ML20206M586
| ML20206M586 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/23/1987 |
| From: | Bolel M, Susan Cooper, Simpson D DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20206M566 | List: |
| References | |
| PROC-870323-01, NUDOCS 8704200140 | |
| Download: ML20206M586 (47) | |
Text
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} erm,34731* s<tR946) *
(1) ID No. RP / 0 / M / g n o 0/13 OUKE TOWErl COMPANY I'
PROCEDURE PROCESS RECORD *"9'2 '
Incorocratea r'; w #CEPAR ATION -
- Re e
'2' STATION ATAWMA NUEEEAR STA* TON 131 PROCEDURE TITLE NRc N0**FTCATION RECCIEEMENTS (4) PREPARED BY Diane P. Si:'tOSon DATE March 9, 1987 (5) REVIEWED BY W DATE 3 7 Cross Disc:otinary Review By I- I ~ I" NR
/ /
(6) TEMPORARY APPROVAL (If Necessaryl By (SRO) DATE By DATE (7) APPROVED BY DATE 3 3 N (8) MISCELLANEOUS Ieviewed/Accroved By DATE Reviewed /Acoroved By DATE
-- '(9) COMMENTS (For procedure reissue indicate whetner aeditional changes, other than oreviously aporoved en s. are inctuced.
Attacn addit;ona; pages.if necessary ) ADDITION AL CHANGES INCLUDED. es ZNo (10) COMPARED WITH CONTROL COPY DATE COMPLET(ON (11) DATE(S) PER FORM ED (12) PROCEDURE COMPLETION VERIFICATION 2 Yes Z N/A Check lists anc/or blanks properly .nitialec, s.gnec, catec or fil;ec a N A or N h. as accropr: ate)
Yes Z N/A Listed enclosures attached)
Z Yes Z N/A Data sheets attached, como'e:ec catec and s-gnec)
Z Yes ! N/A Charts, graons etc. attacnec aac crocerly catec. cent >f ed and markec)
Z Yes Z N/A Acceotance criterra met)
VERIPIED BY DATE (13) PfiOCECURE COMPLETION APPROVEC DATE t) REMARKS (Attaen accit:enai pages if ae:essary i
'J 8704200140 870323 PDR F ADOCK 05000413 PDR .
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. s DUKE POWER COMPANY CATAWB A NUCLEAR STATION NRC NOTIFICATION REQUIREMENTS l 1.0 SYMPTOMS l 1.1 Plant conditions requiring NRC notification in accordance with:
10 CFR50.72,10 CFR20.205,10 CFR20.403, and 10 CFR73.71. 1 1.1.1 Immediate,1 Hour and 4 Hour Notifications. !
u 1.1.2 24 Hour Notifications for Operating License Condition Deviations. pl t
a 1.2 See Enclosure 4.1 for determination of appropriate notification i requirement.
2.0 IMMEDI ATE ACTIONS !
, 2.1 Complete one of the following enclosures:
2.1.1 Enclosure 4.2 " Checklist for Significant Event Notification" or p
2.1.2 ks.osure 4.3 " Report of Serious Physical Se.curity Events" When reporting from Section 4.1.2.7 of Enclosure 4.1 2.2 Notify the NRC Operations Center by the following means: !
2.2.1 Pri. - Emergency Notification System Phone 2.2.2 Alt <
2.3 Notify the NRC Region 11 Office a f any event listed in Section 4.1.1.5 of Enclosure 4.1.
NOTE: No Enclosure for reporting to Region 11 l
f rom Section 4.1.1.5 of Enclosure 4.1 3.0 SUBSEQUENT ACTIONS 3.1 Provide follow-up notification as described below:
3.1.1 Emergency Classer 3.1.1.1 Any further degradition in level of safety of l the plant including those that require
' declaration of any Emergency Class, if such a declaration has not been previously made.
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Page 2 of 3
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3.1.1.2 Any change in the Emergency Class l 3.1.1.3 Termination of the Emergency l
, 3.1.2 Results of ensuing evaluations or assessments of plant I:
- conditions 3.1.3 Effectiveness of response or protective measures taken 3.1.4 Information related to plant behavior that is not understood 3.2 Maintain an "Open", continuous, communications channel with the NRC I Operations Center, upon request by the NRC.
I 3.3 Notify the following individuals: l' 1
3.3.1 Compliance Engineer Prima ry Alternate .
Duty Compliance -
C. L. I Engineer Office:
(See current Station Home:
Duty List) -
I
,, 3.3.2 If neither the Compliance Engineer nor the Duty Compliance h Engineer can be reached then call directly to the:
..] ,
NRC Resident inspector l' Primary - Unit 1 Primary - Unit 2 Alternate - Unit 2 Alternate - Unit 1 e e Alternate - For Either Unit h M.S. esser h
Offic l Home: . I 3.3.3 Nuclear Production Duty Engineer 3.4 Upon completion of this procedure, fill out the Completion i Section of the Procedure Process Recorc' Form and forward to the Compliance Engineer for review prior to submission to '
Master File. l J
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U l RP/0/8/5000/13 Paga 3 cf 3
[D
'- >' 4.0 ENCLOSURES -
4.1 Events Requiring NRC Notification )
4.2 Checklist for Serious Event Notification 4.3 Report of Serious Physical Security Events 4.4 List of Engineered Safeguard Features (ESF) Actuations i
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RP/0/8/5000/13 Events Rsiquiring NRC Notification Enclosure 4.1 o'f 6 Page
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U 4.1.1 Events Requiring "lMMEDI ATE NOTIFICATIONS". -
Immediately after notification to states and counties and not later than one hour after the time the Emergency Class was declared.
4.1.1.1 The declaration of any of the Emergency Classes specified in the Catawba Emergency Plan 4.1.1.2 Any change from one Emergency Class to another 4.1.1.3 Termination of the Emergency 4.1.1.4 For any incident involving byproduct, source or special nuclear material which may have caused or threatens to cause the following:
4.1.1.4.1 Individual Exposure 125 Rem Whole Body or '
3150 Rem Skin of Whole Body or M
3 375 Rem Extremities 4.1.1.4.2 Release of radioactive material in concentration which if averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period 'would exceed 5,000 times the applicable concentration of the limits specified in 10 CFR 20, Appendix B, Table ll.
4.1.1.4.3 Loss of one working week or more of the operation of any unit.
4.1.1.4.4 Damage to property in excess of $200,000.
4.1.1.5 Notification to NRC Reginal Office, Region 11, Atlanta, GA. (see Step 2.3). Receipt of a package of radioactive materials with:
4.1.1.5.1 >0.01 uCi/100cm' loose radioactive inatorial on the external surface or i .
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RP/0/B/5000/13
- - Evsnts Recuiring NRC Notification Enclosur s 4.1 Paga 2_ of 6 -
- 4.1.1.5.2 >200 MR/hr. on external surface l1. 1 d or -
4.1.1. 5.3 >10 MR/hr. at three (3) feet from the external surface 4.1.2 Events Requiring "ONE HOUR REPORTS":
As soon as practical and within one hour of the occurrence.
4.1.2.1 The initiation of any nuclear plant shutdown required by Technical Specifications (i.e.
Safety Limit Violation). See notes:
NOTE: 1. The initiation of a Shutdown is defined as, "A reduction in Power, required by an action statement of Tech. Specs.,
to Mode 3."
- 2. A Shutdown is defined (for reporting requirements) as, " Mode 3 and below".
t 4.1.2.2 Any deviation from a plant License Condition or Technical Specification authorized in 10C FR50.54( x ) .
f- (Licensee may take reasonable action that u./ departs' from a license condition or a technical specification in an emergency when this action is immediately needed to protect the health and safety of the public and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent.)
4.1.2.3 Any event or condition during operation that results in the condition of the plant, including the principle safety barriers, being seriously degraded, or results in the plant being:
4.1.2.3.1 In an unanalyzed condition that significantly compromises plant safety.
4.1.2.3.2 in a condition that is outside the !
design basis of the plant. '
4.1.2.3.3 in a condition not covered by the plant's operating and emergency p roced u res.
4.1.2.4 Any event that results or should have resulted in Emergency Core Cooling System (ECCS)
. discharge into the reactor coolant system as a
- result of a valid signal, a
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RP/0/8/5000/13 Evcnts Recuiring NRC Notification
' * ' Enciesuro 4.1.
Pags 3 of. 6 4.1.2.5 Any event that results in a major lo.ss of
~% -
emergency assessment capability, offsite response
.-) capability, or communications capability (e.g. , .
significant portion of control room indication, Emergency Notification System or Offsite Notification System).
Note: A loss of 25% of the Prompt Alerting Siren System for Catawba Nuclear Station is reportable when 19 or more sirens are reported inoperable for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.2.6 Any natural phenomenon or other external condition or any event that poses an actual threat to the safety of the plant or significantly hampers site personnel in the performance of duties necessary for the safe operation 'of the plant, including fires, toxic gas releases or radioactive releases.
4.1.2.7 Safeguard events as determined by Security personnel and Station Management.
i 4.1.2.7.1 A trace investigation of a lost or unaccounted for shipment pursuant to 10 4
CFR 73.27.
[,
4.1.2.7.2 An attempt (actual or suspected) to commit a theft or unlawful diversion of Special Nuclear Material.
4.1.2.7.3 Any event which significantly threatens or lessens the' effectiveness of the physical security system:
NOTE: Reports of Safeguards Events should be made by Catawba 1
Sec'urity Procedure = 106,
" Reporting of Safeguards
- Events".
Security Supervision will ,
provide all information to l the Operation's Shift Supervisor for NRC notification.
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RP/0/B/5000/13 . _
Ev :nts Rr. quiring NRC Notification Encissura 4.1' Pago 4 cf 6 4 .1.~3 Events Requiring "FOUR HOUR REPORTS"
.;/ As soon as practical and within four hours of the , j occurrence. '
4.1.3.1 Any event found while the reactor (s) is/are shutdown, that had it been found while the reactor (s) was/were in operation would have resulted in the plant, including its principle safety barriers, being seriously degraded j
or being in an unanalyzed condition that signifi-cantly compromises plant safety.
4.1.3.2 Any event or condition that results in manual or automatic activation of any Engineered Safety Feature (ESF), see Enclosure 4.4, including the Reactor Protection System (RPS). (However, activation of an ESF including the RPS, i
that results from and is part of the .
preplanned sequence during testing or
] reactor operation need not be reported).
4.1.3.3 Any event or condition that alone could 3 have prevented the fulfillment of the safety function of structures or systems that are needed to:
t.9) 4.1.3.3.1 Shutdown the reactor and
'V2 maintain it in a safe shutdown condition.
4.1.3.3.2 Remove residual heat. '
4.1.3.3.3 Control the release of radioactive material.
4.1.3.3.4 Mitigate the consequences of an accident.
'N 4.1.3.4 Any airborne radioactive release that exceeds 2 times the applicable concentrations of the limits specified in 10CFR20, Appendix B, Table ll in unrestricted areas when averaged over a time period of one hour.
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, RP/0/B/5000/13 Events Rccuiring NRC Notification Enclcsura 41 Page 5 of 6 ,
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4.1.3.5 Any liquid effluent release that exceeds 2
- times the limiting combined MPC (See ;
10CFR20, Appendix B, Note 1. ) at the 1 point of entry into the receiving water (unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. (Immediate Notifications made under this requirement also satisfy the require-ments of 10CFR20.403, Paragraph (a)(2) and (b)(2)). (See 4.1.1.4.2) .
4.1.3.6 Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.
4.1.3.7 Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, ft - which a News Release is planned or Notification to Other Government Agencies has been or will be made. Such an event r'3 may include an o~nsite fatality or
(_/ inadventent release of radioactively ,
contaminated materials.
4.1.3.8 Steam Generator Tube Plugging in accordance with Tech Spec 3.4.5, Table 4.4-2.
4.1.4 Events Requiring "24 Hour Reports" 4.1.4.1 Operating License Conditions Deviations Requiring "24 Hr. Notifications":
4.1.4.1.1 Refer to Operating License 4.1.4.2 Security Events:
NOTE: Reports of Safeguards Events should be made by Catawba Security Procedure
= 106, " Reporting of Safeguards Events".
Security Supervision will provide all information to the Operation's Shift Supervisor for NRC notification.
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, RP/0/8/5000/13
- - Events Requiring NRC Notification Enclosure 4.1 Page _6 o.f 6
- g 4.1.5 Follow-up Notifications j 4.1.5.1 During the course of the event, report
- l 4.1.5.1.1 Any further degradation in the level l of safety ,of the plant or other -
i worsening plant conditions, including l
those that require the declaration of any of the Emergency Classes, if such a delcaration has not been previously made or Any change in the Emergency Class or Termination of the Emergency.
4.1.5.1.2 The results of ensuing evaluations or assessments of plant conditions 4.1.5.1.3 The effectiveness of response or i protective measures taken, i
'^ 4.1.5.1.4 Information related to plant
),
behavior that is not understood, u ,
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a79WNAQF/tM ENCLOSURE 4.2 PAGE 1 OF 4 CHECKLIST FOR SIGNIFICANT EVENT NOTIFICATION
' ~
~i Complete the applicable portions of this enclosure and transmit to the NRC !
Operations Center as required by Enclosure 4.1. -
l Approved by the Shift Supervisor or Emergency Coordinator i I
State the following to the NRC Operations Center:
"THIS NOTIFICATION IS MADE IN 'ACCORDANCE WITH 10CFR50.72. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION ll MAKING THE NOTIFICATION."
- 1. a. My Name is: My title is:
My Location is: Catawba Nuclear Station, Concerning Unit I can be called-back at (1/2/Both)
- b. "Your Name Please" Event Report Sequence No.
- c. "Do we have your permission to tape record this conversation?"
If No, turn off the recorder.
- 2. Time of Notification Date of Nacification
- 3. Event Classification: Check appropriate box (s).
C;_m
- a. -Emergency Plan Declaration
_ -Other immediate Notification O- Notification of. Unusual Event O- Alert O- Site Area Emergency 0- General Emergency
- 6. O-A "ONE-HOUR" Notification
- c. 0-A "FOUR-HOUR" Notification
- d. O-A "24-HOUR" Notification
- 4. Event
Description:
Category Initiation Signal Reactor Trip ESF Actuation ECCS Actuation Safety injection Flow Other
,.. LCO Action Statement
RP/0/B/5000/13 ENCLOSURE 4.2 PAGE 2 OF 4
.r, System Component U Cause: Mechanical Electrical Personnel Error Procedural Inadequacy Other
~
Event Time EDT/ Event Date Mo. / Day Event
Description:
- 5. Plant Status:
- a. Power prior to event:
- b. Power at time of report:
- c. Did all systems function as required? (if no, Yes/No explain below.
i
- d. Anything " unusual" or not understood?
(if yes, Yes/No explain below) .
O.
... )
- e. Corrective Actions:
- f. Mode of Operation till correction
- g. Estimate of time to restart
- 6. Outside agencies or personnel notified:
State: N.C. L S.C.
County: York, Gaston L Mecklenburg i
NRC Resident , ,
(Y es) (No) (will be)
Other: Press Release: l (Yes/No)
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' RP/0/B/5000/13 ENCLOSURE 4.2 PAGE 3 OF' 4 er
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- 7. Radiological Release: (if yes. complete this o- Y es/No paragraph) .
1
- a. Release: Liquid Gaseous Planned Unplanned
- b. Location / Source:
- c. Release Rate:
- d. Duration of Release:
- e. Estimated Total Activity:
- f. Estimated Total lodine:
- g. Grab Sample: -
- h. Monitor Reading:
- i. Tech Spec Limit:
- j. Personnel Exposed or Contaminated:
.D.
G; .
- k. Areas Evacuated:
- 1. Plant HP Backup Requested:
- m. Additional Information:
- 5. Additional Information on NC System Leaks or S/G Tube Leaks:
- a. Sudden or Long Term Development:
- b. 'itart Date & Time:
- c. Leak Rate:
- d. Leak Volume:
- e. Tech Spec Limit .
-(l.
s/
. f. Primary Coolant Activity: '
- g. Secondary Coolant Activity:
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- RP/0/B/5000/13 ENCLOSURE 4.2 PAGE 4 OF' 4 es
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- h. Radiation Monitor Readings:
- 1. Condenser
- 3. S/G Blowdown
- i. Safety Related Equipment Not Operational:
- j. Special Actions Taken (if any):
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.- RP/0/B/5000/13 ENCLOSURE 4.3
. PAGE 1 OF 1 "a REPORT OF SERIOUS PHYSICAL SECURITY EVENTS' DATE/ TIME OF NOTIFICATION NRC PERSON NOTIFIED State the following to the NRC Operations Center:
"THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10C FR73. 71. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION 11 MAKING THE NOTIFICATION."
My Name is: My title is:
I can be reached at .
"Your Name Please" .
- 1. *DATE OF OCCURRENCE: 3.* POWER LEVEL OF UNITS:
- 2.
- TIME OF OCCURRENCE: Unit 1 Unit 2
') *lf date and time of occurrence are not known, indicate the date and time of
' discovery.
- 4. DESCRIPTION OF EVENT:
- 5. SECURITY RESPONSE / COMPENSATORY MEASURES ESTABLISHED: -
- 6. LLEA (Local Law Enforcement Agency) NOTIFIED 7 YES NO (if Yes, name organization and telephone number)
- 7. CONSEQUENCES AT PLANT:
Description of Equipment Systems Affected fy
':)
. RP/0/B/5000/13 ENCLOSURE 4.4
. PAGE 1 OF 3 9-2 LIST OF ESF ACTUATIONS REQUIRING NRC NOTIFICATION WITHIN FOUR HOURS .
NOTE: This is a guideline only, it may not contain all possible ESF actuations.
- 1. Safety injection (FSAR 6.3.1, 6.3.2)
- a. NV charging path .
- b. Ni charging path
- c. ND charging path
- d. UHI injection
- e. CLA injection
- f. D/G sequencer activation
- g. RX trip signal
- h. FWST - Containment sump ND suction swap ,
- 2. Containment Spray (FSAR 6.2.2)
- a. NS pump start / valve alignment
! - ;4
- b. Actual spray down of containment
- 3. Containment isolation (FSAR 6.2.4)
- a. Phase A (St)
- b. Phase B (Sp)
- c. Containment Purge and Exhaust (Sh)
- 1. EMFs 38, 39, 40 activated
- d. NW system injection
- 4. Steam Line Isolation (FSAR 10.3.2)
- a. Individual steam line valve closure *
- b. System Isolation
- a. Main feedwater control valve c!osure*
- p. b. Main feedwater control bypass valve closu,re*
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- lndividual component activation due to component failure not reportable per this requirement.
@ @/0/8/5000/13 ENCLOSURE 4.4 PAGE 2 OF 3 Oi c. Main feedwater containment isolation valve closure * ,
- d. Main feedwater containment bypass valve closure *
- e. Aux feedwater tempering valve closure *
- 6. Turbine Trip (FSAR 10.2.1) caused by:
- a. Manual actuation (required because of 6 - e and no auto trip)
- b. S afet', injection signal
- c. S/G Hi Hi water level (P-14)
- d. RX trip (P-4)
- e. Trip of both Main feed pumps
- 7. Containment Pressure Control System (FSAR 7.6.5)
- a. Start or termination permissive actuation
- 8. Auxiliary Feedwater System o a. Aux feed pump start (Auto)
- )
V b. Pump suction swap to RN
- 9. Loss of Power (FSAR 8.3.1.1.2)
- a. Actuation of undervoltage relays on loss of voltage to essential busses
- b. Actuation of undervoltage relays on grid degraded voltage
- c. D/G sequencer activation
- 10. Control Room Area Ventilation Operation (FSAR 9.4.1)
- a. Simultaneous operation of A and B trains
- i
- a. Any unanticipated system operation i
- Individual component activation due to component failure not
../ reportable per this requirement.
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RP/0/B/5000/13 1
- . ENCLOSURE 4.4 !
PAGE 3 OF'3 1 m 12. Annulus Ventilation Operation (FS AR 9.4.9. 6.2.3).
i l-Any unanticipated system operation
- a. .
- 13. Nuclear Service water System (FSAR 9.2.1.2. 9.2.1.3)
- a. Auto pump starts
- b. RN train separation *
- c. RN pump suction transfer to SNSWP
- 14. Auxiliary Buidling Filtered Ventilation Exhaust Operation (FS AR 9.4.3.1)
Filtered mode of operation in conjunction with isolation of all Auxiliary Building Areas, except ECCS Pump Rooms.
- 15. Spent Fuel Pool Ventilation Operation (FSAR 9.4.2) l a. System placed in the filter mode by EMF 42
- 16. Engineered Safety Features Actuation System interlocks
- a. Any unanticipated activation fr,
- Individual component activation due to component failure not
' j-r reportable per this requirement.
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Forrn 34731 (R8 85) RP/0/B/5000/14 (Il ID '40-DUKE POWER COMPANY Change (si- 0 s PROCEDURE PROCESS RECORD '3.
) O lnCorDorated PREPARATION 'l Recype (2) STATION Catawba Nuclear Station (3) PROCEDURE TITLE FOLLOW-UP NOTIFICATIONS FROM TSC
.1 (4) PREPARED BY Mike Bolch DATE 12-10-86 (5) REVIEWED BY W A DATE / 7 -/d ~80 Cross Disciplinary Review B b / N/R M-/O b (6) TEMPORARY APPROVAL (If Necessary)
By (SRO) Date By Date (7) APPROVED BY
' DATE N II
/
(8) MISCELLANEOUS
(}
Reviewed / Approved By -
Date
{ :)
uj Reviewed / Approved By' -
Date (9) COMMENTS (For procedure reissue indicate whether additional changes, other han previously approved changes, are incl Attach additional pages,if necessary.) C ADDITIONAL CHANGES INCLUDED.
COMPLETlON (10) COMPARED WITH CONTROL COPY DATE (11) OATE(S) PERFORMED (12) FROCEDURE COMPLETION VERIFICATION O Yes C N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? I C Yes C N/A Listed enclosures attached?
)
C Yes C N/A Data sheets attached, completed, dated and signed?
C Yes C N/A Charts, graphs, etc. attacned and properly dated, identified and marked?
O Yes C N/A Acceptance criteria met?
VERIFIED BY DATE e .= ,
- , (13) FROCEDURE COMPLETION APPROVED DATE
> i,,) l (14) REMARKS (Attach additional pages,if necessary.)
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-S, RP/0/B/5000/14
. DUKE POWER COMPANY '
CATAWBA NUCLEAR STATION FOLLOW-UP NOTIFICATIONS FROM TSC 1.0 SYMPTOMS 1.1 An alert or greater emergency has been declared.
1.2 The Technical Support Center (TSC) is in the process of or has been activated.
1 2.0 IMMEDIATE ACTIONS 2.1 Prior to TSC Activation.
2.1.1 The Offsite Communicators (s) shall proceed directly to the Control Room, to obtain a turnover from the Operations Group.
o Ensure all message forms that have been transmitted are available to take back to the TSC.
o Note the time of the last message transmission and ensure that the next required message is sent on time.
l 2.2 Notification Schedule -
2.2.1 Give Follow-up Messages to offsite agencies listed on Enclosure 4.1, use the following schedule:
o Every hour for Alert, every half hour for Site Area & General Emergency, until the emergency is terminated.
E o if there is any significant change to the situation f escalating o to a higher emergency classification.
NOTE: The State and County notification must be made within 15 minutde of escalation of the emergency.
Use part. l.only for this circumstance. i I
E i o As agreed upon with the individual agencies.
NOTE: Documentation shall be maintained for any
( agreed upon schedule change and the interval
- V shall not be greater than every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Alert, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Site Area & General Emergency, to any agency.
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RP/0/B/5000/14
- Pag 3 2 cf 3 l
,[; 2.2.2 Use parts 1 s 11 of Warning Message Form for t
l E. follow-up notifications. Mark all spaces "N/A" -
l when information is "Not Applicable" and mark l "Later" when information is not currently ;
available. l
\
3.0 SUBSEQUENT ACTION I 3.1 Telephone numbers for offsite agencies are listed on Enclosure 4.1. Messages are authenticated using Enclosure 4.4.
I 3.2 Log the transmission of all messages in the Emergency Comriunications Log, Enclosure 4.2.
3.3 Copy all pertinent questions (from offsite agencies) received on a Message Reply Form (MRF) and relay the message to the Emergency Coordinator for a response. Retain a copy of the MRF I
with the Emergency Comm. Log.
3.4 Information for transmission offsite shall be obtained as indicated by Enclosure 4.3, in4rmation Flowchart. Approval by the Emergency Coordinator must be obtained prior to transmission.
3.5 Problems with the Communications Systems should be directed to the Compliance Engineer, f) 3.6 Important! Anytime that the emergency classification is escalated
(/ '
ensure the following is included on the message form:
4 o Alert to Site Area Emergency - Activate the alerting Siren
' System and inform the public via the Emergency Broadcast System. .
o Site Area Emergency to General Emergency - People living in zones A-O + 5 mi DW remain indoors.
3.7 Document the turnover of communications responsibilities, from
) you ta the CMC's Offsite Notification Coordinator. Inform the Emergency Coordinator of the turnover, i 3.7.1 After the turnover to the CMC, one offsite Communicator i
I shall remain at the TSC to maintain contact with the Offsite Notification Coordinator.
3.7.2 In the event of a loss of communications capability at i
j the CMC or a loss of communications to the CMC the Offsite Communicators will have to re-assume the j information transmission duties, i'
' 3.8 Ensure that the Emergency Message Forms, Message Reply Forms t, Emergency Comm. Log is received by the Compliance Engineer
( following termination of the emergency.
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'. , Pag 3 3 of 3 4.0 ENCLOSURES
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4.1 Offsite Agency Telephone List .
4.2 Emergency Communication Log 4.3 Information Flowchart 4.4 Message Authentication Mechanism - (to be omitted, except with the Control Copy of this procedure) l '7N
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DUKE POWEs JMPANY RP/0/8/5000/1 / .
CATAWBA NUCLEAR STATION ENCLOSURE 4.1 ~~ !
0FF-SITE AGENCY TELEPHONE LIST Page 1 of 2
- , l CRISIS MGT. '
l I. WARNING POINTS SELECTIVE SIGNALING TELEPHONE RADIO CODE A. Counties
- 1. York County Warning Point 41
- 2. Gaston County Warning Point 26
- 3. Mecklenburg County Warning Point 21
- 8. States
- 1. North Carolina Warning Point N/A
- 2. South Carolina Warning Point - initial EPD Radio and escalation messages only, follow-up (later) message to to the Duty Officer at the telephone # provided.
Dept. of Health and Environmental Control
+ These #'s may be accessed jointly by S1*
- II. EMERGENCY OPERATIONS CENTERS A. Counties'
- 2. Gaston County EOC 26 -
Gaston County Police Dept., Gastonia
- 3. Hecklenburg County EOC/ 21 Law Enforcement Center', Charlotte
l k. DUKEPOWEhsMPANY RP/0/B/5000/1k j
CATAWBA NUCLEAR STATION ENCLOSURE 4.1 0FF-SITE AGENCY TELEPHONE LIST Pcge 2 of 2 ..
I l B. States ,
I i
- a. E0C N/A Raleigh, NC D. SERT Crisis Mgt.
Air Guard Armory, Charlotte Radio-No Code #
II. ENERGENCY OPERATIONS CENTERS SELECTIVE SIGNALING TELEPHONE RADIO CODE
- b. FEOC EPD Radio Clover National Guard Armory (later)
III. CRISIS MANAGEMENT CENTER A. Offsite Notification Coordinator N/A B. Offsite Radiological Coordinator No Code #
C. Nuclear Tech Serv Marager N/A SELECTIVE SIGNALING NOTES:
- 1. For prob s with the system, call Maintenance Planner (System Communications) at or have them paged at
- 2. To cancel a call, dial or N. C. stations and or S. C. stations. -
- 3. The ringing signal " times out" after 15 sec. , if you do not connect once, try a couple more times using Group Call and/or Individual #'s. If still no success, then use the Bell liens next and Crisis Mgt. radio last. Radi6 messages
! to N. C. and S. C. can be relayed by the appropriate County Warning Points.
RP/0/B/5000/14 ENCLOSURE 4.2 Paga ~ cf ~
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CATAWBA NUCLEAR STATION EMERGENCY COMMUNICATIONS LOG -
TIME I INITIALS ITEM NO. IN OUT INCIDENT OR MESSAGE ACTION i
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~ 'RP/0/B/5000/14 Enc!ssuro 4.3 l
INFORMATION FLOWCHART Pago 1 cf 1 s,
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OFFSITE CCISEUltICATOR 1
u EEALTR PEYSICS - RADIOtoGICAL DATA ANALYSIS COORD. DATA Part 2 Items 64, 5, 6, 7 8, 9, & 10
" Part 1 Itant 44, 5 , 6 & 7 OPERATICIES _ PLANT Part 2 ASST. OPERATING ENGR. ~
STATUS Itama ti, 2 & 3 Part 3 Items il & 2 i
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ACTICII Item 48 RECCISEENDATICII h
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DUKE POWER COMPANY RP/0/B/5000/14 CATAWBA NUCLEAR STATION Encl:: sura 4.4 MESSAGE AUTHENTICATION MECHANISM Page 1 of 1 rs_ .
This page is left intentionally blank.
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," F rin 34731 (G9 86) (1) 10 N2.HP/0/B/1009/17 DUKE POWER COMPANY Change (s) O ts PROCEDURE PROCESS RECORD o
.m PREPARATION incorporated s ,. .
(2) STATION Catawba Nuclear station (3) PROCEDU.RG TITLE Post-Accident Containmant Af* Ra-nling Ayeram (4) PREPARED BY N - A DATE Ohl (5) REVIEWED BY
- h DATE I /d 2
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Cross Disciplinary Review By N/R -
l (6) TEMPORARY APPROVAL (if Necessary)
By (S810) DATE By DATE (7) APPROVED BY I DATE (8) MISCELLANEOUS +
Reviewed / Approved By DATE O Reviewed / Approved By DATE
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(9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes, are included.
Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. E,Yes CNo (10) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION
- O Yes C N/A Check lists and/or blanks properly initialed, signed, dated or filled in NrA or N/R, as appropriate?
O Yes C N/A Listed enclosures attached?
O Yes C N/A Data sheets attached, completed, dated and signed?
Cyes C N/A Char's, graphs, etc. attached and properly dated, identified and marked?
C Yes C N/A Acceptance criteria met?
VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED DATE l
- (14) REMARKS (Attach additional pages,if necessary.)
1 l
m . . HP/.0/B/1009/17 9 DUKE POVER COMPANY CATAWBA NUCLEAR STATION POST-ACCIDENT C0hTAINMENT AIR SAMPLING SYSTEM 1.0 PURPOSE To describe a method for obtaining a containment air sample after a nuclear reactor accident using the Nuclear Post-Accident Containment Air Sampling System (PACS).
2.0 REFERENCES
2.1 CP/0/B/8800/13, Chemistry Procedure for the Preparation of Thiosulfate Solution for Post Accident Gas Sampling 2.2 HP/0/B/1000/06, Emergency Equipment Functional Check and Inventory
, 2.3 HP/0/B/1009/06, Alternative Methods for Determining Dose Rate Within the Reactor Building 2.4 OP/1/A/6450/10, Containment Hydrogen Control Systems 2.S OP/2/A/6450/10, Containment Hydrogen Control Systems s
2.6 RP/0/B/5000/12, Control of Assessment and Repair Teams i
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2.7 Duke Power Company Nuclear Station Post-Accident Containment Air Sampling System II Manual. File No.: CNM-1210.09-0218001 2.8 NuReg-0737 II.B.3 Post-Accident Sampling Capability 2.9 Post-Accident Containment Air Sampling System - Qualifications, File No.: CN-134.10 3.0 LIMITS AND PRECAtJTIONS 3.1 Exposure from the samples have the potential to be very high; therefore, appropriate surveillance and control of personnel shall be provided by Health Physics when taking sacples. Entry and exit route to sample panel and control panel area are to be determined by Health Physics surveys.
3.2 The Recire Pump shall never be used at any pressure other than 0" of Hg.
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("'N 3.3 Moving the Selector switch (#9) from one mode to another stops all 1
\;,
- current system operations. Depressing the Activate pushbutton (#10) starts operation of the newly selected mode. l 3.3.1 Numbers within parentheses (ex. #9) are locations on Enclosure 5.6 and on the control panel.
3.3.2 (SP) to the left of the enclosure step number requires a person to go to the sample panel.
3.4 The Radiation Monitor (#3) on the contro,1 panel should provide background levels of radiation prior to, during, and after sampling, and an indication of contamination within the system or panel for progressive samples.
3.5 If the needle of the Radiation Monitor (#3) exceeds the upper and of.the meter scale while the lower scale (mR/hr) is being used, immediately turn the selector knob to the higher scale (R/hr)..
3.6 If the Radiation Monitor (#3) reading cannot be reduced below 10 R/hr do not return to the sample panel, but contact the Reserve Personnel / Personnel Monitoring Leader (RPPM) immediately for further instructions. ;
3.7 If problems with the Radiation Monitor (#3) are evident (e.g. no
,c-indication of radiation on the meter), notify the RPPM and rely on Health Physics surveys to determine access to the sample panel, b)
3.8 If thiosulfate comes in contact with the skin during preparation, .
- transferal or dilution, wash the affected area as soon as possible with soap and lukewarm water. Consult station nurse for further instructions.
3.8.1 Do not use NA0H solution and/or sodium thiosulfate crystals (Na 5:03 -SM 0) if the expiration dates on their labels have been exceeded.
3.8.2 Chemistry should prepare NA0H solution and sodium thiosulfate crystals (Na:S 0s-5Hz) per Reference 2.1.
3.9 Dispose of contaminated syringes, septums, rubber gloves, etc., in appropriate radioactive waste receptacles.
3.10 Individuals that have been trained on this procedure are the individuals qualified to use this procedure. Individuals shall be trained and tested every six (6) months and documented in Reference 2.9.
3.11 Due to the nature of this procedure..a Working Copy shall be used to ensure compliance.
4.0. PROCEDUPJ
[ , 4.1 Follow steps on the RPPM PACS Checklist (Enclosure 5.1).
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i "# 4.2 Follow steps on Post-Accident Containment Air Sampling Set-Up (Enclosure 5.2).
- 4.3 Follow steps on Taking Post-Accident Containment Air Samples (Enclosure 5.3) and complete Post-Accident Containment Air Sample Data Sheet (Enclosure 5.4) for each containment air sample request.
4.3.1 If applicable, determine containment dose rate per Reference 2.3.
4.4 Ensure the isotopic analysis of each containment air sample and its associated Enclosure 5.4 are submitted to the Station Health Physicist.
- 4.5 Follow steps on Post-Accident Containment Air Sampling Shut-Down (Enclosure 5.5).
4.6 File enclosures and associated calculations in the Health Physics Satellite Master File. -
4.7 Connect an appropriate transfer container and drain the sump by turning the Key Lock switch (#48) to Sump Pump. Accompanying power ,
light should illuminate.
4.8 Reinventory OSC kit after use per Reference 2.2.
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6.J' O 5.0 ENCLOSURES
- 4 '
5.1 RPPM PACS Checklist 5.2 Post-Accident Containment Air Sampling Set-Up 5.3 Taking Post-Accident Containment Air Sacples 5.4 Sample of Post-Accident Containment Air Sample Data Sheet 5.5 Post-Accident Containment Air Sampling Shut-Down 5.6 Post-Accident Containment Air Sampling Control Panel (PACP) Diagram 5.7 Post-Accident Containment Air Sampling Sample Panel (PASP) Diagram i
5.8 Location of PACP and PASP
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- DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/17 ENCLOSURE 5.1 I[ h
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RPPM PACS CHECKLIST Date/ Time / Unit Check hetion 5.1.1 After completion of Team Personnel Lists of Reference 2.6, select at least one qualified individual based on PACS training and MSA training (refe.r to Reference 2.9, Health Physics file 134.10-4 or the OSC Health Physics Notebook).
Select another individual to accompany the other. Consider: !
- Age
- Accumulated exposure
- Sex
- Respiratory printout 5.1.2 Consider the following for the PACS:
- Operable breathing air hookups
- Throat mikes ,
- Portable instruments (PIC-6A, Teletector)
- High range dosimetry
- Extremity dosimetry I"?X - To and from route to PACS Y.[.'. ',
EMF-2 Control Room readout
- EMF-1 Control Room readout
- Flashlight
- Radios
- Control Points 5.1.3 Request assistance in acquiring needed equipment from the Technical Support Center (TSC).
5.1.4 Prepare Counting Room to receive sa=ple. Consider:
- RC7 setup
- Shielding
- Disposal of sample
- MCA setup
- Personnel
- Dosimetry (high, extremity) 5.1.5 If necessary, complete dose extension forms.
5.1.6 Obtain a High Radiation Area key.
5.1.7 Have equipment prepared for conditions at PACS. Consider:
- Taping wheels on porta-pig
- Bagging loose items s.s e
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ENCLOSURE 5.1
/*9'; RPPM PACS CHECKLIST l M .~ . .
Check Action 5.1.8 Inform selected individuals of precautions, Safety and Health Physics concerns and then have them obtain the sample.
5.1.9 Remain in contact with the technicians throughout the sampling. They should report problems and data as they get them.
5.1.10 Complete Enclosure 5.4 and route to Counting Room before the analysis takes place.
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EP/0/B/1009/17 -
- c,. ENCLOSURE 5.2 POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP Date/ Time / Unit Check Action 5.2.1 Inform the Shift Supervisor that gas sampling will be performed and that one Hydrogen Analyzer will need to be inoperable during sampling. Request that Operations complete the Setup Section for Post-Accident Containment Air Samp1'ing of procedure OP/1/A/6450/10 or OP/2/A/6450/10 (see Reference 2.4 or 2.5).
5.2.2 After notification that Operations has completed the PACS Setup Section, obtain the Post-Accident Containment Air Sampling Equipment located in the OSC Emergency Kit.
The equipment should be the following:
Quantity Item 1
1 - Post-Accident Control Panel (PACP) Key 2 - 500 ml Nalgene bottle labeled "2.42 x 10,8 M NaOH" 2 - vials of .3 ga Na4S0 2 3- SHa0
.fczy, 2 - 500 ml Nalgene bottle labeled " Iodine Sample"
(;i.nf 2 - 100 ml gas bomb 2 - 60 ml Nalgene bottle - labeled " Iodine Sample" 1 - Stop watch 5.2.3 Prepare thiosulfate solution by adding one vial of Na2S2 03-5H2 O to one bottle of NaOH. Shake vigorously until all of the crystals are dissolved. Relabel as
" Thiosulfate".
5.2.4 Verify that the Selector switch (#9) is in the off position. I 5.2.5 Move the System Purae toggle switch (#20) to the Normal position.
5.2.6 Move the Gas Purge toggle switch (#16) to the center position.
5.2.7 Move the Refill toggle switch (#24) to the Off (down) position.
5.2.8 Turn Key Lock switch (#48) to Power On. Accompanying power light should illuminate.
5.2.9 Turn the Radiation Monitor (#3) On by moving the toggle I switch (located below the meter) to the Ug position. l
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ENCLOSURE 5.2 (f,,' POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP .
Check Action 5.2.10 Turn the Radiation Monitor (#3) selector to BATT and verify that the needle is in the " red test region" on the right end of the scale. If reading is below the test region, rely on Health Physics surveys to determine access to the sample panel.
5.2.11 Select the appropriate rate so that the needle is on the meter scale by first turning the selector knob to higher scale (R/hr) and, if necessary, to the lower scale (mR/hr).
(SP) 5.2.12 Open all four (4) service valves DI, VI, N2 and TS by turning handles one quarter turn counterclockwise. The DI, VI, and Na valves are located on the outside upper left side of the sample panel, and the TS valve is located on top of the sample panel.
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. .e, ENCLOSURE 5.3 Q. .? TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES ,
Date/ Time / Unit Check Action (SP) 5.3.1 Pour thiosulfate solution into f.he thiosulfate tank, located on top of the sample panel. Leave the cap off of the thiosulfate tank after transferring the thiosulfate solution (Refer to Section 5.2.3 for preparing more solution).
(SP) 5.3.2 Attach an " Iodine Sample" bottle to the sample panel by inserting the plastic hose into the bottle located on the lower lef t side of the panel. Disconnect the quick connect connector on the lower side of the sample panel and replace with a gas bomb.
5.3.3 Turn Key Lock switch (#48) to on._ ,
5.3.4 Turn Selector switch (#9) to System Purse.
g 5.3.5 Depress Activate pushbutton (#10).
5.3.6 Depress Evac pushbutton (#17) (Evac light should -
illuminate) and watch the vacuum gauge (#6) drop to
-25" of Hg.
5.3.7 When the vacaum gauge (#6) reaches -25" of Ha, depress the i Stop pushbutton (#19).
5.3.8 Press down the Gas Purge toggle switch (#16) and watch the vacuum gauge (#6) swiftly rise to +5" of Mr.
5.3.9 When the vacuum gauge (#6) reaches +5" of Hz, return toggle switch (#16) to center position and depress the Stop pushbutton (#19).
5.3.10 Depress the Evac pushbutton (#17) and watch the vacuum gauge (#6) drop to 0" of Hg. !
5.3.11 When vacuum gauge (#6) reaches 0" of Ha, depress the Stop pushbutton (#19).
5.3.12 Depress Pump pushbutton (#18) and wait for thirty (30) seconds.
5.3.13 Depress Stop pushbutton (#19). *
(y 5.3.14 Press up the Gas Purae toggle switch (#16) and wait three (3) minutes.
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.. DUKE POWER COMPANY
. , CATAWBA NUCLEAR STATION HP/0/B/1009/17 ENCLOSURE 5.3 n.g TAKING POST-ACCIDENT CONTAINMENT AIR SA.TLES
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Check Action 5.3.15 Return the toggle switch (#16) to the center position.
5.3.16 Turn Selector switch (#9) to Solution Changeout.
5.3.17 Record the Radiation Monitor (#3) reading as a backgrcund reference:
R/hr 5.3.18 Depress Activate pushbutton (#10).
5.3.19 Depress Flush pushbutton (#22) and hold five (5) seconds.
5.3.20 Depress Purge pushbutton (#23) and hold ten (10) seconds.
5.3.21 Depress Empty pushbutton (#21) and hold for thirty (30) seconds.
5.3.22 Move the Refill toggle switch (P24) to ON (up) position and wait two (2) minutes and then cove the toggle switch i back to the Off (down) position.
5.3.23 Turn Selector switch (#9) to Dilution Volume Evacuation.
~~
s:04# 5.3.24 Depress the Activate pushbutton (#10) and watch the vacuus (14 -
gauge (#6) drop to -25" of Hg.
5.3.25. When the vacuum gauge (#6) reaches -25" of Hg, turn Selector switch (#9) to Sample Recire.
5.3.25 Depress Activate pushbutton (#10) and wait for five (5) minutes.
5.3.27 Record sample line temperature reading (#4): *C 5.3.28 Record sample inlet line pressure (psig) reading (#5):
psig 5.3.29 Depress Sample pushbutton (#11) and wait for ten (10) seconds.
5.3.30 Depress Trap puchbutton (#12) and wait for thirty (30) seconds.
5.3.31 Enter time of sample trap: (ex. 1355) 5.3.32 Turn Selector switch (#9) to Sample Dilution.
5.3.33 Depress Activate pushbutton (#10).
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5.3.34
,;f Depress Slow pushbutton (#13) and watch the vacuum gauge (#6) j rise to 0" of Hg.
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, DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/17 - -
ENCLOSURE 5.3 TAXING POST-ACCIDENT CONTAINMENT AIR SAMPLES
- Check Action 5.3.35 When the vacuum gauge (#6) reaches 0" of Hg, depress the Stop pushbutton (#14).
5.3.36 Depress the Recire pushbutton (#15) and wait for five (5) minutes.
(SP) 5.3.37 Disconnect the quick connect on the gas bomb outlet side, wait five (5) seconds and disconnect the gas bomb.
Replace the quick connect connector.
5.3.38 Depress the Stop pushbutton (#14).
5.3.39 Turn Selector switch (#9) to Solution Changeout.
5.3.40 Depress Activate pushbutton (#10).
5.3.41 Depress the TS Sample pushbutton (#25).
S.3.42 Depress and hold the Empty pushbutton (#21) for five (5) minutes. Thiosulfate should transfer into the TS sample bottle.
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Zi)> 5.3.43 ' Depress Purge pushbutton (#23) and hold. thirty (30) seconds.
5.3.44 Depress TS Sample Grab pushbutton (#26). .
5.3.45 Turn Selector switch (#9) to System Purge.
5.3.46 Depress Activate pushbutton (#10).
5.3.47 Repeat steps 5.3.6 through 5.3.15 as needed until no noticeable decrease is observed on the Radiation Monitor
(#3) from one purge to the next. Check blank in steps 5.3.6 through 5.3.15 each time the step is performed.
5.3.48 Record the Radiation Monitor (#3) reading: R/Hr 5.3.49 Turn Key Lock switch (#48) to Off.
(SP) 5.3.50 Disconnect and tightly cap the " Iodine Sample" bottle.
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ENCLOSURE 5.3 h.
TAKING POST-ACCIDENT CONTAINMENT AIR SA.9LES Check Action 5.3.51 Determine the Thiosulfate Sample Volume (TSV) and record this value as TSV: el 5.3.52 Using standard chemistry laboratory techniques and under a sample hood, transfer 50 ml of the " Iodine Sample" into the 60 ml Nalgene bottle. Contact Radwaste Chemistry for instructions on disposal ot excess sample.
5.3.53 Place the 60 ml " Iodine Sample" bottle and the gas bomb into a shielded container as needed.
5.3.54 Using a monitoring instrument (such as the R02A or PIC-6A) take a contact dose rate reading on the top of the gas bomb and on the side of the " Iodine Sample" bottle:
R/hr gas bomb, R/hr " Iodine Sample" 5.3.55 Transfer the " Iodine Sample" and gas bomb to the Health Physics Counting Room for isotopic analysis.
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ENCLOSURE 5.4 0.. ,
SAMPLE OF POST-ACCIDENT CONTAINMENT AIR SAMPLE DATA SHEET
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- l Date/ Tine: / Unit Prepared By- Emergency - Drill i
(Circle One)
First Radiation Monitor Reading from 5.3.17 R/hr Sample Line Temperature from 5.3.27 *C Sample Inlet Line Pressure from 5.3.28 psig Sample Trap Time from 5.3.31 Second Radiation Monitor Reading from 5.3.48 -R/hr Contact reading on gas bomb from 5.3.55 R/hr (Top)
Contact reading on " Iodine Sample" bottle from 5.3.55 R/hr (Side)
Containment Sample Volume --
293*K (14.7 psig + psig) tga .
CSV = 1.4 ml X X
--q';
' (273*C + 'C)*K 14.7 psig 4
J1 CSV = ml at standard temperature and pressure
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u
+ . -j Ub SV = 50 ml X 1.0101 =
ml (CSV) X m1 7
ml (TSV) where: 50 m1 sample size + Thiosulfate Samp14 Volume from 5.3.51 1.0101 = 1 + .99, thiosulfate is 99'a efficient for removing iodine Section volume of CSV trapped in gas bomb --
SV G= ml (CSV) X .009 =
ml where: .009 = 100 mi gas bomb + 11194 ml volume of dilution i
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Station Health Physicist ~'
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,, s ENCLOSURE 5.4 .
i..' SAMPLE OF POST-ACCIDENT CONTAINMENT AIR SAMPLE DATA SHEET Date/ Time: / Unit Prepared By: Emergency - Drill (Circle One)
First Radiation Monitor Reading from 5.3.17 R/hr Sample Line Temperature from 5.3.27 *C Sample Inlet Line Pressure from 5.3.28 psig Sample Trap Time from 5.3.31 Second Radiation Monitor Reading from 5.3.48 R/hr Contact reading on gas bomb from 5.3.55 R/hr (Top)
Contact reading on " Iodine Sample" bottle from 5.3.55 R/hr (Side)
Containment Sample Volume --
293*K (14.7 psig + psig)
CSV = 1.4 ml X X .
(273"C + "C)*K 14.7 psig s CSV = ml at standard temperature and pressure
< \
Section volume of CSV trapped in " Iodine Sample" bottle --
SV ml (CSV) X SO ml X 1.0101 = m1 7=
ml (TSV) where: 50 mi sample size + Thiosulfate Sample Volume from 5.3.51 1.0101 = 1 + .99, thiosulfate is 99*. efficient for removing iodine Section volume of CSV trapped in gas bomb --
SV ml (CSV) X .009 =
G= ml where: .009 = 100 mi gas bomb + 11194 ml volume of dilution Station Health Physicist Date i
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ENCLOSURE 5.5
", POST-ACCIDENT CONTAINMENT AIR SAMPLING SHlJTDOWN Date/ Time _,/ Unit Check Action 5.5.1 Turn Selector switch (#9) to Off.
5.5.2 Turn Radiation Monitor (#3) Off.
(SP) 5.5.3 Replace the top to the TS tank.
(SP) 5.5.4 Close all four (4) service valves DI, VI, N2 and TS by turning handles one quarter turn clockwise.
5.5.5 Request that Operations complete the Shutdown Section for Post-Accident Containment Air Sampling of procedure OP/1/A/6450/10 or OP/2/A/6450/10 (see Reference 2.4 or 2.5).
5.5.6 Notify Shift Supervisor of sampling completion and that the Hg Analyzer used during sampling is not required for sampling.
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. s. . - POST-ACCIDENT CONTAINMENT AIR SAMPLING CONTROL PANEL (PACP) DIAGRAM
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i l Cl. +
4g :
, RAO!ATICN -
i 6
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MON lTCR 1 1 l
l
Paga 1 of 1
. DUKE POWER COMPAhT f CATAWBA NUCLEAR STATION
, .HP/0/B/1009/17 .
ENCLOSURE 5.7 I'- ~
_ ,, POST-ACCIDENT CONTAINMENT AIR SAMPLING SAMPLE PANEL (PASP) DIAG A-O l l
%,J n
O O O DI JN3 N2 e,.c .frinie, Ir;et Inist a
OO O D3 INS N2
- w.ater air valve
. 3.......
i.
8m;et
- o. . .o .. I outlet front 5 l
- ,') 9 s
O
- T5 esw t e O O 0"*" O 75 ,! O O TS I lle.et outlet! l s
t
/ ; I
/ !
, \.
1 -
/ .,
'. / l 1
l 1 . - -
Paga 1 of 1
,,e
"' DUKE POWER COMPAhT
' ?
f CATAVBA NUCLEAR STATION !
, HP/0/B/1009/17 -
ENCLOSURE 5.8 ^
[', LOCATION OF PACP AND PASP
- x. ,
\
) -
l l 4
Rx.#1
- J - -
8 .
I r-
' - T
- O _
233 N Unit 1 PASP N Unit 1 PACP 200
,C.1' '
, g g 0% _
244 r" Unit 2 PASP
- ts* /
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L -
I g .
u Rx.w2 i i V
l
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.