ML20053D692
| ML20053D692 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/07/1982 |
| From: | James Smith DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A362 | List: |
| References | |
| EPM001-A, EPM1-A, PROC-820507-01, NUDOCS 8206070214 | |
| Download: ML20053D692 (100) | |
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[ TABLE OF' CONTENTS m,
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,.Emergeitcy Telephone Numbers - (03/01/82, Rev. 6)
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- AP/0/A/1'00h/03. ~ #
Event lodek . (03/09/82) ).- e r 'e '
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1 A1/0/A/2000/02 f-. Unusual tvent - (03/09/82) r ,
AP/0/A/1000/03 * '
'9 Alert e (03/09/82) 1 Site' Area Eoergency
~
'~ AP/0/A/1000/04 ... ' / ' .
.(03/09/82)
AP/0/A/1000/05 / ,,
General Emergency - (03/09/82)
., , , f
', AP/0/A/1000/$6
. Procedure f$r Initiating Protective Action
, $. ' /' Guides for the General Public in the Emer-
, ./ / / gency Planning Zone - (03/09/82) e , /
AP/0/A/1000/07 , ProcedureYdr~0ffsiteDoseCalculations
'~
/ by Control Room Personnel or Emergency 6 '- Coordinatot d6rtng a Loss of Coolant
'7
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c , Accident
- (02(26/22) e
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./'>, ~' AP/0/A/1000/0t,.g* * *
'Pracedure f6r Response Actions for Accidents /
Esergencids - (10/15/81)
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] r e AP/0/A/1000/10' ',
, 'Proceditre for Euergency Evacuation of Station s, -
Person'uel - (02/02/82)
Station Direct!ive 2.9.1 Stati6n AssemSly and Evacuation Procedure - '
,(04/14/62) e, , ,.
7 ,, - ,
Station Directiv'e 2.9.2 <Emerg' enc 3' Response Organization and Training -
F
-y (08/20/81, Original Issue)
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Station Direc'tiv'e.,5.1.3' Personal Injury Procedure - (10/19/81)
PT/0/B/2000/04 })-' ,f , Procedure for Este.blishment and Inspection j~ '
iof the Technical Support Center - (04/25/82)
. CP/1/A/2002/04A; '
. Post Accident Liqu'id Sampling of the Reactor
- Coolant System (12/01/81)
CP/2/A/2002/04A ' '
Post Accident Liquid Sampling of the Reactor Coolant System (13/01/81)
. i ,
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)
Revision, May 7, 1982 EPM 001/A ,
8206070214 820527 PDR ADOCK 05000269 y L_ F___ PDR , _
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Page 2 . % ,
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i Table of Conterts (Implementing Procedures - Continued)'
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 y Pressure Injection System (12/01/81)
CP/0/A/2004/1C Post. Accident Determination of Chioride by Specific Ion Electrode Using Beckman 4500 Meter (04/26/82, Original Issue) ,
p CP/0/A/2004/2E Post Accident Determination of Boron CJncentration Using Carminic Acid (04/26/82, Original Idsue) '
t]5 CP/0/A/2005/2D Post Accident Determination of Gamma Igc$c ic ~ , a .
Activity (04-26-82,,0riginal Issue)
'/
CP/0/B/4003/01 Procedure for Environmental Surveillance ,.'
Following a Large Unplanned Release of ,
Gaseous Radioactivity - (01/13/82)
- c -
CP/0/B/4003/02 The Determination of Plume Direction and Sector (v) -
to be Monitored Foll'owing a Larg6 Unplanned !A Release of Gaseous Activity '- (08/20/81) g HP/0/B/1009/09 Procedure for Detemining the Inplant hDt orne ..
Radioiodine Concentration During Accident Conditions - (07/09/S1)
,g v e. ,
HP/0/B/1009/10 Procedure for Quantifying Gaseous Relea' sed 4,g Ee Through Steam Relief Valves Under Post- ' ** "'j % 3 Accident Conditions " (07/0'J/81)*
- g.
. s l HP/0/B/1009/11 Projection of Offsite Duse from the Uncon-trolled Release of Radioactive Materiala ^
Through a Unit Vent.- (07/08/81) f,. ;.
- Distribution of Potassium Iodide Tdlets i 'l HP/0/B/1009/12 .
the Event of a Radioiodine Release '- (03/02/82),
HP/0/B/1009/13 Procedure for In.plementation and Vekification for the Availability of a Back-Up Source of 1 Meteorological Data.- (04/23/82) ,
HP/0/B/1009/14 Project Offsite Dose from Releases other >
than Through a Vent - (01/29/82) % ) i\ c$ ,
HP/0/B/1009/15 Procedure for Sampling and Quantifying High ,
Level Gaseous Radioicdine and Particulate i Radioactivity - (04/29/82) #
.- 1 Q , ')
EPM 001/A Re, vision, May 7, 1982 N q. - l ,
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%,, Table of Contents (Implementing Procedures - Continued)
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-- HP/0/B/1009/16'.. Procedure for Emergency Decontamination of
.z Personnel and Vehicles en-site and from Off-site Remote Assembly Area - (03/02/82)
IP/0/B/1601/03 Environmental Equipment Checks ,(04/08/82)
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CTIVE d 2.9) f j APPROVAL ,
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, DATE 8/20 1 ,
REVISED DATE I /"
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i DUKE POWER COMPANY j OCONEE NUCLEAR STATION 4 STATION ASSEMBLY AND EVACUATION PROCEDURE
^
Pagei j
I. PURPOSE . . . . . . . . .. . .. . . . . ... . . . . . . . .. 2 II. REFERENCES . . . . . . . . . . . . . . . . .. . . . . . . . .. 2 III. DESCRIPTION . . . . . . . . . .. . . . . . .. . . . . . . . .. 2
) I
V. PROCEDURE
S . . . . . . .. . .. . . . . . . .. . . . . . . .. 2 i
! A. Procedure for Station Assembly . . . . . . . . . . . . . .. 2 B. Procedure for Station Evacuation . . . . .. . . . . . . .. o V. ENCLOSURES . . . . . . . . . . . . . . . . .. . . . . . ....
A-1 Site Assembly Locations . . . . . . . . . .. . . . .... 8 A-2 Station Personnel Accountability . . .. . . . . . . . . .. 9 B-1 Emergency Evacuation Route . . . . . .. . . . . . . . . . 10 l .
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,- .. 2-I. PURPOSE
[']
x- This directive provides procedures to be used when responding to station assembly and preparatory to evacuation from the station if a radiological emergency is declared.
II. REFERENCES A. Oconee Nuclear Station Emergency Plan B. NUREG-0654, FEMA. - Rep-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants C. Technical Specifications 6.4.2 III. DESCRIPTION It is the intent of this directive to identify preplanned responses necessary to quickly and professionally respond to a station assembly and for evacuation from the station if a radiological emergency is declared. By being prepared, the effects of an evacuation from the station can be minimized and can facilitate faster action by station management and personnel, s I
V. PROCEDURE
g_ ,, A. Procedure for Conducting a Station Assembly 1.1 A Station Assembly encompasses the assembly of all onsite personnel at designated assembly points for the purpose of accounting for personnel within station boundaries. Reasons for initiating a Station A:sembly would include:
A) A test of response time and procedures employed in completing an accounting of onsite personnel.
B) A station incident occurs and:
- 1) Portions of the Protected area may require evacuation or
- 2) A station evacuation may be required, or
- 3) Portions of the Emergency Planning Zone may require evacuation.
1.2 A station assembly is initiated by activating the Personnel Assembly Signal in the Units 1 & 2 Control Room. This signal is a warble signal which is heard over the Public Address (PA)
System. The Shift Supervisor is responsible for initiating a ,
f'~'
(
Station Assembly and will assure that the following announcement is made throughout the station twice each time it is made.
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This is a station assembly. This is a station assembly.
/ \ All visitors outside security are to report to the (j. Receptionist Lobby. All visitors inside security are te report to the Security Lobby. All other badged pe esonnel shall report to your supervisor in the area designated on the back of your security badge.
If any particular area of the plant is found to be radiologically unsafe during an emergency, and a site i- assembly is held, warnings should be sounded through the public address system the " safe" corridors to use.
The alarm and announcements shall be continued for a duration long enough to ensure all onsite personnel are aware of the Station Assembly and are responding.
1.3 Action Plan for onsite personnel in responding to a Station Assembly Alarm.
1.3.1 Each person (except those noted in 1.3.4 below) shall assemble with their supervisor. Assembly points for personnel onsite at Oconee Nuclear Station are ident-ified in Table A-1. Additionally, these locations are on the back of the security badge for those personnel inside security.
) 1.3.2 During normal working hours on Monday through Friday v (except holidays) each supervisor shall be responsible for accounting for all personnel reporting to him.
Station Superintendents and the Senior Supervisors of various organizations working at Oconee (e.g., SSD, QA) shall make an accountability report to the Station Manager for their areas of responsibility. Security will make an accountability report for in-plant visitors. When reports from all areas are received, the Station Manager will notify the Shift Supervisor that all persons have been accounted for.
Table A-2 is available to aid in accounting for onsite personnel. Each reporting supervisor is to report location, his name, telephone number, number of people assembled, and any missing persons.
1.3.3 During.the hours not covered by 1.3.2 above, an accountability report should be made by the desig-nated responsible person in each functional work group'present at the Station to the Shift Supervisor.
The Senior Guard Force representative will report visitors.
'%..)
.- . 1.3.4 Persons working in Radiation Control Areas in protec- '
('~'N s tive clothing should leave their work areas and go to the appropriate change room. In the change room, they should contact the appropriate persons as desig-nated by 1.3.2 or 1.3.3 above for personnel account-ability reporting. Judgment should be used concerning the advisability of changing clothes and reporting to normal assembly areas.
NOTE: In case of a Reactor Building evacuation alarm, the reporting requirements in-1.3.4 above apply.
1.4 Action plan for Station Security 1.4.1 When alerted of a Station Assembly requirement, the Security Shift Lieutenant will be responsible for initiating a patrol of the general station areas within station boundaries, both inside and outside of the restricted area, to assure that personnel in remote and noise restrictive areas are aware of the Station Assembly requirement.
1.4.2 Security will restrict traffic in and out of the station during Site Assembly. Should Site Assembly f-~s be initiated during high traffic ingress and egress,
( )
.v normal traffic flow will not be restricted.
1.5 Action plan for Shift Health Physics Representative 1.5.1 Account for Health Physics personnel as directed in 1.3 above.
1.5.2 Provide assistance to personnel exiting contaminated areas or the Protected Area, as necessary, with proper frisking and contamination control.
1.5.3 If Health Physics supervisory personnel are not onsite, direct available Health Physics personnel in controlling or monitoring the radiological situation as required.
1.6 Action Plan for Shif t Supervisor / Station Manager (Emergency Coordinator) 1.6.1 Receive Accountability reports from onsite supervisors using Table A-2 es an aid.
1.6.2 Direct necessary actions to account for any missing personnel. Emergency Coordinator will dispatch l -~s -
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- - - - - . . .- , s
, ,. y 3 Search and Rescue Team (s) that may be composed of personnel from Security, Safety and/or Operations,
(\dj and Health Physics.
1.6.2.1 Health Physics will be responsible for monitoring and will be in charge.
1.6.2.2 Security will provide radio support and
, will be in a position to open controlled access doors.
i 1.6.2.3 Safety and/or Operations will provide medical support.
, 1.7 When personnel accotatsbility has been completed following a Station Assembly, one of the following will occur.
1.7.1 If the requirement for an assembly no longer exists, permission to return to normal duties will be given by the Shift Supervisor / Station Manger or; 1.7.2 Plant conditions may require evacuation of the station and implementation of an emergency organization or; 1.7.3 Other instructions will be given by the Emergency Coordinator.
( _, / B. Procedure for Conducting a Station Evacuation 1.0 A station evacuation shall be conducted when any unplanned radiological condition may result in whole body doses or internal exposures in excess of 10CFR20 limitations for areas outside
'the Radiation Control Area. Unplanned radiological releases contained within various portions of the Radiation Control Area may require evacuation of local areas only.
1.1 Station Evacuation levels are as listed below.
A. All members of the general public, and other persons who are not subject to occupational radiation exposure i at Oconee Nuclear Station must be evacuated if they
- are likely to be exposed to doses in excess of
- 1) External Radiation Level > 2 mrems in any one hour
, 2) Airborne Radioactivity > 1 x mpe for an unrestricted area (10CFR20, Appendix B, Table II)
B. Personnel subject to occupational radiation exposure j at Oconee Nuclear Station must be evacuated if they l are likely to be exposed to unplanned doses in excess
( p., of:
\
]
- 1) External Radiation Level > 2.5 mrem /hr, 100 l .mrems/ week, or 1250 mrems in a quarter l
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. 6-j/g 2) Airborne Radioactivity > equivalent amount
- ('
) inhaled for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week for 13 weeks at 1 mpc (10CFR20 Section 20.103 and Appendix B, l Table 1) l 2.0 When it is determined that a station evacuation is necessary, the station evacuation alarm will be sounded. This alarm is a continuous, single-tone siren that can be heard throughout the station. Evacuation will be by designated preplanned routes which avoid contaminated locations or other locations that may ,
be affected by the emergency situation. Evacuation routes, assembly locations, and other pertinent information shall be passed over the FA system or by telephone.
- 3.0 When directed, evacuees will evacuate using personal cars to the greatest. extent possible. Remote assembly locations, and entrance / exit routes will be provided with evacuation instructions. (Enclosure B-1)
Should personal cars be unavailable due to contamination, bus transportation will be made available. The Shift Supervisor /
Station Manager (Emergency Coordinator) is responsible for arranging bus transportatica as required.
~
Health Physics will survey evacuees and vehicles for contami-nation at designated locations as directed by the Shift Super-
, visor or Technical Support Center. Decontaminants and extra (s,, / clothing will be provided for by Health Physics at designated survey locations. Fire hydrants may be used for decontamination of vehicles. leaving the site.
4.0 Station evacuations are activated only after station personnel have been assembled through a Station Assembly.
A. Various groups of pe'rsonnel at the station are considered nonessential to the safe operation of the station and would be evacuated when directed. -Groups of personnel in this category include:
4 3-Substation Maintenance Wometco l SMS Chem-Nuclear
'SSD Vendors (other than HP)
QA General Office personnel Visitors Duke personnel (other than B&W ONS)
Design Engineering All others (not listed in Keowee B&C below)
Visitors Center B. The following groups of personnel are considered essential '
to the safe operation of the station. When a requirement exists to evacuate the station, these essential personnel
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.. . will be provided instructions as to where to report to assist in the safe operation of the station. Groups of s personnel in this category include:
Operations Licensing and Projects Health Physics NRC Health Physics Vendors Southern Security Biologists Resident B&W Representative a
C. The following groups of personnel ma; selectively be identified as essential to the safe operation of the station. When a requires'nt exist to evacuate the station, station management will identify which of the following personnel will be required to aid in the operation of the station. The remaining personnel will be instructed to evacuate. Groups of personnel in this category include: ,
Administra tion Maintenance Chemistry Performance K-Mac 5.0 After the initial evacuation of the station has been completed, adjustments to station staffing requirements will be made as the situation warrants by the Station Manager or his designee.
Control of station activities will be through the Technical j Support Center.
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. Page 1 of 2 TABLE A-1 SITE ASSEMBLY LOCATIONS p):
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's_/ Section DUKE OCONEE NUCLEAR STATION PERSONNEL Assembly Point Station Manager / Superintendents: Respective Offices and Assigned Clerks Administrative Services:
Administrative Services Administration Clerical Office Training Training Office Safety Training Office Medical Training Office Contract Services Contract Service's Offices Maintenance:
'I&E Engineers I&E Engineers Offices I&E Supervisors & Technicians I&E Shops Mechanical Maintenance Engineers Mechanical Maintenance Engineers Office Mechanical Maintenance Supervisors
& Technicians Maintenance Shop Planners Planning Office Materials Materials Office Operations: All Control Rooms / Unit 1 & 2 Operating
(/~ ') Engineer Office
\_ /
Technical Services:
Licensing & Projects Licensing & Projects Office Performance (All) Performance Engineers Office Health Physics (All) Health Physicist Office Chemistry (All) Station Chemist Office Environmental Environmental Office Quality Assurance: All Quality Assurance Office 4
Training Services: All Personnel at Training Center Oconee Training Center DUKE NON-0CONEE NUCLEAR STATION PERSONNEL Administration Visitors: All Administration Clerical Office Operations Visitors: All Units 1 & 2 Operating Engineers Office SMS: Those Inside Security Sheet Metal Shop Those Outside Security SMS Office Station Support Division: SSD Office
-(
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\ Keowee: All Keowee Hydro Station Visitors' Center: All Visitors' Center Office b _
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- SITE ASSEMBLY LOCATIONS DUKE NON-0CONEE NUCLEAR STATION PERSONNEL (Continued)
A ) Section Assembly Point
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Substation Maintenance: Substation Maintenance Office ,
Quality Assurance: All QA Office f.hemistry: All Station Chemist Office Health Physics: All Health Physicist Office Design Engineering: All Projects Office Maintenance Visitors: Service Building Mezzanine (I&E, Mechanical Maintenance, or Planning Office)
NON-DUKE OCONEE NUCLEAR STATION PERSONNEL Southern Security: Main Guard House 1
4 K-Mac: Those Inside Security Canteen South End, Turbine Building Those Outside Security K-Mac Office i
' Chem-Nuclear: Statioa Chemist Office [
B&W Resident Engineer: Control Room
- \,_-)
, NRC: All Licensing & Projects Office i
.Wometco: All Administration Building Canteen NON-DUKE, NON-0CONEE NUCLEAR STATION PERSONhTL I Health Physics Vendors:
i ,
Rad-Services Health Physicist Office NUMANCO Health Physicist Office Babcock & Wilcox Personnel: B&W Offices, Trailer Visitors:
Inside Security with Permanent Badge Receptionist Lobby Inside Security with Escort Security Lobby, Administration Building Outside Security Receptionist Lobby
'OTHER PERSONNEL OUTSIDE PROTECTED AREA All personnel not identified above will report to the Receptionist Lobby between 0800 - 1630, Monday through Friday. On weekends, holidays, and after hours,
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[J report to Security Lobby, i
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\ \ / DATE ret'5RTING NE- '~' ~ ^
NAnE Noriera N .mi.e r *EP8'rTitic .
. CRolfP TEl.Erltot4E PEurl E NAffE istiMnFR grtittat a .
,_,m_ CROUP
- TER.ErnordE f fort.E Alasnistration Contract Services: Technical Services E -tta c ' "'"^"
Southern Scturity EnvironmentaI:
Trainina & Safety:
Licensing & Projects:
A tm a, n a, s t r a t s, ve Design Engineering Services: NI(C Weetco Ifralth Physics:
Visitors' Center:
Chemistry:
Keowce Ilydro: _
Others:
Station Visitors: _
Receptionist Lobby Security Lobby Tules TOTAL TECIINICAL SERVICES CROUP -
Others:
Quality Assurance 11tlE: TOTAL ADMINISTRATION CROUP '
8 e
9ferations S8 1 8 I
fg! ufPiri
,g Operators On-Shift:
ytnE, Station Support Division Total:
Engineers / Staff: s I
Others:
Training Center:
BW Personnel: - - - -
nebers..
F.fCINNING ENDINC Others Total:
T!HE: Tl?2: TOTAL MOPLE ON-mE:
TIMC: TOTAL. OPERAT10t:S CROUr Unaccounted Personnel Group Action Taken PersonRepgiling Tglepit j tiaintenance Planning & !!aterials: ._
IEE:
RFHAP.KS:
t!-thanical Maintenance:
System itaintenance Support:
Substation ilaintenance: .
Others:
TI!!E: TOTAL MAINTE!!AllCE CROUP MAJOR REVISION
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To Pickena J '
I To- Salem l /
i y 18 .
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181 N P
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Gliti '
j 18' " 's 160 I
Keowee . p Sc hool I u 133 au r* ::
Seneca 8 a 4.:
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13(b se O '
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4 ea gi EttERGENCY EVACUATIO11 It0UTES FROff STATIOli ?
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ASSEllui.Y AREAS:
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To be determined by Emergency Coordinator
- 3 i 1
Keowee School 131 l'
2 Daniel liigh School '
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. Daniel !
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I Iligh School 1 . :
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h'6 Clemson t
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. . ._ , l 1:0RB/AT10N OL.Y Form SPD-1002-1 O '
i DUKE POWER COMPANY (1) ID No:PT/0/B/2000/04 '
PROCEDURE PREPARATION Change (s) _
0 to
?ROCESS RECORD 0 Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Procedure for Establishment and Inspection of the Technical Support Center n (4) PREPARED BY: M%ss eje DATE: M / 2-(5) REVIEWED BY:
"~
Y DATE: j) 74L Cross-Disciplinary Review By:
f / /
N/R: /T[ _
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: 1(SRO) Date:
By: - Date:
) " '/
(7) APPROVED SY: l N lhi. lW t
Date: d fLT 7L s (8) MISCELLANEOUS:
Reviewed / App m.en By: ##M Date: #/P <- 4692 u r <
Reviewed / Approved By: Date:
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. PT/0/B/2000/04
.. Page 1 of 3 DUKE POWER COMPANY OCONEE NUCLEAR STATION PROCEDURE FOR ESTABLISHMENT AND INSPECTION OF THE TECHNICAL SUPPORT CENTER I
1.0 Purpose -
pThis 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 Ce'nter and specifies the in-spection frequency and documentation requirements.
2.0 References 2.1 Oconee Nuclear Station Emergency Plan 2.2 NUREG 0654, FEMA-REP-1, REV. , Criteria for Preparation and Eval-uation of Radiological Emergency Plans and Preparedness in Support of Nuclear Power Plants.
3.0 Time Required .
, O. 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. -
7.0 Required Station Status 7.1 Not applicable 8.0 Prerequisite System Conditions 8.1 Not applicable u
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l PT/0/B/2000/04 Page 2 of 3 9.0. Test Method C\
( I 9.1 All emergency supplies, equipment, and telephone numbers that would
) . \ be used upon activation of the Technical Support Center are to be inspected and/or reviewed on a quarterly basis.
10.0 Data Reuuired i
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.0conee Nuclear Station Emergency L
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 l
enclosures listed in 13.0 as a guide to inspect the following emer-gency equipment and supplies: i f'~'s 12.1.1 Verify all items for the Technical Support Center Telephone i I Communication System on Enclosure 13.2 are available and
' operational.
12.1.2 Verify that the Emergency Telephone Directories are current.
l l 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.
l
! 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:
12.2.1 Each Superintendent shall be responsible for having his emergenc3 telephone system switched to the Technical Support Cetter and/or Operational Support Center.
( 12.2.1.1 The phones for the Technical Support Center /
l , Operational Support Center shall be set up l according to the Check-Off List in Enclosure l f~s 13.2.
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f(._,/ 12.2.2 Follow Check-Off List for setting up the Technical Support Center, Enclosure 13.6, to determine that equipment, sup-i plies, documents, manuals, procedures are in place, i-I l.'
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PT/0/B/2000/04 Page 3 of 3 i
Time /Date Name 12.2.3 All supplies shall be inspected after the emergency, drill and/or exercise and replenished as necessary.
i 13.0 Enclosures l
13.1 Inventory List Checkoff 13.2 Check-off List for Setting up the Phone System in the Technical
., _ Support Center ,
4 .
13.3 General Arrangement of Technical Support Center
~
13.4 General Arrangement of Operational Support Center -
l 13.5 Eme:gency Teleph6ne Switching Diagram i 13.6 Check off List for Setting up the Technical Support Center
[
- 13.7 Drawings in the Technical Support Center ,
1
} g
! 1 l-l W
%A- A
PT/0/B/2000/04 TECHNICAL SUPPORT CENTER, INVENTORY LIST ENCLOSURE 13.1 Date -
v, 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
. I 13.1.9 2 Boxes Pencils.
fN 13.1.10 4 Bottles Nashua 3100 Dry Imager k_s s 13.1.11 2 Boxes Ball Point Pens 13.1.12 17 volt hand-h' eld light 13.1.13 ' 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 sapplies (minimum quantities inventoried) will be restocked after any emergency or after any drill or exercise where the Technical Support Center was activated.
\s~
m(-
OCONEE NUCLEAR STATION PT/0/B/2000/04 ENCLOSURE 13.2 7s- s 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 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 l 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.
1669 VAX 1670 VAX 1105 S&C 1108 NRC Res. Insp.
1138 Data Evaluator 1140 B&W 4
1417 Environmental 1244 Communicator 8
l 1177 H.P. Supvr. 1212 Administration
[h 1409 Performance 1233 1227 Clerical Support Maintenance
( ,,/
1229 L&P 1219 I&E i
1220 Chemistry 1216 P&M 1210 Operations 1223 M.M.
l 4 1213 Tech. Serv. 1211 Station Manager 1234 Station H.P. 882-7076 Station Manager
- NRC Red Phone HPN Black Phone Duke Ringdown 1151 Medical i
13.2.2 Secure key from Shift Supervisor to Technical Support Center Cabinet. Check each phone to make sure that a dial tone exists and that the line is operable -- incoming and outgoing.
13.2.3 Note t y problems encountered and list below.
I O\s. /
13.2.4 Lock telephone boxes.
l 13.2.5 Return telephone systems to normal service.
PT/0/B/2000/04 00KE POWER COMPANY EMERGENCY RESPONSE FACILITIES .
OCONEE NUCLEAR STATION
[ i
(, ,j Enclosure 13.3
\
\
j
'LJ l TECHNICAL SUPPORT CENTER Communication System Includes:
Outside Line (Southern Bell System)
ONS Switchboard Microwave Radio '
Computer (OAC, VAX, TS0)
Telecopier UNIT 1&2 CONTRCL RCCM
]
ENS (Red Phone)
HPN (Health Physics - NRC) b Ringdown phone to Of fsite Agencies (State FEOC, Oconee EOC, Pickens EOC) _
' I i r caAmNGs l Fitg3 CONFERENCE
~
11C8 5 GENERAL ARRANGEMENT g 6 . .,
{"
N ( " h. Support Functions es jl05 HPC 2 Coordinator =
!Y[s' TABLE E **
~
Ringdown Phone 5 $ . ?. hf 1417/RACIO *V x 17 "
- Health Physics to State and E C
~
4* $$2',
' 5 m
@:l h IFIL53 TAa x ,
r- Network HPt2 u
=
.J
% 79 6 1409 PERFCRMANCE Field Monitoring Coordinator IW 12iG ggo 3733 1:23 L & P , ,
"A DHCNE o f 20 CHEM. 682 7076
$ g
_ 2 1669 ~
Data Transmission -
m=e =
1670 - System mrus = canes COMPUTER -
- R C C?.s
's "
~ '
.- 20 x 20
[h t )
y
PT/0/B/2000/04
[t DUKE PO'RR COMPANY EMERGENCY RESPONSE FACILITIES OCCNEE NUCLEAR STATION Enclosure 13.4 OPERATIONAL SUPPORT CENTER
- I.oca tion: Unit #3 I & E Shop C050fUNICATION:
Nuclear l ONS Switchboard Equipment Microwave Operators lo' x 9' (Kitchen Unit 1&2 f Control r Room ) ir '
r-I I '
E e .
,/, R s.
/ i' Qj- -
Data Transmisdon r-l 1669- JC VAX 1670 7
J w 1177 Dosimetry .
27' Records L. ? C_,
1387 P&M 101 ISE Ffedical 1216 1222 121o 1151 41' ,
- The areas designated as the Operational Support Center has the same ventilation and shielding as the Control Room. Provisions for protective clothing and breathing apparatus have been established.
f E
EMERGENCY TF},EPIIONE SWITCilING DIAGRMI ENCLOSURE 13.5 1 I t i_ t , }_ l i 1234 1227 1213 1212 1211 L210 1151 RED RED RED RED RED RED RED I 6 h I
1105 1417 1140 1108 1244
, . - - = , . _ _ - - ,.
RED RED RED RED RED
~
I i I ! 8
!_ I __t 1 tiRC 882-- I 1220 It0T 1233 7076 1.1:!E .
3 I l
Bl.UE RED RED RED RED RED -.
I ' ' ' I-
- g. F - , ,
1 1229 ' 1223 1219 1216 1409
, \
BLUE BLUE BLUE BLUE BLilE
\ !!OISE Emergency Tele;ihone Switching Diagram li hones li.irliEll L'IIh
~17 RtiJ -7ndicat'e suilclids tYrothi at onset of .Tbc activatron
~
- 2. Blue - Indicate switches thrown as needed in TSC "To Switch All Phones !!arked Red Or Blue To:
. a. Unit 1 L 2 TSC throw switch to the right +,
b.. Unit 3 throu nuitch to Icft 4- , .
4
4 PT/0/B/2000/04 Page 1 of 2 OCONEE NUCLEAR STATION Check-off list for setting up the Technical Support Center
[ h ENCLOSURE.13.6 V Date/ Time Name
- 13.6.1 Set up phones - (Determine that phones have been switched in the telephone roon)
I 13.6.2 Set up radio.
. 13.6.3 Check off list of Documents needed.
Emergency Plan & Implementing Procedures e
Crisis Management Plan Pickens & Oconee Emergency Plan
}
Technical Specifications FSAR
__ GeneralArrangementprawings Emergency Planning Zone maps and nomographs i \...sl Safety related structures, systems and ccmponents Station Directiv's e
, Administrative Policy Manual
) Various I&E Drawings Site Drawings i Emergency Procedures Plant Operations Drawings Fire Plan 13.6.4 Paper & pads, pencils & pens, notebooks.
2 13.6.5 Set up TSC Logbook - record names of people in Technical Support Center
, 13.6.6 Determine if everyone has been called that is a part of the emergency response organization.
13.6.7 Notification Procedures Message forms Authentication Procedures
_ _ _ _ . , _ . . , . _ , , ._ . _y _
. __ y ,,, o_ .__y ---
- ~ ' ~
PT/0/B/2000/04 t Page 2 of 2 OCONEE NUCLEAR STATION Check-off list for setting up the Technical Support Center ENCLOSURE 13.6 (Cont'd) !
, :Date/ Time l .Name Crisis Telephone Directory 13.6.8 Contact Security - make sure Security is at the Control Room
. entrances. f i
i Sign people in and cut at that point. l 1
i.
Assign someone to keep the information posted. l j 13.6.10- VAX system on line and oper:ble.
j Plant Data system ODCAR system l 1 13.6.11 Transmission of info.rmation i l
j Teleccpier Copier -
i l
13.6.12 Drawings listed on Enclosure 13.6 taken out of cabinet and ,
i placed'in TSC.
i 13.6.13 Operational Support Center 1
! Personnel in place i
Supplies /first aid kits available
! Survey. instruments available t
4 Dosimetry >
a ,
j i j Protective Cabinet i
i.
4 U \up i
[
-- ----n, , , , ,, - .w-= ,, , -, . , , , , , , --n,---,--m.- , --,, - - - +- - - ,
. . PT/0/B/2C00/04 i Page 1 of 2 .
DR. WINGS IN TECHNICAL SUPPORT CENTER ENCLOSURE 13.7 g-~s Date/ Time i Name v J DR. WING NL?!BER 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 l 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 Arrangement, Plan Elevation 838 + 0
<w 0-12-A 13.7.11 General Arrangement, Cross Section Ns 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 Section 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 0-180 13.7.23 General Arrangement, Spent Fuel Pool n
jk ,) 0-460 13.7.24 Unit 1 Reactor Building Basement 777 + 6 0-461 13.7.25 Unit 1 Reactor Building Ground Floor 797 + 6
- ,- - --,,y.-- ..n,- -- ,-
PT/0/B/2000/04
- ** Enclosure 13.7 Page 2 of 2 Date/ Time -
Name .
l DRAWING NUMBER TITLE l 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 L
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 Uni.t 1 Re' actor 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 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 Floog 0-1460 13.7.36 Unit 2 Reactor Building Basement 777 + 6 1
0-1461 13.7.37 Unit 2 Reactor Building Ground 797 + 6 0-1462 13.7.38 Unit 2 Reactor Building Intermediate 825 + 0 0-1463 13.7.39 Unit 2 Reactor Building Operating Floor.844 + 6
. 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 Soutb 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 Bailding Operating Floor 844 + 6 0-2464 13.7.49 Unit 3 Reactor Building Top of Shielding 861 + 6
.q
( ; 0-2465 13.7 50 Unit 3 Reactor Building Sectional View South O
0-2466 13.7.51 Unit 3 Reactor Building Sectional View East 0-2467 13.7.52 Unit 3 Reactor Building Section
e C') CONTROL COPYa L/ Form SPD-1002-1 II' ORMAil0F ONLY
~
DUKE POWER COMPANY (1) ID No: CP/0/A/2004/03C PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA' Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Pest Accident Determination cf Chloride by Specific _
Ion Electrode Using Beckman 4300 Meter (4) PREPARED BY: _ ev Lt DATE: 4 u k %"2 -
(5) REVIEWED BY: DATE:
Cross-Disciplinary Review By: emdw
- N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
\
U} By: Data:
(7) AFPROVED BY: k IW Date: 4 b )L (8) MISCELLANEOUS:
Reviewed / Approved By: Date:
Reviewed / Approved By: Date:
(O) v
(h CP/0/A/2004/03C Y .
DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT DETERMINATION OF CHLORIDE BY SPECIFIC ION ELECTRODE USING BECKMAN 4500 METER 1.0 Discussion 1.1 Scope This procedure describes the specific ion electrode method for,the post accident determination of chloride ion concentration ([C1 ]) in the RCS when fuel damage is estimated to be greater than 1%.
1.2 Principle The chloride ion-sensitive electrode is a solid-state ion sensor.
The electrode uses a hgs /Hg2C1 2 rensing crystal at the tip of the g electrode. A potential is developed by chloride ions across this J crystal in much the same manner as a glass electrode responds to s/ hydrogen ions. The potential varies with the chloride ion concen-tration. At 25 C it exhibits a 59 mV decrease in potential for each ten-fold increase in chloride ion concentration. A plot of mV vs.
chloride concentration is prepared from standards of known chloride concentration. The chloride concentration of unknown samples can then be determined from this curve. A typical calibration curve is shown in Enclosure 6.4.
1.3 Eimits 1.3.1 This method is applicable in the range of 0.05 ppm to 1.00 ppm C1 .
1.4 Interferences 1.4.1 Exposing the chloride electrode to a pH > 7 will produce an oxide film on the sensing crystal reducing the elec-trode sensitivity. Accurate measurements can be made from 3 pH l'to 7. Treating all samples, standards and soak solutions with ISA will reduce the pH to N 2 and prevent the oxide film formation.
1.4.2 Variations in total ionic strength will affect the chloride je" s electrode response. Maintaining a constant total ionic
( ) strength over a wide concentration range by tree. .ng all i \s / , samples and standards with ISA will enhance the electrode sensitivity and accuracy.
i I
o
a
' CP/0/A/2004/03C 1.4.3 Ions which for~m very insoluble salts with mercury (such as f'~% S 2, I , Br , CNS ) or chromates will poison the sensing.
(N crystal reducing the electrode sensitivity. However n:r.e are expected to be present at the concentrations accessary for the poisoning to occur.
1.5 '
9 Precautions 1.5.1 DO NOT ATTEMPT ANY PHASE OF ANALYIS WITHOUT ICALTH PHYSICS COVERAGE!
Radiation exposure to an individual' during;all phases of ,
1.5.2 f analysis should be limited so as net to exceed a guarterly accumulative exposure of 3 rems whole body; 7.5 ptes , skin of wholebody; or 18 3/4 rems extremities respectivelyN All personnel will need prior. authorization frca ISC ts' t y knowingly exceed any erposure limit.' The exposure Ecceived' may require an occupational exposure penalty a'Kd/or a -
medical decision as to whether an individual can coatinue in radiation work.
1.5.2.1 Ifnecessarytoremedya:situatifn.Luaediately hazardous to life cud property, the Planned g Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholedody; 30 rems skyn'off wholebody; or 75 rems extremities. m , q ,,
[
1.5.2.2 If necessary to save lives or preve t lost of
\ lifeand/orextensivedamagetoproperty(ol-.Q' ,
untary basis only), the Planned Emergency 2.x- f f ' "
posure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of.wholebody;;
or 375 rems extremities. '
l.5.2.3 For Outside Services Personnel the Planned Emergency Exposure' will not exceed 5' rems wholebody; 30 rems skin of wholebody; 75 rems -
extremicies; or 15 rems other single organ.
I 1.5.3 Radiation levels of the lab area shall be measured con-tinuously during all phases of analysis.
1.5.3.1 Air activity should be determined by'use of installed air monitors or through the use of portable air sampling equipment. '
1.5.3.2 Area dose rates should be established'hy the use >
of installed radiation monitors or by portable radiation survey instrument.
I 1.5.3.3 Portable shielding, remote handlitg equipment,
'gq video equipment, etc., should be used where
[ ( 1 practical during sample preparation and sample
. \._ / analysis.
J a
i r .;.
--- -- -- ~- -
D
, s a
- f. ,
CP/0/A/2004/03C
'V
- 1. 5'. 4 Samples and standards shall be stirred during measurement
- i using a magnetic stirrer to reduce electrode response
'4 time.
1.5.5 Since electrode potentials are affected by changes in 1 temperature, samples and standards should not differ more j>
than 2 5 C.
NOTE: Temperature and slope controls are inoperative
, _a in the mV and mV abs mode.
k 'f 1
1.5.6 Samples containing more than 1 ppm chloride should be diluted to less than 1 ppm using demin water.
/' 1
,. 1.5.7 Mercuric salts are poisono'ust Gloves shall be worn when
'~ "
handling the chloride electrode.
- 3. ,
1.5.8 Never store both electrodes together in the same solution.
- , 1.5.9 The electrodes need not be immersed more than one (1) inch for accurate readings. However, they maybe immersed b --
1; - further to obtain more rapid temperature equilibrium.
F - 4 ,. ,,
- 1.5.10 'Always keep the reference electrode filling solution
, levels high'er than the level of solution being measured.
1.5.11 Never operate the reference electrode with the filling hole obstructed.
4 4
1.5.12
~
4 This procedure shall be done in a fume hood and/or other precautions shall be taken to avoid the release of gaseous activity.
i -2.0 Apparatus 2.1 Beckman 4500 Dig' ital pH/mV Meter 2.2. Chloride / Electrode (Graphic Controls PHI 91100 or equivalent) i
-2.3 DoublIJunctionReferenceElectrode(GraphicControlsPHE54473or equivalent)
. 2.4 Beckman 583540 Multiple Electrode Selector 2.5 Electrode' Holder
~ '
4 2.6 Magnetic Stirrer and Teflon-Coated Stirring Bars 72.7 Stopwatch, Clock or Timers Q -D 2.8 150 ml Glass Beakers 2.9 Eppendo'rf Pipettes with appropriate tips: 50., 100,'250, 500, 1000 pf.
Ai - 2.10 Graduated Cylinder,.100 ml-c r$...w) tw. -
fh. >
j w 9,y,; a --
~
- y .
L: 4
- CP/0/A/2004/03C 2.11 Thermometer 2.12 Polishing Kit (Graphic Controls PHA76518 or equivalent) 2.13 1 liter volumetric flask (as needed) 2.14 Erlenmeyer flask or as equivalent 2.15 Parafilm for covering beakers 2.16 Analytical balance 2.17 Shielded Sample Container 2.18 Sample Tongs 4
2.19 Carboy -
- 1 gal.
3.0 Reagents 3.1 Ionic Strength Adjustment Solution (ISA Solution) - slowly add about 63 mis (* 1 ml) of concentrated nitric acid to about 437 mis (t I ml) of demin water. Mix thoroughly. Stable for six (6) months.
3.2 Chloride stock standard solution (100 ppm,C1") - use purchased (Orion 94-17-07 or equivalent) 100 ppm Cl standard or prepare as h
\Q follows: dry sodium chloride (NaC1) to constant weight at N 105 :.
Dissolve 0.1649 g (t 0.0001) of the dry Nacl in demin water and dilute to 1 liter in a volumetric flask and mix. Purchased standard is stable indefinitely. Prepared standard is stable for six (6) months.
3.3 Double Junction Reference Electrode Filling Solutions 3.3.1 Upper filling solution - use the upper filling solution supplied (Graphic Controls PHB1322 or equivalent) with the double junction reference electrode. Stable icdefinitely.
3.3.2 Lower filling solution - use the lower filling solution supplied (Graphic Controls PHB1326 or equivalent) with the double junction reference electrode. Stable indefinitely.
4.0 Procedure
- 34. 1 Initial Condition .
4.1.1 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel, in the lab for the analysis.
4.1.2 Request HP to perform a constant radiation survey during
[' the analysis.
I
, m -
-w--
.. - . - - -.- . - - _ ~ - - - - - - . - - . . - _ - . .. . . - _ - _ - -
CP/0/A/2004/03C l
l
\
'4.1.3 Determine and use the required respiratory equipment and
1.00 ppm repeat 4.2.14 thru 4.2.19 using a more dilute sample.
4.2.19.2 If the sample concentration is < 1.00 ppm but
> 0.05 ppm apply the necessary dilution factor V and record on the calibration curve.
E
CP/0/A/2004/03C 4.2.19.3 If the sample concentration is < 0.05 ppm consider
[g repeating 4.2.14 thru 4.2.19 using a less dilute
\j sa7ple or apply the necessary dilution factor to
< 0.05 and record the "less than" value on the
<;alibration curve.
4.2.20 Place the mV meter in STA.DBY V and either repeat sections 4.2.15 to 4.2.19 for additional C1 measurements or pro-ceed to 4.2.21.
4.2.21 Rinse the electrodes with demin water and store the elec-trodes as follows:
~
4.2.21.1 Store tha Cl electrode in 100 ml of demin water containing 1 ml of ISA solution.
4.2.21.2 Store the reference electrode in a separate '
portion of demin water.
4.3 Waste Disposal 4.3.1 Dispose of all liquid analytical waste in the " Post Accident Liquid Lab Waste" carboy. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waste.
s g 4.3.2 Dispose of all solid analytical waste in the " Post Accident Solid Lab Waste" container.
I 4.3.3 Request HP to designate an area where both post accident
{ 1ab waste containers may be stored until final disposal.
4.3.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protectvie covering to prevent the spread of airborne activity.
4.4 Dose Exposure Evaluation 4.4.1 Evalusta the exposure to all personnel involved and com-plete all records, internal-body burden analysis, etc., as
. required. The exposure received may require an occupational exposure penalty. Higher doses will require a medical decision as to whether an individual can continue in radiation work.
5.0 References 5.1 Beckman Model 4500 Digital pH Meter Instruction Manual (1976) 5.2 . Graphic Controls PHI 9100 Chloride Electrode Instruction Manual
- ' 5.3 I. Sekerka, J. F. Lechner, and L. Harrison, Analysis for Chloride Ion in High Purity Water and Heavy Water of Pressurized Reactors and
.. Cooling Systems by Ion Selective Electrode (1977)
CP/0/A/2004/03C 5.4 .BAW Water Chemistry Manual, BAW-1385 (1975) 5.5 NUREG-0737 5.6 DPC System Health Physics Manual 5.7 Radiological Health Handbook, U.S. Dept. of HEW (1970) 5.8' Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev. 1 (1972) 6.0 Enclosures 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA 6.3 Conversion Factors '
6.4 Typical Calibration Curve 6.5 Manual Sample Dilution
'l CP/0/A/2004/03C ENCLOSURE 6.1 SHIELD THICKNESS The following equations can be used as an aid in determining shielding requireraents for a sample of RC$ after an accident.
given: I=Ie* g E
where: p = p,p I/I g =emY P* I In(I/I ) = -p,px in(Ig/I)
(eq. 6.1.1) **
p,p ,
where: x = thickness of absorber (cm) p = linear attenuation coefficient (cm l) p* = mass attenuation coefficient (cm 2/8) @ the energy 1evel (Mev) of the source p = density of the absorber material (g/cm ) 3
. o I = source intensity w/zero thickness of the absorber 1 (mR/hr or R/hr)
I l I = source intensity w/an x thickness of the absorber (mR/hr or R/hr)
~
given: (HVL) I/Ig= 1/2 = EY mP*
In(1/2) = -p,px
, (eq. 6.1.2) _ 0.693 p,p A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As I a general rule we add one HVL to our absorber thickness calculations I for conservatism:
i.
(eq. 6.1.3) _
I"(I /I) o + 0.693
- total - p,p U
L
CP/0/A/2004/03C 5NCLOSURE 6.2 5, A and R Values for 1% Failed Fuel and DBA 1% Failed Fual:
- 5
- 0.34 MeV/ dis. AN 0.293 mci /ml R = 0.18 mR/hr-mci @ Im for 5 % 0.34 MeV j 100% Failed Fuel'or Design Basis Accident (DBA) 5$ 1.14 MeV/ dis. A
- 1.324 x los pCi/ml R = 0.58 R/hr-Ci @ im for 5
- 1.14 MeV A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.
1 e
5 4
"'~
CP/0/A/2004/03C ENCLOSURE 6.3 CONVERSION FACTORS Source Activity - (A) 1 Curie (Ci) = 3.7 x 1010 dis./sec. = 2.22 x 1012 dpm 1 mci = 3.7 x 10 7dps = 2.22 x 108 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 10sdpm R _
mR hr-Ci hr-mci Density - (p)
(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm3 Mass Attenuation Coefficient - (p,)
(p ) for elements and common materials at varying energy levels (i@el) for the source can be found on pg. 137 thru 139 of the
" Radiological Health Handbook."
Distance - (d) given: I g/I = d 2/d g2 where: I n= Source intensity (mR/hr or R/hr) @ distance (d )g I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.
I ft.= 0.305 m 3 ft. = 0.914 m O
b en m- -
. Ixct.osuar 6.4 cP/o/A/2cc4/03c 1.00. _
_;r_ . .! i ,- . .
.i
._4 .
., - ., 6
.- . : i i n .. .. i ,
0.90
.., enn, .gm .. p ... . m . .c , ya , , mf . .. .
CN : -:- i : { . a ret t a ,r t.=ri s t sid s t + ::*:1 ut ~ t- *{t : ): r tre r r;;j-:.t- arytt r f_ .2- t r t::: t : : rt: ;-
on:_cr.su r -1::=t =-issn-manm =sh: .m= 1 m: 51 - .- - M==sil:_::p + ; :h f n W. W- til:
w -.-
!M:s WfMEER F4 i+ L
. i H d 4:isii:nM iiGiiWE:Mi#S=4 21:41=2 t2 ": -U i+"" A . ;i=
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CP/0/A/2004/03C ENCLOSURE 6.5 MANUAL SAMPLE DILUTION 6.5.1 Place a magnetic stirrer in the shielded work area.
6.5.2 Partially fill a glass volumetric flask with demin water and place on the magnetic stirrer in the shielded work area.
~6.5.3 Using tongs remove the sample from the shielded sample container and place in the shielded work area.
6.5.4 Using a pipette transfer enough sample to the volumetric flask to produce the desired dilution.
6.5.5 Fill the volumetric flask to the mark with demin water, insert a stirring bar and cap.
6.5.6 Using tongs place the sample back into the shielded sample container. .
6.5.7 Stir the diluted sample for ~ 5 min and allow to remain in the shielded wrk area until ready for analysis or disposal.
m 6.5.8 Repeat 6.5.1 thru 6.5.7 for additional samples.
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- . 1 pJ CONTROL COPY
\MECWMIO
,_ S,D_1ce.1 DUKE POWER COMPANY (1) ID No:CP/0/A/2004/02E PROCEDURE PREPA2ATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee Nuclear Station .
(3) PROCEDURE TITLE: Post Accident Deter.ination of Boron Concer.tration Using Carminic Acid (4) PREPARED BY: b ,,, e k. DATE: Sk L3 % "L (5) REVIEWED BY: '
DATE: E E
//
Cross-Disciplinary Review By:CCx al N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
'N' By: G Date: ,
(7) APPROVED BY: Ls.
i b -
lw%- Date: d 2 l- d L L
(8) MISCELLANEOUS:
Reviewed / Approved By: Date:
Reviewed / Approved By: Date:
e l b L
,' CP/0/A/2004/02E Page 1 of 12 L
DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT DEIERMINATION OF BORON CONCENTRATION USING CARMINIC ACID 1.0 Discussion 1.1 Scope ,
This procedure describes the colormetric method for the post accident determination of boron concentration ([B]) in the RCS when fuel damage is estimated to be greater than 1%.
1.2 Principle
- l In concentrated sulfuric acid, boron forms a red colored chelation I complex with carminic acid by splitting off water. Due to its hygroscopic nature, sulfuric acid aids in splitting off the water and prevents the reaction from reversing. Hydrochloric acid is added to inhibit the interference of nitrates. The intensity of the red color is proportional to the concentration of boron ([B]) in the sample, that is, it obeys Beer's law.
O 1.3 Limits v 1.3.1 This method is applicable in the range of 0.1 to 2.0 ppm B.
1 1.3.2 Refer to CP/0/B/2001/03 for the laboratory quality control of the spectrophotometer.
1.4 Interferences 1.4.1 Substances normally present in reactor coolant do not interfere with this test.
1.4.2 Colors at 590 nm interfere, however, none are expected.
1.5 Precautions 1.5.1 DO NOT ATTEMPT ANY PHASE OF ANALYIS WITHOUT HEALTH PHYSICS COVERAGE!
1.5.2 Radiation exposure to an individual during all phases of analysis should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively.
bs \
All personnel will need prior authorization from TSC to knowingly exceed any exposure limit. The exposure re-k ceived may require an occupational exposure penalty and/
= . - -. __
k-CP/0/A/2004/02E
- . Page 2 of 12 or a medical decision as to whether an individual can s continue in radiation work.
1.5.2.1 If necessary to remedy a situation immediately ;
hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities 1.5.2.2 If necessary to save lives or prevent loss of life and/or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities.
1.5.2.3 Fcr Outside Services Personnel the Planned
l l'. 5 . 3 Radiation levels of the lab area shall be measured con-tinuously during all phases of analysis.
1.5.3.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.
i
- 1. 5 . 3 . 2 Area dose rates should be established by the use of installed radiation monitors or by ports',1e radiation survey instrument.
1.5.3.3 Portable shielding, remote han'dling equipment, video equipment, etc., should be used where practical during sample preparation and sample analysis. ;
1.5.4 Water droplets or smudge marks on the cuvettes will cause an error in absorbance. Ensure light path surfaces of cuvettes are clean and dry.
9 1.5.5 Matched cuvettes shall be used in order to correct for absorption due to the glass surfaces of the cuvette.
1.5.6 Clean cuvettes with dilute nitric acid (1 + 99), air dry, and rinse with several small portions of standard or sample before filling and reading the absorbance.
U.S 7 Samples containing more than 2 ppm B should be diluted to less than 2 ppm usign demineralized water.
1.5.8- The carminic acid solution is hygroscopic (absorbs water).
fq
- Keep tightly capped except when using.
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. _ _ _ _ . . . _ _ , _ ~- - _ . - , - - - - - - - -
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CP/0/A/2004/02E Page 3 of 12 1.5.9- This procedure shall be done either in a fume hood and/or other precautions shall be taken to avoid the release of gaseous activity.
1.5.10 Maximum color development requires approximately one hour with the color intensity decreasing slightly thereafter, but is of little consequence if standards are run simul-taneously with the samples.
2.0 Apparatus 2.1 Spectrophotometer suitable for measurement at 590 nanometers (nm) - (Bausch and Lomb Spectronic 70 or equivalent).
2.2 50 mm cuvettes, matched, nitric acid washed,'and air dried 2.3 5 ml glass pipettes - nitric acid washed .
2.4 Dispensers, preset for 5 ml and 30 ml 2.5 Dropper bottle 2.6 Disposable beakers 2.7 100 ml glass volumetrir flask's - nitric acid washed 2.8 Eppendorf pipettes with appropriate tips: 10, 25, 50, 100 pl 2.9 Parafilm for covering beakers 2.10 Analytical balance 2.11 Shielded Sample Container
- 2.12 Sample Tongs 2.13 Poly bottles - 60ml (2 oz.) size 2.14 Carboy - % 1 gal.
3.0 Reagents '
3.1 Carminic Acid Solution - Dissolve 0.50 g (t 0.01 g) of carminic acid in'100 mis of concentrated sulfuric acid. Mix thoroughly until solution is complete. Store in a plastic bottle. This solution is relatively stable for several days, but exercise care to prevent water absorption. Discard after seven (7) days.
3.2 Boron Standard (s 1000 ppm B) - Standardize either the purchased or ,
prepared standard before use per CP/0/A/2004/02A or CP/0/A/2004/02B.
')'
3.2.1 Parchased Standard - Use Fisher S0-B-155 or equivalent.
Check the expiration date before use and discard if expired.
3.2.2 Prepared Standard - Dissolve about 5.72 g (t 0.01 g) of boric acid in demin. water and dilute to 1 liter with L..- ,
. . , CP/0/A/2004/02E Page 4 of 12
- i demin. water in a volumetric flask and mix. Stable for w two (2) weeks.
)
d 3.3 Concentrated Hydrochloric Acid - Use from dropper botti.e. Sp. Gr.
1.19.
. 3.4 Concentrated Sulfuric Acid - Sp. Gr. 1.84.
3.5 Nitric Acid (1 + 99) - Mix 1 volume of concentrated nitric acid-(Sp.
Gr.1.42) to 99 volumes of water.
4.0 Procedure 4.1 Initial Conditions 4.1.1 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel, in the lab for the analysis.
4.1.2 Request HP to perform a constant radiation survey during the analysis.
4.1.3 Determine and use the required respiratory equipment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation. Use high range and/or extremity dosimetry if required by HP.
4.1.4 Prepare one (1) carboy (* 1 gal.). Label as " Post Accident Lab Waste". This container must be shielded and used as interim liquid waste disposal container for all liquid analytical waste.
4.1.5 Prepare a shielded work area in a fume hood. This area must be used for handling the sample when it is removed from the shielded sample container.
4.1.6 Prepare a waste disposal container for all solid analytical waste. Label as " Post Accident Lab Waste".
4.1.7 Check the serial numbers of the cuvettes to ensure that they are matched. Visually check the cells for scratches, cracks, chips and discoloration. Replace or clean as necessary.
4.138 Clean cuvettes with dilute (1 + 99) nitric acid and air dry.
4.1.9 Prepare a 1:2000 sample dilution using the post-accident sample panel or by the manual method described in Enclosure 6.5. Ensure 5 ml of diluted sample for the analysis, g
v) 4.2 Concentration Measurements
-^
, , CP/0/A/2004/02E Page 5 of 12
~
4.2.1 Prepare a series of boron standards in 100 ml volumetric flasks by diluting measured volumes of 1000 ppm boron g ) standard with demin. water to produce 100 mi solution of Nd the concentrations as follows:
4 -
pl of 1000 ppm stock diluted to 100 ml = ppm B 10 pl 0.10 25 pl 0.25 50 pl 0.50 100 pl 1.00 200 pl 2.00 4.2.2 Pipet 5 ml of demin. water (reagent blank) and each sta.ndard to separate beakers and cover.
, 4.2.3 Pipet 5 ml of the 1:2000 sample dilution (s) to separate beaker (s) and cover.
- 4.2.4 To each beaker, add 5 drops of conc. hcl and 30 ml of conc. H2 SO4 , swirl to mix and cover. Allow approximately 15 minutes for cooling (less time will be needed for cooling if an ice bath is used to cool the samples).
CAUTION: Hydrogen chloride fumes and large amounts of heat may be generated during this phase.
Add the conc. H2 SO 4 slowly and exercise care.
N 4.2.5 Add 5 ml of carminic acid solution to each beaker and swirl to mix. Cover and allow to stand approximately 45 minutes for full color development.
4.2.6 Rinse a clean and dry 50 mm cuvette with several small t
portions of the reagent blank before filling the cuvette completely.
4.2.7 Set the Spec-70 wavelength to 590 nm and set the absorbance to zero with the resgent blank.
4.2.8 Record the absorbance of each reacted standard in order of increa' sing concentration - rinse the matched 50 mm cuvette with several small portions of each standard before filling the cuvette completely and reading the absorbance of that standard. ,
4.2.9 Record the absorbance of each reacted sample - rinse a clean and dry 50 mm cuvette with several small portions of each sample before filling the cuvette completely and reading the absorbance.
4.2.10 Plot the data obtained in 4.2.8 on linear graph paper I
/'~N as shown in Enclosure 6.4. i e
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l
. CP/0/A/2004/02E Page 6 of 12 4.2.11 Compare the abs. reading (s) from 4.2.9 to the calibration curve.
\ 4.2.'1.1
. If the sample concentration is > 2.00 ppm repeat 4.2.1 thru 4.2.11 using a more dilute sample.
4.2.11.2 If the sample concentration is < 2.00 ppm but
> 0.10 ppm apply the necessary dilution factor and record on the calibration curve.
4.2.11.3 If the sample concentration is < 0.10 ppm consider repeating 4.2.1 thru 4.2.11 using a less dilute sample or apply the necessary dilution factor to < 0.10 and record the "less than" value on the calibration curve.
. 4.3 Waste Disposal
- 4.3.1 Dispose of all liquid analytical waste in the " Post Accident Liquid Lab Waste" carboy. This container must be shielded
! and used as an interim liquid waste disposal container for
- i. all liquid analytical waste.
- 4.3.2 Dispose of all solid analytical waste in the " Post Accident i
Solid Lab Waste" container.
i 4.3.3 Request HP to design'tea an area where both post accident lab waste containers may be stored until final disposal.
4.3.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.
4.4 Dose Exposure Evaluation s 4.4.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc., as required. The exposure received may require an occupational exposure penalty. Higher doses will require a medical decision.as to whether an individual can continue ia radiation work.
5.0 References
'5.1 ASTM, Part 31, D 3082-79-Method A (1980) 5.2 B&W Water Chemistry Manual, BAW-1385 (1973) 5.3 NUREG-0737
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- .. .. CP/0/A/2004/02E Page 12 of 12 ENCLOSURE 6.5 MANUAL SAMPLE DILUTION i
6.5.1 Place a magnetic stirrer in the shielded work area.
6.5.2 Partially fill a glass volumetric flask with demin water and place on the magnetic stirrer in the shielded work area.
6.5.3 Using tongs remove the sample from the shielded sample container and place in the shielded work area.
1 6.5.4 Using a pipette transfer enough sample to the volumetric flask to produce the desired dilution. .
- 6.5.5 Fill the volumetric flask to the mark with demin water, insert a stirring bar and cap.
6.5.6 Using tongs place the sample back into 2e shielded sample container.
6.5.7 Stir the diluted sample for ~ 5 min and allow to remain in the ,
shielded work area until ready for analysis or disposal. '
6.5.8 Repeat 6.5.1 thru 6.5.7 for additional samples.
l t
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DUKE POWER COMPANY (1) ID No: CP/0/A/2005/02D l PROCEDURE PREPARATION Change (s) NA to f PROCESS RECORD NA Incorporated l (2) STATION: Ocenee Nuclear Station (3) PROCEDURE TITLE: Post Accident Detomination of Ga= a Isotopic Activity Y (4) PREPARED BY: b . i e_w h $ tt_ DATE: Ql M 67 (5) REVIEWED BY:
DATE: N [b Cross-Disciplinary Review By Om N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
O By: - Date:
\ -, \
(7) APPROVED BY: % Oh Date: .'
(8) MISCELLANEOUS:
Reviewed / Approved By: Date:
i Reviewed / Approved By: Date:
- - y m - yyy-y
s CP/0/A/2005/02D g
DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT DETERMINATION OF GAMMA ISOTOPIC ACTIVITY 1.0 Discussion ,
1.1 Scope - This procedure descefbes the post accident determination of gamma isotopic activity as measured by gamma ray spectrometry in the RCS when fuel damage is estimated to be greater than 1%.
1.2 Principle - Gamma interact with lithium drifted germanium diodes,or Ge(Li) detectors, having an applied electric field, to produce electric charge pulses. These pulses are proportional to the energy lost by the incident gamma. Amplifiers amplify these electric pulse to produce voltage pulses. The multichannel analyzer (MCA) determines the amplitude of each voltage pulse and accumulates in a memory the number of pulses (or counts) in each amplitude band (or channel) in a given period of time. The number of counts accumulated in each channel forms a continuous curve of photopeaks called a " gamma spectrum".
The location of a photopeak in the gamma spectrum is proportional to the gamma energy of the incident gamma and is the basis for identi-fying a particular isotope in a sample. The area or total counts under a photopeak then represents the gamma activity of that partic-ular isotope in the sample. Isotopes and their gamma activity are identified and calculated by computer program using the sample data stored in the MCA memory and reference data stored in a library file on magnetic disc. The results of the " pulse-height analysis" is presented on a paper printout. See Enclosures 6.1 and 6.2.
Certain conditions may require manual identification of photopeaks and calculation of gamma activity for isotopes not listed in the nuclide library as identified by computer program. The process of identifying photo p'eaks and calculating gamma activity is presented in this procedure.
1.3 Limits 1.3.1 The sample size and geometry must be selected such that less than 15% deadtime is encountered at the Analog to Digital Converter (ADC).
1.3.2 .The lower limit of detectability is dependent on the o background of the detector system in use, elapsed count l I ) time, sample size, sample geometry, detector efficiency l
'\j and isotopes present. I 1
, .: CP/0/A/2005/02D s 1.4 Interferences (s_,) 1.4.1 Variations in sample geometry can cause both qualitative and quantitative variations in the gamma ray spectrum.
Calibration sources duplicating standard sample geometries can account for geometry effects.
1.4.2 Electronic characteristics such as deadtime, resolution and pulse pile-up degrado with increasing sample activity.
Maintaining the deadtime below 15% by reducing the sample activity via decay or volume reduction and interpreting the gamma spectrum via computer program can provide easier and more reliable sample analysis.
1.5 Precautions 1.5.1 DO NOT ATTEMPT ANY PHASE OF ANALYSIS WITHOUT HEALTH PHYSICS
- COVERAGE!
i' 1.5.2 Radiation exposure to an individual during all phases of analysis should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively.
All personnel will need prior authorization from TSC to kneeingly exceed any exposure limit. The exposure re-ceived may require an occupational exposure penalty and/
or a medical decision as to whether an individual can continue in radiation work.
~
k 1.5.2.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.
1.5.2.2 If necessary to save lives or prevent loss of i
life and/or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of
' wholebody; or 375 rems extremities.
1.5.3 Radiation levels of the lab area shall be measured con-tinuously during all phases of analysis.
1.5.3.1 Air activity should be determined by use of I.
l
[N
( ,j) installed air monitors or through the use of
_ portable air sampling equipment. 1
,~ .
t t '- 0-1
- CP/0/A/2005/02D d
1 1
1.5.3.2 Area dose rates should be established by the use '
[ of installed radiation monitors or'by portable radiation survey instrument.
1.5.3.3 Portableshielding,remotehandliAg: equipment, video equipment, etc., should be used where practical during sample preparation and's~ ample analysis.
1.5.4 Ensure sample container has not leake'd prior,to sealing in poly bag.
1.5.5 This procedure shall be done in a fume hood and/or other precautions shall be taken to avoid the releas.e of gaseous activity.
2.0 Apparatus
- 2.1 15 cc glass gas vials with rubber septum 2.2 Hypodermic syringe - assorted sizes 2.3 Plastic Petri Dishes (2")
y 2.4 Poly bottles: 50 ml, 500 ml, 1000 ml and 3500 ml. . /
2.5 Ge(Li) detector and multichanral analyzer (ND6600 or equivalent) I\
k 2.6 Shielded Sample Container ,
2.7 Sample Tongs -
2.8 Carboy - ~ 1 gal. ,
3.0 Reagents - None 4.0 Procedure .
4.1 Initial Conditions 4.1.1 Evaluate the use of portable shielding, remote handling 9 equipment, video equipment, etc., to minimize the exposure to personnel, in the lab for the analysis.
4.1.2 Request HP to perform a constant radiation survey during the analysis.
4.1.3 Determine and use the requir.d respiratory equipment and -
protective clothing to prevent or minimize interal' exposure- ~
in any Planned Emergency situation. Usc Sigh range and/or.
extremity dosimetry if required by HP.
(G) 4.1.4 Prepare one (1) carboy (~ l gal.).
Lab Waste".
Label as " Post Accident i
This container must be shielded and used as intedim _ liquid waste disposal container for 111 liquid analytical waste.
+
1 *
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- J. -
c CP/0/A/2005/02D
- 4. L5 Prepare a shie"1ded work area in a fume hood. This area A) must be used for handling the sample when it is removed 3 - -
( from the shielded sample container.
%./
4.1.6 Prepare a waste disposal container for all solid analytical waste. Label as " Post Accident Lab Waste".
4.1.7 Prepare a sample dilution using the post-accident sample panel or by the manual method described in Enclosure 6.6.
/
4.2 Preparation of Gas Samples for Counting
}
4.2.1 Remove about 10 cc of air from a sealed and labeled gas vial
, , using a syringe to extract the air.
4.2.2 Insert the syringe needle through the rubber septur of the sample gas bomb. Adjust the volume of sample in the syringe to the desired volume (based on activity). -
4.2.3 Quickly remove the syringe from the sample gas bomb and
> insert the syringe needle through the rubber septum of the gas vial, inject the sample and remove the syringe from
, the gas vial. .
,_ 4.2.4 Seal the vial in a poly bag and store in a plastic bag.
Allow the vial to remain in the shielded work area until e -
ready for analysis or disposal.
t V)l, -
, 4.3 Preparation of Liquid Samples for Counting 4.3.1 Transfer the desired volume of the sample dilution (based on activity) to a labeled poly bottle. The Ge(Li) system is calibrated for 50 ml, 500 ml, 1000 ml and 3500 ml geo-
- metries.
4.3.2 Seal the poly bottle in a poly bag and store in a plastic bag. Allow the poly bottle to remain in the shielded work area until ready for analysis or disposal.
j'- --
' 4. 4 Waste Disposal 4.4.1 Dispose of all liquid analytical waste in the " Post Accident Liquid Lab Waste" carboy. This container must be shielded
_^ '
". and used as an interim liquid waste disposal container for
, all liquid analytical waste.
4.4.2 Dispose of all solid analytical waste in the " Post Accident 3
. Solid Lab Waste" container.
4.4'.3 Request HP to designate an area where both post accident '
'/ , lab waste containers may be stored until final disposal.
A (d
)
'i
- 4. 4'. 4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.
N am em *M"
. - - ._ - . - =-. .. .- . -
CP/0/A/2005/02D 4.5 Dose Exposure Evaluation 4.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc. ,. as required.
The exposure received may require an' occupational exposure penalty. Higher doses will require a medical decision as to whether an individual can continue in radiation work.
5.0 References b
5.1 BAW Water Chemistry Manual, BAW-1385 (1973) 5.2 BAW Radiochemistry Manual, BAW-1410 (1975) 5.3 ASTM, Part 31, D3649-78 3
5.4 ASTM, Part 31, ANSI / ASTM D2459-72 5.5 NUREG-0737 5.6 DPC System Health Physics danual 5.7 Radiological Health Handbook, U.S. Dept. of HEW (1970) 5.8 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev. 1 (1972)
')
,,/ 6.0 Ecclosures 6.1 Title Page of ND6600 Print-out 6.2 Summary Page of ND6600 Print-out .
6.3 Shield Thickness 6.4 5, A, and R valves for 1% Failed Fuel and DBA 6.5 Conversion Factors 6.6 Manual Sample Dilution O
_ m e w. . _
w-**~*o*ee..e********************r********************o*******
.**o*+**o*o**o*+o* 13 NOV 1990 12: 41: 13 'AM o*++o*****+****** (NCTE 1)
- o**o**oo*o**oo*****ooo**o*o*****************oo*** .
CHEM. 2 LPI CRUD SRWP 4 . (NOTE 2) ENCLOSUNE6.1 MPLE DATE: 7NOV80 1820:00 MPLE IDENTIFICATION: CRUD FILTER YPE OF SAMPLE: SOLIDS
' SAMPLE QUANTITY: 100.0000 UNITS: ML SAMPLE OEOMETRY: FILTER AT 6CM EFFICIENCY FILE NAME: EFF.CFILT6 ACQUISITION DATE: 13NOV80 29: 37
- FWHM(1332) 1.856 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY: 5.000 ELAPSED REAL TIME: 644. SEC
- SHAPE PARAMETER : 35.0 %
ELAPSED LIVE TIME: 600. SEC
- NER ITERATIONS: 10.
G*************************************************************
DETECTOR: GELI-C
- LIBRARY: NUCL. MASTER DATE CALIBRATED: 12NOV80 29: 45
- ENERGY TOLERANCE: 1.750KV -
KEV /CHNL: 0.5004218
- HALF LIFE RATIO: 8.00 OFFSET: -0.1842307 KEV
- ABUNDANCE LIMIT: 80.00%
o444**********************************************************
COLLECTED BY:
- COUNTED BY:
RWP/SRWP/ LWR /GWR:
- COMMENTS:
p l0PIRATORY EQUIP USED:
(
- N .40NTROL GROUP USE)
- o*************************************************************
DEAD TIME: 7.33%
ACTION REQUIRED: NONE o*************************************************************
ENERGY WINDOW 32.343 TO 2046.541 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT l 1 0 67.07 1451. 17278. 1.71 134.39 130 9 2.418E 00 13. 1 l
2 0 80.27 17243. 25599. 1.66 160.77 154 14 2.874E 01 1. 5 l 3 0 109.63 294 11084. 1.24 219,45 213 6 4.900E-01 51.0 4 0 140.56 7004 23187. 1. 73 281.25 276 12 1.167E 01 3. 3
, 5 0 145.32 790. 13928. 1.52 290.77 288 7 1.317E 00 21.4 6'O 153.31 656. 16112. 2.09 306.73 304 7 1.093E 00 27.7
- 7 0 162.33 9200. 27129. 1.61 325.75 320 12 1.533E 01 2. 7
, 8 0 176.99 2423. 20205. 1. 91 354.05 350 9 4.030E 00 8. 5 l 9 0 273.52 610. 9725. 1.56 546.94 543 9 1.016E 00 23.2 l 10 0 284.35 20076. 15503. 1. 78 568.59 561 15 3.346E 01 1. I 11 0 304.87 3257. 12620. 1. 88 609.59 603 13 5.42SE 00 5. 2
,_,12 0 319.36 1954. 10192. 1.56 639.55 634 11 3.256E 00 7. 7
( X3 0 329.34 13920. 15892. 1.74 657 43 652 16 2.320E 01 1. 5
( 14 0 340.51 2337. 9485. 1.66 680.S1 676 11 3.896E 00 6. 2
~'15 0 244. 51 205590. 15875. 1. 79 728.78 721 19 3.426E 02 0. 2 16 0 423.56 2152. 6074. 1. 56 846.77 340 13 3.537E 00 5. 6 17 3 432.50 1577. 3230. 2.00 864.64 853 24 2.629E 00 5. 7 1.56E 00 le 3 437.54 1091. 2755. 1. 79 974.70 858 24 1.81?E 00 7. 5 19 0 487.05 22400. 7556. 1. 37 973.64 96" 19 3.737E 01 0. 9 20 0 496.95 179. 3142. 1. 08 993.42 990 8 2.975E-01 45.0
( 3 .3 e..s S -- w m :- , i- ime % 5 .vo o 3 n 4.- -- nn ,e v
CP/0/A/2005/02D Page 1 of 2 INCLOSURE 6.1
/
LEGEND FOR ENCLOSURE 6.1 NOTE 1: Date print-out generated.
NOTE 2: Title of sample.
SAMPLE DATE: Date sample collected.
SAMPLE IDENTIFICATION: Description of sample container (vial, bottle or filter).
TYPE OF SAMPLE: Gas, liquid or solid.
SAMPLE QUANTITY: Number of units and unit type for sample distributed in sample container. -
SAMPLE GEOMETRY: Sample container at the specified distance from the detector.
EFFICIENCY FILE NAME: Describes the efficiency curve referenced as a function of the geometry.
- ACQUISITION DATE
- Date data acquisition began.
PRESET TIME (LIVE): User specified count time in seconds.
's ELAPSED REAL TIME: Elapsed clocktime in seconds.
ELAPSED LIVE TIME: Elapsed ADC time in seconds.
FWHM: During detector calibration, the ratio of the peak width at half its maximum height of the 1332 kev (Co-60) peak is calculated. The Peak Search program applies this value to each peak to determine if it is a single or multiplet peak.
SENSITIVITY: The Peak Search program will ignore a peak whose height is lest than the selected number of standard deviations above the average background in the region of the peak.
SHAPE PARAMETER: A channel must be greater than the average background in the region of the peak by the specified percentage to be considered as part of the peak area.
NBR ITERATIONS: To analyze multiplet peaks, the Peak Search program will successively refine the shape of the peaks (run a line thru the points) until successive " passes" over the peaks do not differ significantly or until the maximum number (NBR) of passess as specified are reached.
%e.gf P-
. CP/0/A/2005/02D Page 2 of 2 ENCLOSURE 6.1 h
J DETECTOR: The user-selected detector used.
DATE CALIBRATED: Detector /ADC calibration date.
KEV /CHANL: Slope of the energy calibration curve in kev / Channel.
OFFSET: Intercept of the energy calibration curve in kev.
LIBRARY: Library file used for identification of peaks.
ENERGY TOLERANCE: The ND program compares the kev of detected peaks with the kev of known nuclides from the selected library file. A detected peak will be accepted as a known nuclide if its kev is within (t) the selected energy tolerance of the known nuclides kev.
- HALF LIFE RATIO: For a nuclide to be considered genuine, 8 half-lives must not be exceeded between the Sample Date and the Acquisition Date.
ABUNDANCE LIMIT: The ND program will accept the identification of a nuclide having multiple gammas if the total detectable abundance exceeds the selected percentage of the nuclides absolute abundance.
9 i
i v
- .v'.t. n. c 4ucustev.metua 6 cm w.sv v*, u e r i TUMMARY OF NUCLIDE ACTIVITY PAGE 4 .
TOTAL LINES IN SPECTRUM 58 LINES NOT LISTED IN LIERARY 13 ENCLOSURE 6.2 IDENTIFIED IN
SUMMARY
REPORT 42 72.41%
C\
&FISSION GAS .
NUCLIDE HLIFE HLSEC DECAY UC/UT ERROR % ERR XE-131M 1.19E 01D 1.028E 06 2.264E -3 2.297E -2 6.239E -4 2.74 XE-133 5.25E OOD 4.536E 05 3.338E -3 3.115E -3 4.726E -5 1.52 ACTIVATION PRODUCT NUCLIDE HLIFE HLSEC DECAY UC/UT ERROR % ERR CR-51 177E 01D 2.393E 06 1.901E -3 1.645E -3 1.25GE -4 7.65 MN-54 3.12E 02D 2.700E 07 1.686E -3 8.840E -5 1.100E -5 12.44 CC-58 7.08E 01D 6.117E 06 1.755E -3 5.703E -3 3.462E -5 0.61 FE-59 4.46E 01D 3.853E 06 1.809E -3 1.457E -4 2.329E -5 15.99 CO-60 5.27E 00Y 1.663E 08 1.670E -3 1.415E -4 1.247E -5 8.81 AG-110M 2.51E 02D 2.167E 07 1.691E -3 4.230E -4 1.263E -5 2.99 HALOGEN FISSION PRODUCT NUCLIDE HLIFE HLSEC DECAY UC/UT ERROR % ERR I-131 8.04E 00D 6.947E 05 2.623E -3 3.294E -2 7.806E -5 0.24 I-133 2.08E 01H 7.48SE 04 1.119E -1 3.218E -2 1.142E -3 3.55 N
\
s / .
FrdSION PRODUCT '
NUCLIDE HLIFE HLSEC DECAY UC/UT ERROR % ERR ZR-95 6.40E 01D 5.528E 06 1.764E -3 1.276E -4 1.616E -5 12.66 NS-95 3.52E 01D 3.037E 06 1.849E -3 2.312E -4 1.514E -5 6.55 RU-103 3.93E 01D 3.400E 06 1.828E -3 2.556E -5 1.151E -5 45.04 C3-134 2.06E 00Y 6.501E 07 1.675E -3 1.186E -3 2.063E -5 1.74 C3-136 1.31E 01D 1.132E 06 2.202E -3 7.144E -4 1.683E -5 2.36 CS-137 3.02E 01Y 9.521E 08 1.667E -3 1.259E -3 1.776E -5 1.41 BA-140 1.28E 01D 1.105E 06 2.216E -3 8.845E -3 1.CC1E -4 1.38 LA-140 4.02E 01H 1.44SE 05 1.468E -2 4.826E -2 4.068E -4 0.84
CP/0/A/2005/02D Page 1 of 1
- ESCLOSURE 6.2 LEGEND FOR ENCLOSURE 6.2 TOTAL LINES IN SPECTRUM: Total number of peaks found by Peak Search program.
LINES NOT LISTED IN LIBRARY: Number of peaks not identifiable by the ND program.
- IDENTIFIED IN
SUMMARY
REPORT: Number of peaks identif,ied and accepted.
NUCLIDE: The nuclides identified by the ND program.
HLIFE: The half life of the identified nuclides in scientific notation with the appropriate time.
< HLSEC: The half life of the identified nuclide converted to seconds in scientific notation.
DECAY: The ratio of the elapsed time between the Sample Date and the
- Acquisition Date to the HLSEC.
UC/UT: The activity of the identified nuclides in pCi per unit of volume or weight.
ERROR: The confidence level (standard deviation) at I sigma, of the activity
,,) of the identified nuclides in pCi/ unit volume or weight.
% ERR: The standard deviation (t I sigma) in percentage.
a
_-..4. -
e.--w --m m--
CP/0/A/2005/02D Page 1 of 1
. s ENCLOSURE 6.3 SHIELD THICKNESS The following equations can be used as an aid in determining shielding requirements for a sample of RCS after an accident.
given: I=Ie* g E
where: p = p,p I/I =g EY mE*
In(I/I g) = -p,px l
In(I g/I) l (eq. 6.1.1) ** pp where: x = thickness of absorber (cm) p = linear attenuation coefficient (c51) 2 p" = mass attenuation coefficient (cm./g) @ the energy level (Mev) of the source p = density of the absorber material (g/cm3 )
\
Ig = source intensity w/zero thickness of the absorber (mR/hr or R/hr)
I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/Ig = 1/2 = eYo
- In(1/2) = -p,px (eq. 6.1.2) x _ 0.693 P,P A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations for conservatism:
(eq. 6.1.3) In(I g/I) + 0.693 x
total = p ,p O) t v
- CP/0/A/2005/02D Page 1 of 1
( ENCLOSURE 6.4 5, A and R Values for 1% Failed Fuel and DBA 1% Failed Fuel:
5% 0.34 MeV/ dis. AN 0.293 mci /ml R = 0.18 mR/hr-mci @ Im for 5
- 0.34 MeV -
100% Failed Fuel er Design Basis Accident (DBA) 5 s 1.14 MeV/ dis. A
- 1.324 x los pCi/ml -
R = 0.58 R/hr,-Ci @ im for 5 s 1.14 MeV A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.
i 9
L --- - -- -- -
~
, CP/0/A/2005/02D Page 1 of 1
. ENCLOSURE 6.5 CONVERSION FACTORS L
Source Activity - (A) 1 Curie (Ci)=3.7xiO 10 dis./sec. = 2.22 x 1012 dpm 1 mci = 3.7 x 10 7 dps = 2.22 x 10 9 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 10 dpm 8 R -
mR J
hr-Ci hr-mci Density - (p)
(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm3 Mass Attenuation Coefficient - (p,)
(p ) for elements and common materials at varying energy levels (MEV) for the source can be found on pg. 137 thru 139 of the
" Radiological Health Handbook."
Distance - (d) given: I g/I = d 2/d g2 where: I g= Source intensity (mR/hr or R/hr) @ distance (d )g I = Source intensity (mR/hr or R/hr) @ distance (d)
, 1 m. = 3.281 ft. = 39.37 in.
I ft.= 0.305 m 3 f t. = 0.914 m i
- l. :
i 1
, - . , .g,,., .,- ,e- ~ , + , - - - - , - - + - - - - = . - , - , - - - w-r- n-- -~-w' vsre~e,- w w~"*9Y '
- * ' ' Y*** 'M*
, , CP/0/A/2005/02D
. Page 1 of 1 INCLOSURE 6.6 MANUAL SAMPLE DILUTION 6.5.1 Place a magnetic stirrer in the shielded work area.
6.5.2 Partially fill a glass volumetric flask with demin water and place
, on the magnetic stirrer in the shielded work area.
6.5.3 Using tongs, remove the sample from the shielded sample container and place in the shielded work area.
6.5.4 Using a pipette, transfer enough sample to the volumetric flask to produce the desired dilution.
6.5.5 Fill the volumetric flask to'the mark with demin water, insert -
a stirring bar and cap.
- 6.5.6 Using tongs, place the sample back into the shielded sample container.
6.5.7 Stir the diluted sample for s 5 min. and allow to remain in the shielded work area until ready for analysis as disposal.
I 6.5.8 Repeat 6.5.1 thru 6.5.7 for additional samples.
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i DUKE POWER Lunrmu . ID No: un/n/n/1nn9/13 PROCEDURE PREPARATION Change (s) 7 to i PROCESS RECORD N/A Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Procedure for Imolementation and Verification for the Availability of a Back-Up Source of Meteorological Data (4) PREPARED BY: h m ,(Ob DATE: S QQ Q -
nf ,e (i (5',
REVIEWED BY: / 'N,u he !I,ns c c __ DATE: '/ ,1 2 - f Z.
/ ei Cross-Disciplinary Rev ew By: N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: .
(SRO) Date:
% By* Date:
(7) APPROVED BY- l he Date: 4 '23\31 (8) MISCELLANEOUS:
t/m Date: [
Reviewed / Approved By C , ,3/f'>
f
. y:- c Reviewed / Approved By: / Date:
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HP/0/B/1009/13
_, Page 1 of 3 DUKE POWER COMPANY O) t LJ OCONEE NUCLEAR STATION PROCEDURE FOR IMPLEMENTATION AND VERIFICATION FOR THE AVAILABILITY OF A BACK-UP SOURCE OF METEORO-LOGICAL DATA 1.0 Purpose To provide a procedure for implementation and verification for the availability of a back-up source of meteorological data needed to make an offsite dose projection should the station's meteorological data equipment become unavailable.
2.0 References ,
2.1 NUREG 1.23, Proposed Revision 1* to Regulatory Guide 1.23, Meteoro-logical Programs in Support of Nuclear Power Plants.
2.2 NUREG 0654, Annex 1 to Appendix 2, (o), Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
b 2.3 Oconee Nuclear Station Emergency Plan.
G 3.0 Limitations and Precautions 3.1 Maintain record of notification (Enclosure 5.1) for a minimum of two years. This procedure will be superseded as acceptable backup measures are developed by Oconee Nuclear Station.
3.2 Contact the National Weather Service at the Greenville-Spartanburg Airport by telephene using Enclosure 5.1. The telephone number listed on the Enclosure is a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> number.
3.3 These contacts shall be made monthly and alternate among shifts.
4.0 Procedure 4.1 Record the following meteorological information on Enclosure 5.1.
4.1.1 Wind direction (in tens of degrees).
4.1.2 Wind speed (in knots).
4.1.3 Air temperature.
4.1.4 Weather conditions (clear, partly cloudy, etc.)
v
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4.2 Record concurrent on-site meteorological information on En-closure 5.1.
L
HP/0/B/1009/13 Page 2 of 3 5.0 Enclosure 5.1 Communications Check, Meteorological Data.
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DUKE POWER COMPANY (1) ID No: HP/0/B/1009/15 PROCEDURE PREPARATION Change (s) 4 to PROCESS RECORD N/A Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Procedure for Sampling and Quantifying High Level Gaseous, i- Rad ic iod ine , and Particulate Radioactivity -
(4) PREPARED BY: [. h. u., . /1 DATE: 4- 24f y 2.
(5) REVIEVED BY: J_ h mew DATE: V - Ef -f L Cross-Disciplinary Review By:
i /
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(6) TEMFORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
By: Date:
(7) APPROVED BY: Yf 4%,/c-## Date: 4./29/#2 (8) MISCELLANEOUS:
Reviewed / Approved By: Date:
Reviewed / Approved By: Date:
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' HP/0/B/1009/15
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DUKE POWER COMPANY OCONEE NUCLEAR STATION PROCEDURE FOR SAMPLING AND QUANTIFYING HIGH LEVEL GASEOUS, RADI0 IODINE, AND PARTICULATE RADIOACTIVITY 1.0 Purpose i
This procedure describes methoos for collecting samples to evaluate effluent and containment noble gas and radiciodine activities during accident conditions.
2.0 References 2.1 System Health Physics Manual,Section I, M, Radioactive Waste Control Requirements 2.2 Technical Specifications Oconee Nuclear Station, Appendix A.
Section 3.10 Release of Gaseous Radioactive Waste s ,j/ 2.3 HP/0/B/1000/60/A, Procedure for Gaseous Waste Sampling and Analysis 2.4 HP/0/B/1000/60/D, Procedure for Unit Vent Sampling and Analysis 2.5 HP/0/B/1000/57, Air Sampling, Counting and Calculating Procedure 2.6 HP/0/B/1000/60/B, Procedure for Reactor Building Gaseous Purge 2.7 HP/0/B/1000/60/H, Procedure for Changeout and Analysis of Reactor Building Iodine Cartridges and Particulate Filters 2.8 HP/0/B/1000/55, Instrument Monitoring and Survey Procedure 2.9 HP/0/B/1001/14, Procedure for Nuclear Data 6600 System Operation 2.10'HP/0/B/1006/07, Procedure for Preparation of Gas Calibration Sources 3.0 Limits and Precautions 3.1 This procedure is written for use under abnormal conditions which could involve extremely high radiation levels. Only Health Physics management should authorize the use of this procedure when needed and should provide appropriate surveillance and control of people
. /Ng taking the samples.
l
'l 3.2 Whenever the effluent monitor goes offscale, appropriate grab samples l or radiation level measurements should be taken to estimate effluent j release rates and the amount of effluent released.
l.
L -- _
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NOTE: No samples will be taken unless authorized by Health 4 Physics management. When samples are taken, use pro- ,
tective clothing, gloves, respiratory protective equip-
~
ment, portable shielding, high rahge dos'imeters and survey instruments as determined by prejob ALARA planning.
3.3 Should effluent concentrations exceed those values specified in Enclosure 5.5, notify the emergency coordinator of possible tech-
. nical specification violation.
~~
4.0 Procedure .-
1 4.1 Conduct planning session. Consider the guidance provided in Enclo-sure 5.1 in preplanning.
4.2 Use an ion chamber to measure the radiation dose rate from the reactor building or unit vent RIA' supply line.
4.3 When contact dose rate readings at Iodine RIA sample holder (RIA-44 for Vent /RIA-48 for Reactor Building' and middle point of Gaseous 1
RIA supply line (RIA 45/46 for Vent /RIA 49 for Reactor Building) are less than 3 R/hr, collect gas and Iodine samples as described in Steps 4.4.1 to 4.4.6.
l 4.4 Sample Collection
, 4.4.1 Prepare a flow path in the following order:
4
! NOTE: During an accident, the containment building is l isolated. Contact Shift Supervisor for manual
. override to open valves for sampling.
I '
! Supply + particulate filter paper + CP-100G silver zeolite i sample cartridge + vacuum pump + flow meter (0-80 LPM) +
100 ml Argonne gas bomb + return line.
- See 2nclosure 5.2 for apparatus setup. -
i j 4.4.2 Collect sample. Minimum sample volume is 5 liters.
} 4.4.3 Upon completion, turn off sample pump, close exhaust valve of gas . bomb, close intake valve of gas bomb, close supply valve, then close return valve.
{
4.4.4 Remove filter and cartridge; monitor sample and place in.
{ protective wrapper (poly bag). Indentify with 4.4.4.1- Start time i
4.4.4.2- Stop time 4
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- 4.4.4.3 Flow rate
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4.4.4.4 Sample location ,
4.4.5 Place samples in shielding container for return to the counting laboratory.
4.4.6 If contact reading on sample is greater than .01 R/hr, Count Room personnel will make decision on counting sample.
4.5 If the dose rate at the gaseous RIA (RIA 45/46 for Vent /RIA 49 for Reactor Building) supply line is greater than 3R/hr, obtain gaseous concentration (pCi/ml) corresponding to the radiation dose rate (R/hr) from Enclosure 5.3.
4.6 If the dose rate at the Iodine RIA (RIA 44 for Vent /RIA 48 for Reactor Building) sample holder is between 3 R/hr and 15 R/hr, follow Step 4.6.1 to 4.6.5. If the dose rate exceeds 15 R/hr, no samples will be taken.
NOTE: Contact Shift Supervisor for manual override.
4.6.1 Remove chcrcoal cartridge from the Iodine RIA sample holder. 3urvey removed charcoal cartridge and save to be counted if possible.
('~'N 4.6.2 Collect sample through silver zeolite cartridge for two (2)
( _, )
minutes. Collect data from RIA flow meter for correct volume.
4.6.3 Remove cartridge" from sample holder, monitor sample'and place cartridge in poly bag and put bag into a shielded container for transport to a lower background area for counting. Place new cartridge in sample holder for future use if desirable.
4.6.4 Take a contact dose rate measurement on the sample cartridge using an ion chamber. Obtain Iodine concentration (pCi/ml) corresponding to the radiation dose rate (R/hr) from Enclosure 5.4,
'4.6.5 If the contact reading is below .01 R/hr, perform a gamma isotopic analysis of the sample.
4.7 Isotopic Analysis of Sample 4.7.1 Iodine + Particulate - Separate filter and cartridge and seal in wrappers. Label cartridge with data. Analyze particulate and iodine cartridge by Reference 2.9.
b
\
i.
4.7.2 Gaseous - Gas bomb is labeled for desired data and processed for gamma spectroscopy.
4 4.7.2.1 Test gas bomb for exces'sive d'ead time by Reference 2.9.
4.7.2.1.1 If the dead time is greater than 15%
at the 9cm geometry for gas bombs, dilute the gas sample by Ref. 220.
l Further dilutions may be necessary until the desired dead time value
< 15% is achieved.
l 4.7.3 Review spectral display versus printout to assure correct gamma isotopic analysis report. i l
4.8 Results 4.8.1 Forward MCA results to TSC for review and further distri-buiton.
NOTE: For rapid assessment of technical specifications compliance, use Enclosure 5.5.
5.0 Enclosures
( 5.1 Guidelines for Collecting, Transporting, Analyzing, and Disposing of High Level Samples
(
5.2 Apparatus setup for sample collection.
5.3 Conversion of gaseous RIA supply line dose rate (R/hr) to gaseous effluent concentration (uC1/ml) 5.4 Conversion of Iodine sample cose rate (R/hr) to Iodine effluent concentration (pCi/ml) 5.5 Conversion of Vent Sample Results to Curies per second o ,
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ENCLOSURE 5.1 O)
(
~J GUIDELINES FOR COLLECTING, TRANSPORTIN,G, ANALYZING, r
ADD DISPOSING OF HIGH LEVEL SAMPLES
- 1. Before entering sampling points, be aware and prepare for high radiation levels and possible airborne areas.
- 2. Preplan and stage sampling apparatus in a low background area.
- 3. Take samples expeditiously.
- 4. Handle samples with either the source handling tools available in the H.P.
Source Room or with tongs from station supply area.
- 5. Transport hot samples to counting lab with good ALARA practices.
Examples: A. sample sitting on a cart or hand truck ----- distance.
B. Sample surrounded by a lead blanket or lead bricks (all of which are availabe in the H.P. Lab areas or supply) --- shielding.
- 6. Contamination control should be maintained by double bagging the sample
['"' during transport and analysis.
\ Disposal or storage of the high level samples in the Counting Facility 7.
should merit the same controls, as sampling,. i.e. , ALARA transportation, shielded storage,or storage at a remote location.
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ENCLOSURE 5.2 HP/0/B/1009/15 , ,
SAMPLE COLLECTION Flow Filter Meter 4
Flcw Gas Supply ? i Cart. O Pump O O Return Collector A) Set up sample system according to diagram.
B) Before opening supply and return valves ENSURE
- 1) Tight hose fittings.
- 2) Correct valve positions.
- 3) Open flow rate meter (a couple of full turns).
- 4) Regulate flow rate with supply valve (when possible).
C) Turn on sample pump.
D) Shut system down if pressure or vacuum meters build up.
E) Check gas collector for build up of back pressure.
F) Sample time is an important consideration in the validity of the sample results.
. G) Upon completion of sample:
f a) Turn off sample pump.
b) Close exhaust valve of gas bomb.
c) Close intake valve of gas bomb.
I Close supply valve.
d)
- e) Close return valve. ,
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]f(' p I! dose rate (R/hr) into l I l i jl[ ft V [i
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,__, l ii k concentration (uCi/ml). I
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- rneasured dose rate (R/ hour) into concen-
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= - = - . -
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ENCLOSURE 5.5 CONVERSION OF VENT SAMPLE'RESULTS TO VENT ACTIVITY RELEASE RATE O
- 1) Determine vent activity release rate in Ci/see for iodine, in Ci/see tor noble gases, and in Ci/see for particulates by the following equation:
Ci/sec = V7 x Conc. x 4.72 x 10 where, VF = Vent fl w rate in CFM Cone. = sample concentration results in Ci/m NOTE: 1 pCi/ml = 1 Ci/m 4.72 x 10 = conversion of ft /3min to meters /sec 3 ft 0.02832m3 1 min min ft3 60 sec NOTE: Should any other gaseous waste releases be in process, calculate Ci/sec values as above and sum station total Ci/sec of iodine, noble gases, and particulates.
- 2) Average the calculated vent activity release rates over the period of a O calendar quarter to determine Ci/sec/qtr for iodine, Ci/sec/qtr for noble gases, and Ci/sec/qtr for particulates by the following equation:
Ci/sec/qtr = Ci/sec x duration of release in seconds-7.88 x 100 where, C1/sec = vent activity release rates calculated in 1). 7.88 x 106 = seconds in a calendar quarter
- 3) Compare results to the following values:
When rate of gaseous waste release in Ci/see when averaged over a calendar quarter exceeds: a) iodine - 2.4 x 10- Ci/sec/qtr noble gas - 3.2 x 10-3 Ci/sec/qtr particulates - 7.0 x 10-8 Ci/sec/qtr (Co=pliance with Tech. Spec. 3.10.1 required.) b) ' iodine - 9. 6 x 10-8 Ci/sec/qtr k/ noble gas - 1.28 x 10-2 Ci/sec/qtr particulates - 2.8 x 10-7 Ci/sec/qtr (Compliance with Tech. Spec. 3.10.2 required.) E _
. - - . . - . - - . . . . . . . - . . . . . - -. -. . . = = . .- . - . . . . . _ . ._ . _ ~ .
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i t t i- ! l c) iodine - 1.2 x 10-6 Ci/sec/qtr , j particulates - 3.5 x 10-6 C1/sec/qtr i. I j (Compliance with Tech. Spec. 3.10.2 required) d) noble gas - 8.0 x 10-2 Ci/sec/qtr ] l (Compliance with Tech. Spec. 3.10.2 required) { 4) Should any of the above values be exceeded, notify the emergency coordinator l of condition. .1 . i
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l l l l l Form SPD-1002-1 l DUKE POWER COMPANY (1) ID No: IP /0/B/1601/3 PFOCEDURE PREPARATION Change (s) o to PROCESS RECORD ._/ Incorporated (2) STATION: Oconee < i (3) PROCEDURE TITLE: Environmental Equipment Checks (4) PREPARED BY: a#, DATE: NM-8h ., (5) REVIEWED BY: ATE: [M , Cross-Disciplinary Review By: N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: b Date: /-["[2 (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: _, - r 4;rr ' ','7.
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DUKE POWER COMPANY / OCONEE NUCLEAR STATION ENVIRONMENTAL EQUIPMENT CHECKS j / i- 1.0 Purpose , y . . . .
. 1.1 To furnish a procedure for documentationl of weekly data collection - ,6 and equipment functional c'ecks. h f
2.0 References ,,
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2.1 Duke Dwg. 0-714-D, 0-829, 0-829-A : ,s i ,- 3.0 Test Equipment Required , / f, b
- t p-3.1 Portable psychrometer 7
, 4.0 Prerequisites.(Sign-offs on Enclosure 11.1) ,
f r p g 4.1 This procedure should not be performed during a gaseous waste release period. .l;
- c. ,
4.2 Supervisor has reviewed and initialed all portions of.this ' pro- j cedure which are not applicable to'the activity being p'erformed. <'.', , The Supervisor's review is not required-if the p/rocedure Q'ecifies' sections to be omitted. f
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4 4.3 Verify that all changes in the Control Co6y are incorpofated in
, the Working Copy.
).
S.0 Limits and Precautions .- - i 5 .1 ' Use proper precautions while working with ' components that h' ave high
, voltage or high pressure present.
6.0 Unit Status '/ i .
- N/A -'
7.0 General Description ( The environmental equipment monitors the following parameters and ' records" ' tha information on individual chart recorders; wind speed, wind ,directior.( _ air' temperature, humidity, and amount of rainfall. ,, u , -/~ J > j There are two meteorological monitoring stations for.the wind spees and. ,9 direction. Site #1 is located at the micro-wave tower and Site tf2.is
-1 located adjacent to the river below Keowee discharge.
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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 U 8.4 Two Teledyne Geotech Series 40 OM-333-275 Wind Direction Modules 8.5 Two Teledyne Geotech Series 40 OM-333-276 AC Power Supplies 8.6 One Leeds and Northrup 3-Lead
- Resistance Temperature Detector (RTD)
Air Temperature System 3.7 One Belfort Instrument Company Hygro-thermograph Recorder s S.8 One Belfort Instrument Company weighing Rain Gauge Recorder 9.0 Equipment Specifications l Wind Speed 0-30 mph .04 mph 7 (60 and 90 mph selectable ranges) Wind Direction 0-540 degrees t 5.7 l~ Ambient Air Temperature -15 to 105 F t 0.7 F q Temperature Differential -30 to 30 F t 0.9 F i f'7 Rainfall Gauge 0-12 in. t .03 in. (0-6 in.) jf- t .06 in. (6-12 in.)
' 'r "
z , 10.0 Procedure Instructions (Sign-offs on Enclosure 11.1) a 6' '
', , .n NOTE: Use Control Room computer clock for all time recordings.
7" f!, Mark on charts all as found calibration points (R Found, 7
;r > '
T., Found and F.S. Found) before adjustments are made. If j;, aajustments are made, mark all as left calibration points l
.A
{N , (Rg Left, T Left and F.S. Left) on charts.
, _ Perform as found string checks using the following procedure
}y/:)/[' j ; ' and complete Enclosure 11.3.a and b. a- p. ,, , _ . ,k *o f'
- j. r >^
l
t 3-10.1 ONS Site 1 !
- 1. Check recorder zero on wind speed and direction recorders by turning translator power off. Rotate charts slowly and i individually for good trace. Verify positions on recorders
, and note time and date. Mark '"R, Found" on each chart beside the trace.
- 2. ~ Return power on translator and check wind speed and direction i 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 module in the Hi Cal. position. Rotate
- chart slowly and verify position on recorder. Mark "F.S. Found" t on each chart beside the trace.
l 4. Place wind speed and direction' modules in operate position. i Verify normal response on recorders. Insure ink wells are full. 4
- 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.
b positions on the wind speed and direction recorders. Rotate charts slowly and individually for good trace. Label chart l "T, Found".
- . 2. Place Control Room switch in the Hi position. Verify Hi l Cal. positions on the wind speed and direction recorders.
i Rotate charts slowly and individually for good trace. Label "F.S. Found".
- 3. Check recorder zero on wind speed and direction recorders by j disconnecting field inputs in back of recorders and installing a jumper wire across the terminals. Label chart "R Found".
Document time and date on charts. Rotate charts in51vidually and slowly for good trace. Verify position on recorders.
- 4. Remove jumpers.and reconnect field inputs to recorders.
F
- 5. Place Control Room switch to the operate position. Verify
, normal response on recorders. Insure ink wells are full.
- 6. Change charts on recorders. Document starting time and date on charts.
-If-all string checks are within tolerance, remove and staple together.
the front approval sheet, list of enclosures, and sign off sheet. Insure all equipment mentioned above is returned to service and _/ continue. If all string checks are not within-tolerance, continue with~Section 10.6. I b
p 10.3 Air Temperature Recorder
- 1. Turn off chart recorder. Document time and date on chart.
- 2. Remove weeks run of chart paper. Replace chart paper as nec-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 be something wrong with the air temperature system, please note this on the chart from Step 2. 10.4 Hygro-Thermograph Recorder
- 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.
- 4. Prepare recorder for another week of operation by rewinding clock mechanism, inking the pens, and aligning chart for v ) correct time. Document the temperature and humidity readings from Step 1 on chart.
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
- 1. Open the sliding door and lift the pen from the chart by pulling the pen arm shifter away from the mechanism support column.
- 2. Next remove the collector and empty the bucket slowly from the platform so that the gauge mechanism will not be subject to any sudden shock as the pen returns to the zero reading.
- 3. Peplace the collector.
- 4. Lift the chart cylinder and remove old chart noting time and date on chart.
- 5. Change the chart on the rain guage recorder. Document start time and date on chart.
G 6. Prepare recorder for another week of operation by rewinding clock (v) mechanism, inking the pen, and aligring chart for correct time.
- 7. Verify pen on zero point. If not, adjust the zero knob until zero is obtained.
5-Ink' the pen, set the chart to correct time. Press the pen O 8. arm shifter all the way in and verify pen is making contact with chart.
- 9. Close sliding door.
10.6 Calibration Procedures A. Wind System
- 1. To adjust recorder zero, ensure power supply on trans-lator is off. The zero adjustment arm is located on I
the inside bottom of recorder under the chart take-up reel. Make adjustments until recorder reads zero. Mark "R Left" on chart beside the trace after the final
'ad}ustment.
- 2. To adjust the translator full scale, turn the power supply 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.
- 3. To adjust the translator zero, turn the mode switch to the Lo Cal position.' On the wind direction module adjust the Lo Cal adjtisting screw on the front of the module to ob-O tain a zero reading. Mark "T Left" on chart beside the trace after the final adjustmInt.
N01'E: The translator zero for the wind speed module should be performed in a lab since the adjust-ments necessary must be made internal of the translator and requires a considerable amount of time and accuracy. If translator zero for wind speed exceeds tolerances contact the E.S.S. (Environmental Services Section). B. Hygro-Thermograph Recorder
- 1. If the temperature indication is found to be incorrect an adjustment may be made by turning the thumb screw 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 g to read 92* by adjusting the thumbscrew in tne base of the instrument located beside the temperature setting L* . L.
l i . 6-screw. Do not set the pen to read 100% humidity. No ! amount of artificial wetting seems to wet the hair to i 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 i correct error per psychrometer reading. 10.7 As Left String Checks (Enclosure 11.5a and b) 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. 11.0 Enclosures i l 11.1 Sign-Off Sheet 11.2 Reference Data (None) 11.3 As Found String Checks ) . 11.3.a ONS Site 1 l 1 11.3.b ONS Site 2 t
, 11.4 Calibration Data Sheets (None) l 11.5 As left String Checks 11.5.a ONS Site -1 11.5. b ONS Site 2 -
s 1 1 4 4 0
_.. - ~- - . -___ _ . .. i ENCLOSURE 11.1 IP/ 0/B/1601/03 SIGN-OFF SHEET Prerequisites Date Begun 4.1 Date Completed 4.2 W.R.# 4.3 Unit # Double Verification of Wires Removed and Connected
, __10.2.1 Wires removed and jumpers installed on input to recorder.
, 10.2.2 Jumpers removed and wires replaced string checks.
11.3.a 11.5.a 11.3.b 11.5.b' Performed By Notified Instrument Supervisor that a tolerance of 2% ('iech) was exceeded on the following components: Init. and Date An evaluation was made on the above problem (s) and the Inst. Supvr. following corrective action taken: Init, and Date Remarks: W
\-_,)
I
. - . .- - - . _ . . . - . . _ . . - - . . - _ . . _ _ . - ._- . - . - - _ - . . - . .-. =_
i' . i. f .i i I i ENCLOSURE 11.3.a IP/0/B/1601/03- ! i AS FOUND INT 2 GRATED STRING l VERIFICATION DATA SHEET Item Wind, Speed & Direction Test Equipment Used [ i j Mfg Teledyne Geotech Item SN [ \ t 1- Type Series 40 , !- Calibration Tolerance W/S 0.4 mph; W/D t 5.0 ! System Environmental
- 1 l Span W/S 0-30 mph; W/D 0-540*
{ Location Upper Meteorlogical Site (ONS Site 1) 4 Input Required' AS Required AS i ' Reading Found Reading _ Found - W/S W/S W/D W/D I I I Rz 0 0 - Lo Cal 0.6 i .1 mph 0-Hi Cal N/A N/A Full Scale . l ; i j Equipment Removed From Service , 4
- Equipment Returned To Service ,
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g ENCLOSURE 11.3.b IP/0/B/1601/03 l AS FOUND INTEGRATED STRING 1 VERIFICATION DATA SKEET j Item Wind, Speed & Direction Test Equipment Used i Mfg Teledyne Geotech Item SN ! Type Series 40 - i i Calibration Tolerance W/S 0.4 mph; W/D t 5.0
. System Environmental __
Span. W/S 0-30 mph; W/D 0-540 i Location Lower Meteorlogical Site (ONS Site 2) 1 - Input Required' AS Required AS g' Reading Found. Reading Found j W/S 1 W/S W/D W/D Rz O O i } Lo Cal 0.6 t .1 mph 0 t i Hi Cal' N/A N/A Full Scale ] a
- Equipment Removed From Service ,
Equipment Returned To Service , I 1 i' I s l i t e
ENCLOSURE 11.5.b () IP/0/B/1601/03 AS LEFT INTEGRATED STRING VERIFICATION DATA SHEET Item Wind, Speed & Direction Test Equipment Used Mfg Teledyne Geotech Item SN Type Series 40 Calibration Tolerance 'W/S 0.4 mph; W/D t 5.0 System Environmental l Span W/S 0-30 mph; W/D 0-540 l Location Lower Meteorlogical Site (ONS Site 2) 1 Input Required' AS Required AS Reading Found Reading Found O Rz W/S 0 W/S W/D 0 W/D r Lo Cal 0.6 .1 mph 0 Hi Cal N/A N/A Full Scale i ! Equipment Removed From Service , i Equipment Returned To Service , 4 - 4 . k
l ENCL'0SURE 11.5.a IP/0/B/1601/03 AS LEFT INTEGRATED STRING VERIFICATION DATA SHEET Item Wind, Speed & Direction Test Equipment Used Mfg Teledyne Geotech Item SN Type Series 40 Calibration Tolerance W/S 0.4 mph; W/D t 5.0 System Environmental Span W/S 0-30 mph; W/D 0-540 Location Upper Meteorlogical Site (ONS Site 1) Input Required' AS Required AS O Rz Reading W/S 0 Found W/S Reading W/D 0 Found W/D Lo Cal 0.6 t .1 mph 0 Hi Cal N/A N/A Full Scale Equipment Removed From Service , Equipment Returned To Service , I I l O r 1}}