
i 10.4 Failed Fuel Calculations - Case I 10.5 Failed Fuel Calculations - Case II 10.6 Failed Fuel Calculations - Case III l
10.7 Failed Fuel Calculations - Case IV em s_ -
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Pag 2 1 of 1 t
b I
Q ENCLOSURE 10.1 i
DENSITY CORRECTION FACTOR (X) t Find the appropriate RC System temperature at the time of accident.
Find the approximate temperature at which the RC saeples are taken. The intersection of both numbers is the density correction factor, X.
' i NOTE:
Normal RC System sample temperature is approximately 90*F.
Use this
-temperature if no other information is available.
E I
I RCS Sample Temperature 'F
(
80 90 100 j
100
.996
.998 1
f,h G/
150
.983
.985
.987 i
200
.966
.968
.970 t
l 250
.945
.947
.949 300
.921
.923
.924 RCS i
Temperature 350
.894
.895
.897 t
- F 1
400
.862
.864
.865 t
450
.827
.828
.830 7
500
.787
.788
.790
[
550
.739
.740
.741 l
560
.728
.729
.731
- l 570
.717
.718
.719 580
.706
.708
.708 N
590
.693
.694
.695 i
i 600
.680
.681
.683 I
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Pag 2 1 of 1 ENCLOSL1tE 10.2 CORE I-131 INVENTORY CORRECTION FACTOR (Y) 10 2.1 Situation 1:
Use the following equation to calculate (Y) at power operation (except 0%) where the power level has not changed more than i 10% within the last 22 days.
Eq. 10.2.1.1 Y = 100 p
Where:
Y = the Core I-131 inventory correction factor.
FL = the power level, in %, at the suspected time of fuel failure.
10.2.2 Situation 2:
Use the following equation to calculate (Y) at times other than covered by Situation 1 above.
100 I
Eq. 10.2.2.1 Y=
(PL )(e~A') + (PL )(1-e-AE) g g
V Where:
Y
= the core I-131 inventory correction factor.
PL1 = the initial power level before the power change.
PLg = the final power level before/at the suspected time of fuel failure i
1 A
= the decay constant for I-131, 0.084 day t
=tt+t2 tt = the median time, in days, to make the power change from PL to PL.
t g
t2 = the time, in days, after the final power level (PL,)
is reached that the fuel failure is suspected to have occurred.
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ENCLOSURE 10.3 s
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EXAMPLES l
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Problem 1 l
b a.
Power level has been decreased from 85% to 50%.
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b.
This pcwer change took four hours and occurred between 1200
[
and 1600. T at 50% is 570*F.
AVG At 1800 a loose part monitor alarm goes off indicating & loose object j
c.
in the core. The reactor is not tripped.
j d.
' A Chemistry team is immediately dispatched to take a sample RC System j
t as failed fuel is suspected.
Chemistry sample indicates I-131 concentration is 10.0 pCi/ml.
e.
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Part 1.
Determine the best estimate of the number of failed pins.
Part 2.
Determine the best estimate of percent failed fuel.
Solution This is Case II, Section 4.0 Use equation 4.2.1.2 for Part 1 Use equation 4.2.1.5 for Part 2 Measured I-13'i concentration pCi/ml p,
7, (X)(Y) = Number of failed pins 2
16.5 x 10 pCi/ml Determine X: Enclosure 10.1 T
is 570*F at 50%.
N b e RCS Sample Temperature 4
is 90*F Therefore, X =.718 4-Determine Y: Enclosure 10.2
~1 A7 =.0864 day t = (4) + (2) = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 2
Remember, t is the median time to make a power change plus the difference between the time when the damage is suspected and the time the new power level s
is reached.
1 da Convert t to days t = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> x
=.167 days r
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i ENCLOSURE 10.3 I
EXAMPLES I.
I*
100 (85)e- (.08M day
') (.167 day) + (50) 1-e - (.0864 day ') (.167 day) 4 I"
Y = (85)(.9857) + (50)(.0143)
= 1.183 P
e Part 1.
10 pCi M I
(.718) (1.183) 51.5 = 52 failed pins Answer 16.5 x 102 pCi/al i
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Pa 2.
Measured I-131 Concentration pCi/ml (X)(Y) = % failed fuel
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3 83.7 pCi/ml
't 8 7pi 1 (.718) (1.183) = 0.1% failed fuel Answer I
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Peg 2 3 of 8 N
ENCLOSURE 10.3 EXAMPLES j
4 Problem 2' The reactor has just tripped instantly from 100% power due to a mal-a.
functioning instrument. There were no unusual conditions prior to the trip.
b.
T is now 557'F at 0% power.
AVG The operator, while'having no reason to suspect failed fuel, is curious-c.
about the amount of failed fuel present now following the trip.
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d.
A Chemistry team is sent to take an RC sample 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the trip.,
The Chemistry sample gives an I-131 concentration of 2.0 x 10 pCi/al.
I 2
e.
(A typical value for a normally operating plant.
See Note under Case I, I
Section 3.0) i 4
f.
Chemistry personnel also indicate that RC sample temperature is 100*F.
j i
Part 1.
Determine the maximum expected number of failed fuel pins.
[
Part 2.
Determine the maximum expected percent failed fuel in the core.
f Solution i
This is case I, Section 3.0 Use equation 3.2.1.1 for Part 1 Use equation 3.2.1.3 for Part 2 l
+
Measured I-131 concentration pCi/mi Part 1.
(X)(Y) = Number of failed pins
_3 3.5 x 10 pCi/ml Determine X: Enclosure 10.1 RC Temperature is 557*F at 0%
RC sample temperature is 100*F
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Therefore, X 3.732 i
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ENCLOSURE 10.3 EXAMPLES t
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I Determine Y: Enclosure 10.2-f Situation 2:
t = 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> x
=.5 days 2
r.
t f
1 100 j
(100) e (.0864) (.5) + (0) 1-e -(.0864) (.5)
L Y = 1.044 f
i NOTE:
If t = 0 or a sample was taken immediately, Y = 1.0.
I
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Part 1. 2.0 x 10 pCi/ml (.732)(1.044) = 4.4 f
2
~3 f
Os 3.5 x 10 pCi/al or E 4 to 5 failed pins Answer i
.t Pa t 2.
Measured I-131 Concentration pCi/ml (X)(Y) = % failed fuel 1.8 pCi/ml i
2.0 x 102 f
uCi/ml (.732) (1.044) =.0085 % failed fuel 1.8 pCi/ml i
The above numbers are indicative of normal operation.
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Answer i
NOTE:
I-131 spiking may be a problem here.
See Section 2.5.
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Pagm 5 of 8 p
ENCLOSURE 10.3 EXAMPLES i
Problem'3 a.
Power level has been between 50% and 65% for the last 30 days and is pre-sently at 60% at 1800.
b.
T is 3 575'F at 60% power.
i AVG c.
It is desired to see if any significant failed fuel exists in the core even though no abnormal occurrences have taken place.
d.
At 2200 the same day, a Chemistry sample is taken of the RC system.
2 The Chemistry sample indicates I-131 concentration is 3.9 x 10 pCi/ml; e.
Part 1.
Determine the best estimate of the number of failed pins.
Part 2.
Determine the best estimate of the % failed fuel.
Solution This is Case I, Section 3.0 Use equation 3.2.1.1 for Part 1 Use equation 3.2.1.3 for Part 2 Measured I-131 concentration pCi/ml Part 1.
(X)(Y) = Number of failed pins 3.5 x 10 8 pCi/ml Determine X: 0.1 T
is 575*F at 60% power AVG Assure RCS sample temp. of 90*F Therefore, X E.713 Determine Y: Enclosure 10.2 Situation 1 Y = 100 = 1.67 9
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- a ___.
Page 6 of 8 l
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ENCLOSURE 10.3 EXAMPLES
}
2 pCi/al (.713)(1.67) = 13.27 f
l Part 1.
3.9 x 10 3
3.5 x 10 pCi/a1 i
a 14 failed pins Answer i
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i pCi/al (X)(Y) = % failed fuel
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Part 2.
18 C 1
2 3.9 : 10 pCi/al (.713)(1.67) =.026% failed fuel Answer 1.8 pCi/al 7
1 The above numbers are acceptable for a normally operating plant.
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Page 7 of 8 O
ENCLOSURE 10.3 EXAMPLES i
Problem 4 The unit has been at 97% power for a month when a'depressurization of the a.
RC system occurs.
b.
The reactor trips.
c.
Heavy vibration is observed in the RC pumps.
d.
Thermocouple temperatures over 1000*F are indicated in the core.
e.
RIA-36 has alarmed.
4 f.
High Pressure Injection was delayed and it is suspected the core was un-covered between 30 and 60 minutes before sufficient reactor vessel water level was regained.
g.
The incore instrumentation system is still operable.
h.
The RC sample indicates an I-131 concentration of 3800 pCi/ml.
i.
A Chemistry sample is taken inunediately (within the hour) after the trip.
Part 1.
Determine the maximum expected number of failed pins.
Part 2.
Determine the maximum expected % of failed fuel.
solution This is Case III, Section 5.0 Use equation 5.2.1.1 for Part 1 Use equation 5.2.1.4 for Part 2 Determine X: Enclosure 10.1 RC Temp. T at 0% power is 557*F.
AssumesamhShtemperatureof90F Therefore, X E.730 Determine Y: 0.2 l
Y = 100 = 1.03 9
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ENCLOSURE.10.3 EXAMPLES I
l 3800 pCi/mi Part 1.
(.730)(1.03) = 1.90.5 2.4 pC1/al E 1191 number failed pins, max. expected Answer i
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i 3800 pCi/e1 (.730)(1.03) = 2.28% failed fuel, max. expected Answer Part 2.
1255 pCi/ml I
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ENCLOSURE 10.4 t
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i FAILED FUEL CALCULATIONS
[
I CASE I l
UNIT DATE/ TIME BY X=
Y=
I-131 pCi/ml i
I Maximus Number of Failed Fuel Pins (Best Estimate):
I
)
(
)*
3.5 E-3
.[
~
Minimus Number of Failed Fuel Pins:
(
)
(
)
4.9 E-3 t
f Maximum % Failed Fuel (Best Estimate):
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(
)
(
) _
1.8 y
Minimum % Failed Fuel:
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(
)
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2.5 COMMENTS:
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ENCLOSURE 10.5 FAILED FUEL CALCULATIONS CASE II
[
. UNIT DATE/ TIME BY X=
Y=
I-131 J Ci/ml
(
r Maximum Number of Failed Fuel Pins:
(
)
( )
j 5.5 E-2 j
i i
l Best Estimate of Failed Fuel Pins.
('
)
(
)
f 1.65 E-1 Minimum Number of Failed Fuel Pins:
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(
)
(
)
I 2.74 E-1 i
Maximum % Failed Fuel:
.(
4 I
)
(
)
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27.9 i
i Best Estimate Failed Fuel:
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(
}
(
)
83.7 i
i Minimum % Failed Fuel:
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)
(
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I 139.5
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COMM'.NTS:
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Paga 1 of 1 l
9 ENCLOSURE 10.6 l
(
FAILED FUEL CALCULATIONS I
CASE III UNIT DATE/ TIME BY 1
i X=
Y=
I-131 pC1/mi i
Maximum Number of Failed Fuel Pins:
i
(
)
(
)
2.4 Best Estimate of Failed Fuel Pins:
(
)
(
)
2.9 I
?
Minimus Number of Failed Fuel Pins:
I
)
(
)
3.2 4
f Maximum % Failed Fuel:
(
)
(
1255 i
i i
Best' Estimate Failed Fuel:
(
)
(
)
=
f 1535 l
).
l Minimum % Failed Fuel:
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(
)
(
1675 l
COMMENTS:
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i ENCLOSURE 10.7 FAILED FUEL CALCULATIONS i
CASE IV i
UNIT DATE/ TIME BY X=
Y=
I-131 pCi/al f
i Best Estimate of Failed Fuel Pins:
(
)
(
)
=
5.5 t
i Best Estimate of % Failed Fuel:
2790
- (
)
I
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COMMENTS:
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yr-et-e,- eamt 1BIOR W 0 1.03.Y Fort: SPD-1002-1 b&
DUKE POWER COMPANY (1)
ID No: CP/0/8/4003/02 PROCEDURE PREPARATION Change (s) n/a to l
PROCESS RECORD Incorporated l
i (2) STATION:
Oconee
]
(3) PROCEDURE TITLE:
The Determination of Plume Difection and Sector (s) to be
[
lionitored Following a large Unolanned Release of Gaseous Radioactivity (4) PREPARED BY:
h[*7/r DATE: C 4 - 2 9 - f3'2.
(5) REVIEWED 3 me f/ d DATE:
87 Cross-Discip inary eview By:
N/R:
r (6) TEMPORARY APPROVAL (IF NECESSARY):
1
- By:
(SRO) Date:
By:
Date:
(7) APPROVED 3Y: l N _ 1,
Ild w Date: '
5 3D
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(8) MISCELLANEOUS:
s Reviewed / Approved By:
Date:
Reviewed / Approved By:
Date:
t REVIEWED TO ASSURE ADEQUACY
[
s BY ^ *4 DATE 5 " 3 - ** -.
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This werking copy has been ec= pared wit'.1 the control copy and is appropriate by P11' k Este 8 -8s -62 s
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Page'1'of.5L DUKE POWER COMPANY.
OCONEE NUCLEAR STATION THE DETERMINATION OF PLUME DIRECTION AND SECTOR (S)
.TO BE MONITORED-FOLLOWING'A LARGE UNPLANNED RELEASE OF GASEOUS RADIOACTIVITY 1.0 ' Discussion i
4 1.1 -Scope - This procedure covers the methodologies and techniques used-
~
in determining the direction of a plume and the sector (s) to be moni-tored by the Field Monitoring Teams in the event of an' accidental ~re-leas ~e of radioactive gases from ONS.
1.2 Principle - The determination of plume direction and,.therefore, the sector (s) to be monitored whall be based on site specific meteorolo-i stical-conditions. The Unit 1 Control Room operator (s)- shall provide meteorlogical data (wind speed and direction, temperatures and vertical.
temperature gradient obtained from the primary meteorological tower (46 m) and wind direction'from the river tower located near the S.C. Highway 183 bridge). Plume evaluation nomographs have been pre-l pqred using the various combinations:in which'these-meteorological-i variables might occur. The applicable nomograph (s) shall be selecte'd and placed on the 10 mile radius map. The area bounded by the overlay then becomes the sector (s) to be monitored in accordance with Procedure No. CP/0/B/4003/01.
I 1.3 Limits and Precautions 1.3.1.
The Control Room shall provide meteorological condition up-4 dates every,15 minutes once the Technical Support Center has been activated.
1s i.
1.3.2 In the event site meteorr;1ogical_ data is not available, the following meteorological data shall be obtained from the National Weather Service at the Greenville-Spartanburg Air-j port:
i 1.3.2.1-Wind' speed.in mph (mph = knots x 1.15) 1.3.2.2-Direction from which wind is blowing in degrees.
1.3.3 The plume evaluation nomographs (overlays) shall be kept in
~
-the Field Monitoring Coordinators emergency ~ kit situated in the Environmental Lab, Administration Building Annex.
'2.0 ~ Procedure y
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- 2.1; 0btain -'and' record on Enclosure 4.1 the-following meteorological; dat$ -
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.from.the Unit 1' Control Room.(vertical: board pane 1 displaying' weather
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':information; located at the northeast corner of the Control Room):
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-CP/0/D/4003/02 Page 2 of 5
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2.1.1 At in F (differenc'e in temperature between the top of the
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tower and the bottom).
NOTE:
The at can be positive or negative.
2'.1.2 Wind speed in sph (Primary Tower) t 4
~
Dirgetion from which the wind is blowing in degrees, C to-
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2.1.3 360 (Primary Tower) l t
1 2.1.4 Dirgetion from which the wind is blowing in degrees, O to f
360 (River Toweg) i i
2.2 Select the correct plume evaluation nomograph using the above meteor-
~f ological data and the following guidelines:
[
2.2.1 If the time of day is between 1600 and 1000 and the primary-tower wind speed is less than 15 mph and the primary tower At is positive, select pomograph "A".
-l 2.2.2 For all other meteorological conditions select' one of five other nomographs using the following combinations of para-
[
meters:
[
i For a At Of And Wind Speed Of Select Nomograph
{
-25.0 to -1.3 F 0 to 50 mph "B"
-1.2 to -1.0 F 0 to 50 mph "C"
i
-0.9 to -0.4 F 0 to 50 mph "D"
h
-0.3* to +10.0 F 0 to 6 mph "E"
[
-0.3 to +10.0 F 7 to 50 mph "F"
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2.2.3 If National Weather Service meteorological data is-used select one of three nomographs based on the following:-
For Time of Day And Wiild Speed of Select Nomograph 1000 to 1600 0 to 50 mph "D"
[
1600 to 1000
> 15 mph "F"
1600 to 1000
< 15 mph "A"
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'2.2.4 Record the nomograph selected on Enclosure 4.1.
2.3 Determine the direction of the plume in the' following manner:
I i
2.3. I '-
If plume evaluation nomograph "B",
"C", "D", "E" o~r "F".was
{
' selected in Section 2.2, place the nomograph on the 10 mile
- radius map with the end of the arrow on the station (center of l
map) and the top pointing in the opposite direction from which.
}
E the primary tower wind is blowing.
}
6 2.3.2
.If plume evaluation nomograph "A" was selected in Section'2.2, l
(
the "A" nomograph should be placed on the.10 mile radius map -
i as.follows:
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CP/d/B/4003/02 Page 3 of 5 dU)'
NOTE:
If National Weather Service meteorological data is used and nomograph "A" was selected, use the same assumption as in Step 2.3.2.3.
2.3.2.1 If the river wind direction from Step 2.1.4 is be-i 4
tween 100 and 190" and the river wind direction differs from the primary tower wind direction by more than 45, place nomograph "A" on the map with the arrow pointing in the direction of 350, t
and then place a second nomograph "A" on the map with the arrow pointing opposite the primary tower wind direction.
t i
2.3.2.2 If the river wind direction from Step 2.1.4 is between 100 and 190 and the primary tower wind direction.is not-different from the river wind.
direction by more than 45, place one nomograph "A" on the map with the arrow pointing in the direction of 180" and then place a second nomograph "A" on the map with the arrow pointing opposite the primary tower wind direction.
2.3.2.3 If the river wind direction is not between 100 and 190" but the primary tower wind direction differs i
from the river wind _ direction by more than 45, the O
plume direction can not be determined and all dir-
\\
ections are considered to be affected. Place tne "A" ngmograph on the map with the arrow pointing in j
the O direction but assume that all directions are i
affected and dispatch Field Monitoring Teams to monitor in all directions.
2.3.2.4 If the river wind direction is not between 100 and 190 and the primary tower wind direction does not I
differ from the river wind direction by more than 45", place nomograph "A" on the map with the arrow pointing opposite the primary tower wind direction.
2.4 Determine the sector (s) and predesignated sampling locations to be moni-tored.
l 2.4.1 Once the appropriate nomograph has been placed over the 10 mile radius map, dispatch Field Monitoring Teams to locate and moni-j tor the plume within the bounds of the nomograph and in accord-i ance with Procedure No. CP/0/B/4003/01.
i 2.4.2 The dashed lines on the plume evaluation nomographs show the i
appropriate plume width. The solid lines encompass the area i
likely to bracket the plume centerline. The areas possibly affected by the plume include the area inside the solid lines r
t 1/2'of the plume width (as indicated by the dashed lines).
A
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NOTE:
If nomograph "A" is selected, assume the affected
+
t area or the area to be monitored is ! 90 from the nomograph centerline or t _4 sectors.
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I CP/0/E/4003/02'
'f Page 4 of 5
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- 2.5 Reassess nomograph selection ~ every hour and/or whenever there is a.2.5 shift in wind direction.
t 4
. 3.0 References l :.
3.1 Procedure for Environmental Sutveillance Following a Large Unplanned i
Release of Gaseous Radioactivity (CP/0/B/4003/01) i
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4.0 Enclosures
-4.1 Meteorological Data i
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CP/0/B/4003/02 Page 5'of 5
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r E.NCLOSURE 4.1 t
e METEOROLOGICAL DATA t
3' Primary Tower (46m)
River Tower National Weathee Service
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.' 1.. Time of Day 1.
Time of Day 1.
Time of Day
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2.
At
- F (temp.
2.
Direction From Which' 2.
Direction From Which gradient between Wind is Blowing Wind is Blowing e
top of tower and Degrees Degrees bottom) 1 i
3.
Tower Wind Speed j
f mph i
i 4.
Direction From Which Wind is Blowing 4
Degrees l,
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CONTROL COPY i
I LL Form 34731 (10-81) yg (Formerly SPD-10021) i i
DURE POWER COMPANY (t)
ID No: HP/0/0/10_09/12 PROCEDURE PREPARATION Clianr.e (8). 2 _t o PROCESS RECORD N/A _Ineorpora t cd (2) STATION:
Oconee i
(3) PROCEDURE TITLE: - D I s t r I bu t I on__o f,.,Po.t a.s.s I urn i ed I de Tqb I e t s I q _t he _Eyen.L___
of a Radiofodine Release (4) PREPARED BY: [
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DATE:J/// /f2_
(5) REVIDED BY:
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DATE:
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Cross-Disciplinary Revie By:
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4 (6) TDIPORARY APPROVAL (IF NECESSARY):
Bv:
(SRO)
Date:
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By-Date:
W Date: YD L
(7) APPROVED BY:
l (8) MISCELLANEOUS:
Reviewed / Approved By:
Date:
Reviewed / Approved By:
Date:
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IIP /0/11/100'I/12 x.
DUKE P0k'ER COMPAIIY OCONEE NUCI. EAR STATION DISTRIBUTION OF POTASSillM IODIDE TABLETS IN THE EVENT OF A RAD 1010 DINE RELEASE l.0 Purpose This procedure provides information necessary to distribute Active Potassium Iodide (KI) tablets to inplant personnel in the event of a release of radiciodine. Also, it outlines storage and supply information to assure sufficient quality and quantity of thyroid blocking material.
2.0 References 2.1 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases of Radioiodine 1977 2.2 NCRP Report No. 65; Management of_ Persons Accidentally
}
Contaminated with Radiciodine 1980 f
p
~ 2.3 Body Burden Analysis procedure 2.4 System Health Physics Manual
'2.5 NUREG 0654 t-3.0 Limits and Preesutions i
3.1 Persons who are allergic to KI must not receive these tablets.
3.2 Nursing mothers who receive RI tablets must be advised to use nutrient substitutes (ex: milk or a formula) for children for the duration of the ten-day tablet use period.
3.3 Personnel must be advised not to deviate from prescribed dosages and dosage rates.
3.4 Best results will be achieved when'KI tablets are administcreil
-immediately (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) af ter an exposure, although ailminis-tration as late as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an emergency will be of (limited) value.
l, Do not distribute discolored, disfigured tablets, or tablets that L
3.5 have reached their expiration date. Such tablets shall be iliscarded.
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.0) 3.6 Hands of g ersonnel must be ince f rom contamination prior to taking
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<KI tablets.
4.0 Procedure 4.1 Responsibilities for Distribution 4.1.1 Persons suspected of having been in the af fected arca prior to detection and during the release, persons pre.sent in the affected area, and persons who will enter the.irca while a signific.uit.imount of radiciodine is present will be instructed by the Station Health Physicist to immediately register in the KI dist ribution center (for example, the Technical Support Center (TSC) for each unit).
NOTE:
A significant amount of radioiodine in this case is that amount taken into the body that would-result in a quarterly permissible occupational dose or more. For example, exposure to 4.6 x g mci /ml airborne iodine for one hone would y
10 result in such an exposure. This corresponds to 520 !!PC-bra which is the quarterly limit.
4.2 Registration of persons exposed to a significant amount of radioiodine
["%
4.2.1 When persons notified by Hcalth Physics arrive at the
(
)
distribution area, record appropriate data per Enclosure 5.1.
4.2.2 The Station Health Physicist or his designee should give one (1) tablet to cach af fected person and inst ructions con-cerning the use of the tablet. Then issue to cach affected person one bottle containing nine (9) KI tablets, and the package insert for the use of the tablets (refer to Enclo-sure 5.2 for an example of the package insert).
4.2.2.1 Tablets are to be taken only as directed. One (1) tablet per day for ten (10) days is the recommended dosage.
4.2.2.2 After the' initial dose of K1, subsequent doses will be taken on a daily basis. Tablets should be taken as near a 24-hour schedule as possible.
NOTE:
For best results, emphasis must be placed upon the proper use of these tablets.
4.2.3 Tablets removed from tull bottles of KI should be stored in 10 ml plastic vials. The expiration date on the bottle l
from which the tablets were taken or from the expiration l
date extension letter and the name of the Health Physics A
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representative must be recorded on the 10 mi vials.
T.shlets stored in.10 ml plastic vials should then be used f
for the single tablet initial issuance of KI to af fected I
persons.
i.'
Thyroid Burden Analysis Following Radioiodine Expcsnre t
5 4.3
[
All personnel receiving KI tablets should receive a
[
4.3.1 If the number of people render this step l
thyroid scan.
impractical, the Count Room Supervisor should draw a l
i representative sample of persons listed on Enclosure 5.1 l
who received K1 tablets.
4 Subsequent action involving thyroid burden NOTE:
analysis should follow guidelines established in the System ficalth Physics Manual.
r
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l Records of thyroid scan should be mair+.ained per procedure.
t 4.3.2 f
j Thyroid scans immediately after an accident could lengthen KI distribution time and cause l
NOTE:
confusion among personnel. Distribute KI before analyzing thyroid concentration.
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4.4 Storage Requirements
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There are three major storage requirements to be observed:
4.4.1 i
Store lii a temperature range of 59 to 86 degrees l
4.4.1.1 f
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-Store in a low humidity area (avoid direct l
a 4.4.1.2 exposure to liquids).
i Store in an area' protected from exposure to l
4.4.1.3 light.
Supplies of KI tablets are maintained
(
}
NOTE:
in the TSC emergency cabinet and the emergency kits'for field monitoring teams.
The supplies are inventoried as per i-PT/0/B/2000/04 and CP/0/B/4003/06..
f Upon receiving a shipment of.KI, boxes should be. opened 4'.4.2 as soon as possible and bottles examined to ensure that Bottles must bc in airtight seal has been maintained.:
rsturned to boxes, and boxes must be sealed shut,
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so as L
to avoid exposure to light.
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To ensure a sufficient supply of tablets, a minimum of
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50 bottles with 14 tablets per bottle. should be maintained l
4.4.3 on-site.
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4.5 Shelf Life and Changcout of K! Tablets 4.5.1 Theyo Block " tablet bottles are labelled with an expiration date from the factory.
As' tablets reach the expiration dates, the tablets must be discarded.
NOTE:
The expiration date listed on the bottle may
[
J have been extended. Documentation of an extension should be placed with the supply of KI tablets.
4.5.2 Order replacement tablets at least three (3) months prior r
to the date of expiration listed on the bottles of KI.
v 4.5.3 Upon receiving a shipment of KI tablets, supplies should be shifted so as to use older tablets before new tablets.
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4.5.4 After the radioiodine emergency, tablets in the 10 ml plastic vials mus.t be discarded.
l 5.0 Inclosures 5.1 Potassium Iodide Tablet Distribution Data Sheet 5.2 Package Insert for Thyro-Block Tableir and Solution f
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);4 ENCLOSURE 5.I
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POTASSIUM IODIDE TABLET DISTRIBUTION DATA SHEET HP BADGE DATE & TIME OF DATE & TIME OF NUMBER NAME DEPARTMENT SUSPECTED EXPOSURE INITIAL ISSUANCE-f i
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Enclo.ure 5.2 Pags I of 2 s.
Package Insert for Thyro-Block Tablets and Solution
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THYRO 8 LOCK" (rQTASSIUM 600:04 (pronounced poe TASS **m EYEerHtyed sacere..i.s no j
TAeLETS ano sowrics u1P.
i IF YOU ARE TOLD TO TAKE THIS MEDICINE.TAKE IT
[
ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. MORE WILL NOT HELP YOU AND MAY IN.
1 CREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUO IF YOU KNOW YOU ARE Afil'ROIC TD IODIDE. (SEK SIDE EFFECTS BELOW.)
INDICATIONS THYROID BLOCKING IN A RADIATION EMERGENCY ONLY.
l DIRECTIONS FOR USE i
Use only se directed by State or local pubhc health authorsties in r
the e mit of a radiation emergency.
DOSE Tablete:
ADUL13 AND CHILDREN 1 YEAR OF AGE OR OLDER: One 11) tablet once a day. Crush for smau chddren.
BABIES UNDER 1 YEAR OF AGE:
One. ball (1cl tablet oece a day. Crush i
first.
t Solution:
ADULTS AND CHILDREN 1 YEAR OF AGE OR OLDER: Add 6 drope to one.
half glass of Equid and drmk each day.
(
BABIES tJNDER 1 YEAR OF AGE:
Add 3 dropie to a emeR amount of liquid
(
oncea day.
For e# desage forme Take for 10 days unlese.daracted otherwise by State or local public health authorities.
Store at contround room temperssure between 15' and 33*C (59' to 86*Fl. Keep container tightly closed and protect fazem Eght.
Do not use the solution ifit appears browmeh sa the nosale of the bottle.
WARNING Poenesium iodide shouM not be used by people ouergse so iodade.
i Keep out of the ranch of chddren. In case of overdoes or muergic reaction, contact a physicana or the public beelsh authority.
{
DESCRIPTION Each THYRO.BLOCKm TABLET containe 130 mg of N
potaassom iodade.
Each drop of THYRO.BLOCKMSOLUTION contame 21 mg of potaasium iodide.
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HOW POTASSIUM IODIDE WORKS Certaan forms of iodine help your thyroid gland work right. Most people get the iodine they need from foods, like iodized salt or fish. The thyroid ras " store" or hold only a certain amount of sodana.
In a radiation emergency, radio.ctive iodine may be released la the air. Th!,e matenal may be beeathed or swallowed. It may entar the thyroid gland and damage it. The damage would pro-bably not show itself for years. Chudren are most likely to have thyroid damage.
If you take potassium iodide. It will fi!!.up your thyroid gland.
This reduces the chance that harmful radioactive lodine wG enter the thyroiu gland.
WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should not take potassium iodide are people who know they are allergic to todade. You may take potassium iodide even if you are taking medicmes for a thyroid problem (for esaaspie, a thyroid hormone or antithyroid drugt. Pregnant and nursing women and babies and children may also take this drug.
HOW AND WHEN TO TAKE POTASSIUM IODIDE Potasenum lodi.se should be taken as seen se possible a(tar public health officials tall you. You should take one dow evwy 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. More will not help you because the thyroid can " hold" on-ly limited amounts of iodane. Larger doses wdl increase the risk of side effects. You will probably be told not to take the drug for more than 10 days.
SIDE EFFECTS Usually, side effects of potassium iodide happen when people take higher doses for a long time. You sho ald be careful not to take more than the recommended does or take it for longer than you are told. Side offacts are salikely because of the low does and the short time you wG be taking the drug.
Possible side effects include skin rashes, seeihng of the salivaty giaads and "iodiam" testalbc tasta, burnag mouth and throat, sors teeth and guma. symptome of a head cold, and sometamos stomach upset and diarrhees.
A few people have an allergic reaction with more sonous symp-toma. These could be fever at d joint peias, or swelling of parts of i
the face and body and at tune.' severe shortness of breath requir-ing imanodante medscal attention.
Taking iodide may rarely cause overactivity of the thyroid gland. underectavity of the thyroid gland, or enlargement of the thyrned gland (guters.
WHAT TO 00 IF SiOE EFFECTS OCCUR --
If the side effects are severe or if you have an allergic reaction, stop taking potasema iodade. Thee, if pa==Ma call a doctor or public health authority for instructaons.
HOW SUPPLIED THYRO BLOCKN TABLETS IPotassium Iodide. U.S.PJ bot-ties of 14 tablets (NDC 0037 3472 20J Each whita. round, scored tablet containe 130 mg potassium iodade.
THYRO BLOCKW SOLLT.ON (Potaseman todide Solution.
U.S.PJ 30 ml11 fL osJ lisht reenetaat. --- _- A,,, dispensing units INDC 0037-4287 251. Each drop containe 21 mg potassium nodido.
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ID No: IP/0/3/1601/3
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PROCEDURE PREPARATION Change (s)
'3 to PROCESS RECORD 3
Incorporated t
(2) STATION:
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(3) PROCEDURE TITLE:
Environmental Equipment Checks l
l (4) PREPARED BY:
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(5) REVIEWED BY:
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DATE:
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Cross-Disciplinary Review"By:
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(6) TEMPORARY APPROVAL (IF NECESSARY)-
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By:
(SRO) Date:
i By:
Date:
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IP/0/B/1601/03 DUKE P0bER COMPANY I
' OCONEE NUCLEAR STATION I
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ENVIRONMENTAL F(UIPMENT CHECKS
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i
' 1.0 Purpose.
=
r 1.1 To. furnish.a procedure for documentation 'of weekly data. collection and equipment functional checks.
2.0 References
}
2.l~
Duke Dug. 0-714-D, 0-829, 0-829-A a
I 30 Test Equipment Required 3.1 Portable psychrometer 4.0 Prerequisites (Sign-offs on Enclosure 11.1) f 4.1 This procedure should not be performed during a gaseous waste
{
1; release period.
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4.2 Supervisor has reviewed and initialed all portions of this' pro-i cedure which are not applicable to the activity being performed.
. i e
i The Supervisor's review is not required if the procedure specifies f
sections to be omitted.
i l
4.3 Verify that all changes.in the Control Copy are incorporated in
}
the k'orking - Copy.
j 5
4.4 This procedure must be retyped within 30 days of any approved change.
f r,
2 4.5 A copy of the control copy must be sent-to emergency preparedness-
' [
coordinator any time a change is made.
1
- 5.0 Limits and Precautions' 1..
. 5.1 Use proper precautions-while working with-. components-that have high voltage or high pressure'present.
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I 6'0 Unit Status I
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'I 7.0 General Description Q-The environmental equipment monitors the following parameters and records the information on individual chart recorders; wind speed, wind direction, air tempereture, humidity, and amount of rainfall.
There are two meteorological monitoring stations for the wind speed and direction. Site #1 is located at the micro-wave tower and Site #2 is located adjaunt to the river below Keowee discharge.
i 8.0 Major Components Description Man. Ref.
8.1 Four Esterline Angus Series "A" Analog Recorders 8.2 One Leeds and Northrup Speedomax OM-267-514
'H&W Multipoint Recorder 8.3 Two Teledyne Geotech' Series 40 OM-333-274 Wind Speed Modules 8.4 Two Teledyne Geotech Series 40 OM-333-275 Wind Direction Modules i
8.5 Two Teledyne Geotech Series 40 OM-?';3-276 V
AC Power Supplies I
8.6 One Leeds and Northrup 3-Lead Resistance Temperature Detector (RTD)
Air Tentperature Sy,atem 8.7 One Belfort Instrument Company Hygro-s thermograph Recorder 8.8 One Belfort Instrument Company weighing Rain Gauga Recorder 9.0 Equipment Specifications
.l Wind Speed 0-30 mph (60 and 90 mph selectable 7.
ranges)
Wind'Oirection 0-540 degrees.
. Ambient Air Temperature
-15 to 105'F Temperature Differential
-30 to 30*F Rainfall Gauge 0-12'in.
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10.6 Procedure Instructions (Sign-offs on Enclosure 11.1)
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NOTE:
sUse Control Room computer clock for all time recordings.
Mark on charts all as found calibration points '(R,de.
- Found, T Found and F.S. Found) before adjustments are ma If adjustments are made, mark all as'lef t calibration points (R Left, T Left and F.S. Left) on charts.
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Perform as found string checks using the following procedure and complete Enclosure 11.3.a and b.
-10.1 ONS *ite 1 1.
Check recorder zero on wind speed and direction recorders-by turning translator power off. Rotate charts slowly and individually for good trace. Verity positions on recorders and note time and date. Mark "R Found" on each chart beside z
the trace.
2.
Return power on translator and check wind speed and direction
- Lo Cal. by placing modules in the Lo~ Cal. position. Rotate
' charts slowly and individually for good trace. Verify positions on recorders. Mark "T Found" on each chart beside the trace.
3.
Place the wind direction and wind speed module in the Hi Cal.
position. Rotate chart slowly and verify posit' ion on recorder.
D)
Mark "F.S. Found" en each chart beside the trace.
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4.
Place wind speed and direction modules in operate position.
Verify normal response on recorders.
Insure ink wells are full.
5.
Change the charts on recorders. Document start time and date on the charts.
10.2 ONS Site 2 1.
Place Control Room switch in the Lo position. Verify Lo Cal, positions on the wind speed and direction recorders. Rotate charts slowly and individually for good trace.
Label chart "T, Found".
2.
Place Control Room switch in the Hi position. Verify Hi Cal. positions on the wind speed and direction recorders.
Rotate charts slowly and individually'for good trace.
Label
'?F. S. Fo und".
3.
Check recorder zero cut wind speed and direction recorders by i
disconnecting field inputs in back of Jrecorders and installing
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a jumper wire across the-terminals.
Label chart "R Found".
l Document time and date on charts. Rotate charts individually and slowly for good trace.. Verify' position on recorders.
i 4.
Remove jumpers and reconnect field inputs to' recorders.
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5.
Place Control Room switch to the operate position. Verify
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normal response on recorders.
Insure ink wells are full'.
6.
Change charts on recorders. Document starting time and date on charts.
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If all' string checks are within tolerance, remove and staple together the front approval sheet, list,of enclos'ures, and sign off sheet.
Insure all equipment mentioned above is returned to-service and continue.
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If all string checks'are not within tolerance, continue with Section 10.6.
10.3 Air Temperature Recorder 1.
Turn off chart recorder. Document time and date on chart.
E 2.
Remove weeks run of chart paper.. Replace chart paper as nec-i essary.
3.
Restart chart and recorder. Verify proper response. Document time and date on chart.
NOTE:
If there are any problems or you think-there may b'e something wrong-with the air temperature system, please note this on the chart from Step 2.
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10.4 Hvgro-Thermograph Recorder s
1.
Check the temperature with a thermometer and humidity.with a portable psychrometer.
2.
Remove old chart from recorder noting time and date on chart.
3.
Change the chart on the hygro-thermograph recorder.. Document
' start time and date on chart.
j 4.
Prepare recorder for another week of. operation _ by rewinding clock mechanism, inking the_ pens, and aligning chart for i
correct time. Document the temperatuse and humidity readings from Step 1 on chart.
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If the temperature or humidity is found, upon comparison with a thermometer and psychrometer, to be incorrect proceed to Section 10.6 for adjustment procedures.
10.5 Rain Gauge Recorder
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Open the sliding door and lift the pen from the chart by pulling the pen arm shif ter away from the mechanism support column.
2.
Next remove the collector and' empty the bucket slowly from the
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{/1 platform so that the gauge mechanism will not be subject to any y
sudden shock as the pen returns to the zero reading.
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-Replace the collector.
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- 4.
. Lift the' chart cylinder and remove old chart noting time and date.
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on chart.
5.
Change the chart on the. rain guage recorder. Document, start time and date on chart.
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'6.
- Prepare recorder for another week of. operation by rewinding clock mechanism,-inking the pen, and aligning chart-for correct-time.
7.
Verify pen on.zero point.
If not, adjust the ze' o knob r
until zero is obtained.
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- 8.
Ink the pen, set the chart to correct time.. Press the pen l
arm shifter all the way in and verify pen is making contact
.j with chart.
9.
Close sliding door.
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10.6 Calibration Procedures
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Wind System h
1.
To. adjust recorder zero, ensure poser supply on.trans-j lator is off. The zero adjustment-arm is located on
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the inside bottom of recorder under the chart take-up-v reel. -Make adjustments until recorder reads zero. Mark i
"R Left" n chart beside the trace after the final
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z adjustment.
t 2.
To adjust the translator full scale, turn the power supply i
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on and the translator mode switch to the -Hi Cal position.
Adjust the Hi Cal adjusting screw on front of module to ~
achieve a full scale reading. Mark "F.S._Left" on chart beside the trace after the final adjustments.
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3.
To adjust the translator zero, turn the mode switch to the-Lo Cal position. On the wir.d direction module adjust the 11 Lo Cal adjusting screw on the front of the' module to.ob--
l tain a zero' reading.' Mark "T Left" on chart beside the j
t trace after the final adjustment.
NOTE:
The translator zero for the wind speed module should be performed. in a lab since the adjust-
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ments necessary must be made internal of the translator and requires a considerable amount l
of time and accuracy.
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If translator zero for-wind speed exceeds' 1
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tolerances contact the E.S.S. (Environmental' Services Section).
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Hygro-Thermograph Recorder
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1.
If the temperature indication is found to be incorrect an adjustment may be made by turning the thumb screw j
nearest the front of the case until the thermometer and instrument pen are in agreement.
2.
If the humidity is found to be' incorrect, wet the hairs by stroking them gently with a camel hair brush wetted
-with distilled water. Continue this wetting for several minutes until no further rise of the pen can be observed.
When a stable position is reached, set the humidity pen =
to read 92% by adjusting the thumbscrew in the base of the instrument located beside the temperature setting screw. Do not set the pen to read 100% humidity. No amount of artificial wetting seems to wet the hair to the same extent as actual exposure to saturated air.
If.
after several checks an error is found in humidity indi-cation, the rear adjustment thumbscrew can be used to correct error per psychrometer reading.
I 10.7 As Left String Checks (Enclosure 11.5a and b)
F Perform as left string checks as required due to maintenance action or calibration in Section 10.2 for.all strings affected following procedure steps in Section 10.1.
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11.0 Enclosures f
11.1. Sign-Off Sheet 11.2 Reference Data (None)
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r 11.3 As Found String Checks 11.3.a ONS Site 1 11.3.b ONS Site 2 11.4 Calibration Data Sheets-(None) l 11.5 As Lef t String Checks i
11.5.a ONS Site 1 i
11.5.b ONS Site 2
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IP/0/B/1601/03 Sign Off Sheet
- PREREQUISITES Date Begun 4.1 Date Completed 4
4.2-WR#
4.3 4.4 4.5 4
STRING CHECKS AND DATA SECTIONS 10.0 10.3 10.6 ll.4.a.
-ll.5.a.
10.1 10.4 10.7 ll.3.b.-
ll.5.b.
10.2 10.5 b
10.2.3 Wires removed and jumpers installed.
4 10.2.4 Jumpers removed and wires replaced.
Performed by i
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i Notified Instrument Supervisor that a tolerance of 2% was exceeded (Tech) on following compoents:
Init. and date i
An evaluation was made on the above problem (s) and the following Inst. Supvr.
corrective action taken:
Init. and Date i
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J Remarks:
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AS FOUND INTEGRATED STRING 3
- VERIFICATION DATA SHEET' j
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Item Wind, Speed & Direction Test Equipment Used~
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1Hfg Teledyne Geotech Item SN i
' Series-40'
-Type 1-l l, Calibration Tolerance! W/S 1 0.4 uph; W/D 5.0 i-6:.
' System Environmental l
Span W/S'0-30 mph; W/D 0-540 i
i Location: Upper Meteorlogical Site (ONS Site 1) 1 l
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-Input Required AS Required
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Reading Found Reading Found-l W/S W/S W/D~
W/D' mnh mnh Amo A..
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- Af IP/0/B/1601/03 AS FGl.'ND INTEGRATED STRING r
- I VERIFICATION DATA SHEET 1
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Item Wind, Speed & Direction Test Equipment Used e
i' Mfg Teledyne Geotech Item SN Type Series 40
- I Calibration Tolerance W/S 0.4 mph; W/D t 5.0:
l System Environmental I
Span W/S 0-30 mph: W/D 0-540 l
t Location Lower Meteorlogical Site (ONS Site 2)
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Input Required AS Required AS f
Reading Found Reading Found i
W/S W/S W/D W/D mph mnh dec den j
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l' Location-- Upper Meteorlogical Site (ONS Site.1)-
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Item Wind, Speed & Direction Test Equipment Used Mfg Teledyne Geotech Item SN t
Type Series 40 I
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Span W/S 0-30 mph; W/D 0-540 4
Location Lower Meteorlogical Site (ONS Site 2) t i
e Input Required AS Required AS O-Reading Found Reading Found W/S-W/S W/D W/D mnh mnh doo doe a
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Equipment Returned To Service
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