DCL-02-140, Emergency Plan Implementing Procedure Update
| ML023500208 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/06/2002 |
| From: | Gillies G Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 50-275-OL, 50-323-OL, DCL-02-140 | |
| Download: ML023500208 (12) | |
Text
WE Pacific Gas and Electric Company Diablo Canyon Power Plant P0 Box 56 Avila Beach. CA 93424 December 6, 2002 80O 5456000 PG&E Letter DCL-02-140 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Emer-qency Plan Implementinq Procedure Update
Dear Commissioners and Staff:
In accordance with Section V, "Implementing Procedures," of 10 CFR 50, Appendix E, enclosed is an update to the emergency plan (EP) implementing procedures for Diablo Canyon Power Plant, Units 1 and 2.
As provided under 10 CFR 50.54(q), the changes have been made without prior NRC approval since they do not decrease the effectiveness of the EP. The EP, as changed, continues to meet the standards of 10 CFR 50.47(b) and 10 CFR 50, Appendix E.
This update does not contain privacy/proprietary information.
If there are any questions regarding this update, please contact Mr. Mark Lemke of my staff at (805) 545-4787.
Sincerely,
- c.
Grant C. Gillies Director, Site Services baf/1 3451A0522550E24 Enclosures cc:
David L. Proulx Girija S. Shukla cc/enc: Ellis W. Merschoff (2)
A member of the STARS (Strategic Teaming and Resource Sharing) Altiance Cattaway
- Comanche Peak a Diabto Canyon o Palo Verde e South Texas Project
- Wolf Creek PG&E Letter DCL-02-140 LOCATION OF PRIVACYIPROPRIETARY INFORMATION IN EMERGENCY PLAN IMPLEMENTING PROCEDURES FOR DIABLO CANYON POWER PLANT, UNITS 1 AND 2 Procedure Number Privacy/
Proprietary Information Title/Location of Privacy/Proprietary Information Release of Airborne Radioactive Materials Initial Assessment No EP R-2 Rev. 21
4 PG&E Letter DCL-02-140 DIABLO CANYON POWER PLANT EMERGENCY PLAN "IMPLEMENTING PROCEDURES Table of Contents - Emergency Plan Implementing Procedures Volume 1A (OM10.1D3 only), Volume 1B (OM10.DC1 only), and Volume 3B
- . No.
Rev.
Title OM10.1D3 OM10.DC1 EP G-1 EP G-2 EP G-3 EP G-4 EP G-5 EP R-2*
EP R-3 EP R-7 EP OR-3 EP RB-1 EP RB-2 EP RB-3 EP RB-4 EP RB-5 EP RB-8 EP RB-9 EP RB-10 EP RB-11 EP RB-12 EP RB-14 EP RB-15 EP EF-1 EP EF-2 EP EF-3 EP EF-4 EP EF-9 EP EF-10 Proc 6
Emergency Plan Training 2
Emergency Preparedness Drills and Exercises 31 Emergency Classification and Emergency Plan Activation 25 Activation and Operation of the Interim Site Emergency Organization 39 Notification of Off-Site Agencies and Emergency Response Organization Personnel 19 Assembly and Accountability 9A Evacuation of Nonessential Site Personnel 21 Release of Airborne Radioactive Materials Initial Assessment 8C Release of Radioactive Liquids 13 Off-Site Transportation Accidents 6A Emergency Recovery 5B Personnel Dosimetry 4B Emergency Exposure Guides 4
Stable Iodine Thyroid Blocking 4A Access to and Establishment of Controlled Areas Under Emergency Conditions 4C Personnel Decontamination 16 Instructions for Field Monitoring Teams 11 Calculation of Release Rate 9
Protective Action Recommendations 12 Emergency Offsite Dose Calculations 6
Plant Vent Iodine and Particulate Sampling During Accident Conditions 7
Core Damage Assessment Procedure 11 Post Accident Sampling System 29 Activation and Operation of the Technical Support Center 27 Operational Support Center 22 Activation and Operation of the Emergency Operations Facility 14 Activation of the Off-Site Emergency Laboratory 8
Backup Emergency Response Facilities 5
Joint Media Center Activation and Operation
- Procedure included in this submittal Proc
,*ISSUED FOR USE BY:
DATE:
EXPIRES:_______
"-PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2' NUCLEAR POWER GENERATION REVISION 21 DIABLO CANYON POWER PLANT PAGE 1 OF 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE:
, Release of Airborne Radioactive Materials Initial
-Assessment 1
EFFECTIVt DATE PROCEDURE CLASSIFICATION: QUALITY RELATED 1.*-SCOPE 1.1 This procedure describes the steps to be taken by on-shift personnel to initially evaluate the off-site consequences of an accidental airborne release that ma'y result in Emergency' Plan Activation.
1.2 It does not describe the operation of the plant equipment necessary to terminate or minimize the release. This latter subject is covered in the appropriate E, ECA,'and FR "series Emergency Proceduresfor the partcular release mechanism.
- 2.
DISCUSSION 2.1 An accidental airborne release of radioactive materials that may result in site boundary dose rates in excess of the limits speified in the EP G-1 shall require a prompt initial "a"sseissminent by' the operating staff. 'This initial release rate and dose assessment is performed using either the Plant Process Computer (PPC) program "EPR2," or manually
.u-isin Seciin'7 f this proceduie.
-2.2 This procedure shall onlybe used by Control Room personnel to perform initial accident
" dose assessments. This procedure shall not be used to evaluate compliance With Technical Specificati6ri limits during planned effluen't ieleases conducted as part of normal plant operations. The ineth6dology contained in this pr6cidure' is intended to provide a rapid and conservative calculation of the projected off-site doses due to an accidental release of airborne radioactive materials. More advanced methodologies are contained in procedures EP RB-9 and EP RB-11 or the appropriate chemistry procedures.
- 3.
DEFINITIONS 3.1 Accidental Release - A release of radioactive material unrelated to any planned effluent release evolutions.
3.2 Committed Dose Equivalent (CDE) - The dose to the organs or tissues that would be received from an intake of radi6dictiVe material b 'an indi.idul during the 50 years following the intake.
3.3 Committed Effective Dose Equivalent (CEDE) - The sumof the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the CDE to these organs ortissues"
- " T i -
00358421.DOA 03B
-2 1031.0313
PACIFIC GAS AND ELECTRIC COMPANY NUMBER-- E? R-2 DIABLO CANYON POWER PLANT REVISION'. 21 PAGE 20f 5
TITLE:
Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 3.4 Deep Dose Equivalent (DDE) - Dose associated wvith exposure of the whole body (depth of I cm).
3.5 Total Effectiv-e Dose Equivalent (TEDE) - The sum of the DDE (for external exposure) and CEDE (for internal exposure).
3.6 TEDE Rate,- The time rate of change of Total Effective Dose Equivalent as a function of immersion and inhalation exposure time.
3.7 Thyroid CDE Rate - The time rate of change of Thyroid Committed Dose Equivalent as a function of immersion and inhalation exposure time.
- 4.
RESPONSIBILITIES 4.1 Emergency Evaluation Coordinator (EEC) is responsible for performing an initial assessment of an airborne radiological release when directed by the ISEC.
4.2 Interim Site EmergenCy Coordinator aSEC) is rfesponsible for determining when an assessmhent is needed and directing the EEC to iniplement this procedure based on emergency evaluation priorities.
5.,
PREREQUISITES 5.1 Unified Dose'Assess'ment Center (UDAC) is not a'ctivated and performing the function of "radi6logical assessment.-.
5.2 Interim Site Emergency Coordinator (ISEC) has deteriined, based on ilant accident conditions or symptoms of an accidental radiological release, that an initial assessment of projected off-site doses has priority over other actions being pei-formed by the EEC.
The following listed symptoms indicate that an airborne release may be occurring from within the RCA as guidance to th& ISEC:
Theie is actual or suspected leakage of water, steam,' or noncondensible gases from any ve'ssel 'or piping system containing primary' coolant, liquid radwaste, or gaseous radwýaste.
.or.gaseous Damage occurs to a submerged, irradiated fuel assembly with the resultant release of significant quantities of noncondensible gases.
"* Alarms occur on CAMs.
"* A fire'occurs involv'ing radiohctive materials.
(Refer to EP M-6)
"* Verified alarm on radiation monitors RE-14/14R, RE-28/28R, RE-29, RE-15/15R, or RE-24/24R.
"* A major radi6active material spill occurs.
00358421 DOA 03B 10310313
-,,PACIFIC GAS AND ELECTRIC COMPANY,.
NUMBER-EP R-2 DIABLO CANYON POWER PLANT REVISION 21 PAGE 3 OF 5 TITLE:
Release of Airborne Radioactive Materials Initial Z
,UNITS, 1 AND 2 Assessment
- 6.
PRECAUTIONS
.6.1 Do not use SPDS to obtain RMS readings. Radiological Monitor readings off SPDS may be based on different units of measurement than required as input to the calculations.
6.2 If the Main Condenser is available during a SGTR event with a stuck open Safety Relief or 10% Steam Dump to atmosphere; there are two release pathways.
6.3 Obtain an independent verification of your 'alculatioii whenever time permits to confirm no errors or incorrect assumptions about plant conditions.,
6.4 Default release ratis are extreinely conservative and may result in higher classifications or PARs than would be warranted if actual release indications were available.
6.5 N-16 will be detected on the MSL Radiation Monitors while at power and may cause a false high off-site dose calculation.
6.6 This procedure shall not be used to evaluate compliance to Technical Specifications
, during planned efflueýnt.releases'., Such evaluations shall be performed by the Chemistry Departmenii.
.W.
6.7 Fuel Handling Accident (FHA) in Containment with Equipment Hatch open is a special case.' Use the analyzed default dose rates and doses listed in Attachment 10.1 and go
- 7.
INSTRUCTIONS j
NOTE: This calculation can be performed on the PPC using the turn-on code "EPR2."
"7.1..
'-RELEASE RATE CALCULATIONS-7.1.1 Obtain aworking copy of Attachment 10. 1.
7.1.2 Determine release source locationf as Plant Vent, Atmospheric Steam Release, or, Unmonitored.
CAUTION: Do NOT use SPDS to obtain radiation monitor readings.
7.1.3' Gather and record tle'required information in accordance with the appropriate section of the form.
NOTE: Plant Vent Extended Range Rad Monitor RE-87 will automatically activate if the Normal Range Gas Monitor's RE-14/14R approach their
-., maximum reading.,
7.1.4 Perform the required calculation to determine the release rate of Total Effluent and record the results in both this Attachment and Attachment 10.2.
7.1.5 If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3 of Attachment 10.1 and choose the most appropriate value for input to Attachment 10.2. For an FHA in containment with equipment hatch open, use default dose rates and doses from 0.1 and go directly to EP G-1 for comparison to the EALs.
00358421 DOA 03B 1031.0313
PACIFIC GAS AND ELECTRIC COMPANY NUMBER ;, E? R-2 DIABLO CANYON POWER PLANT REVISION' 21 PAGE 4 OF 5 TITLE:
Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 7.2 OFF-SITE DOSE CALCULATIONS NOTE:. Calculations may be performed using the PPC routine "EPR2," or by hand, as follows:
7.2.1 Obtain a working copy of Attachment 10.2.
7.2.2 Gather and record the riluired information in accordance with the appropriate sectiofi of the form.
NOTE: Plant Process Computer (PPC) Meteorological Data turn on codes are "METP" (Primary Data) and "METB" (Back-up Data).
7.2.3 Determine the appropriate activity source term and circle the associated DCF's to be used in Section 4A and 4B.
7.2.4 Perform the required calculations to determine the TEDE and THYROID CDE RATES.
7.2.5 Project the RELEASE DURATION in hours as inputto determining projected doses.
7.2.6
- Ifa duration cannot beprojected, iise the DEFAULT DURATION of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
7.2.7 Perform the required calculations to deterniine the TEDE and THYROID CDE at the Site Boundary (800 meters).
7.3 REPORTING THE RESULTS,
7.3.1 Refer to EP G-1 and compare the results of the above calculations with the Emergency Action Levels.'
7.3.2 Refer to EP RB-I 0and compare the iesilt6 of the dose calculations with the PAR determination criteria.
7.4 Advise the IStC of any EAL thresholds that are exceeded based on site boundary dose rates and doses, or the need to rev'ise PARs dtie to changing conditions'.
7.5 CONTINUOUS ACTIONS, 7.5.1 As directed by the ISEC, continue to perform assessment of airborne releases to support evaluaton of EAL status and PARs by repeating the above instructions.
7.5.2 Contact Chemistry to request:
- a.
A sample of the radioactive effluent (if possible) and in-plant airborne activity.
b.-
A confirmatory assessment of the site boundary dose rate from the release.
00358421 DOA 03B 1031 0313
-PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:
Release of Airborne'Radioactive Materials Initial Assessment NUMBER REVISION PAGE "UNITS
- 8.
RECORDS 8.1' All checklists generated during activation of the EOF for drills and exercises are non-quality Good Business Records and shall be retained by Emergency Planning Group fnr three vearsI S..
.2 8.2 All checklists generated during activation of the EOF for a real event are non-quality records and shall be retained in RMS ii accordance with AD1O.ID2.
- 9.
APPENDICES None
- 10.
ATTACHMENTS, 10.1
""Release Rate Calculations," 10/31'/02' 10.2
'""Off-Site Dose Calculations," 08/05/94
- 11.
REFERENCES 11.1 EP G-1= "Accident Classification and Emergency Plan Activation."
1 L2 EP G-2, "Activation and Operati6n of the Interim Site Emergency 0 Room).
11.3 EP RB-9, "Calculation of Release Rate.".
11.4 EP RB-I 0, "Protective Action Recommenditions."
-11.5
. EP RB-11, "Emergency Off-site Dose Calculations."
11.6 EP RB-12; "Mid and High Range Plant Vent Radiation Monitors."
11.7 E3P M-6, !"Fire."
11.8 NRS-RES Calculation No. RA 93-12, New Dose Conversion Factor:
rganization (Control s for EP R-2 and SRB-1i1, Validation and Vernticatlon, Kev. 1, 121151i3.
11.9 NOS-RECE Calculation No. RA 93-04, EP RB-9, Calculation of Release Rate, Rev. 7 and R-2, Release of Airborne Radioactive Materials, Rev. 12,'Validation and Verification, Rev. 0, 4/12/93.
11.10 SH&ES Calculation No.'EP-94-01, Rev'0, EP R-2, Release'of Airborne Radioactive Materials, Rev 17, Validation and Verification.
11.11 PG&E Calculation PAM-0-04-517, Rev. 4, 4/6/97 "Steam Generator Narrow Range Level Uncertainty."
11.12 PG&E Calculation STA-160, Rev.0, "Estimate of Expected Exposures Associated with a Fuel Handling Accident With Containment Open."'...
00358421.DOA 03B 1031.0313 EP R-2 21 5 OF 5 1 AND 2 I
DIABLO CANYON POWER PLi EPR-2-1 '
ATTACHMENT 10.1 10/31/02 TITLE:
Release Rate Calculations PLANT VENTrRELEASE
- 1.
GENERAL INFORMATION Date:
Time:
A Assessment No.-
Assessment By:
Unit Releasing J
- 2.
PLANT VENT FLOW RATE DETERMINATION, A.
DIRECT'- Plant Vent Flow Rate FR-12 (0-30x104 CFM (CFM)
Ei=
ii (CFM)
B.
ALTERNATE - Operating Ventilation Equipment (Max No. possible)
- Fans (CFM/Fan)
FHB Exhaust (1) x 35,750 (CFM)
Aux Bldg Exhaust (2) x 73,500
=
(CFM)
GEGWArea
-(1).
x 25,000 (CFM)
Cont. Purge
'(1) x 55,000 (CFM)
- 'x "
M )
'--.--Cont. Hydrogen' (1)..
"x
' 300
=
(CF Plant Vent
'Flow Rate' (CFM)
- 3.
RELEASE RATE CALCULATION CAUTION: Do NOT use SPDS to obtain monitor readings.
A.
NOBLE GAS RELEASE RATE,'
Circle -
Reading (Units)
S..
Conversion Plant Vent-Noble Gas, Monitor Factor Flow Rate Release Used.
(CFM)
-' Rate (Ci/sec)
Primary RE-14/14R/87 CVcc x 4.72E-04
'x x Backup RE-29 mR/hr
,x 4.72E-06 x
'=
B.
TOTAL EFFLUENT RELEASE RATEo NOTE: Refer to Page 3 for criteria in choosing RCS, GAP, orCORE below.
...Noble G 'Rel6ase Total Effluent
- Total Effluent Rate (Ci/sec)
Conversion Factor Release Rate S...
(Ci/sec)
__________________x 1.00(RCS)
=
1.11 (GAP) 1.50 (CORE)
NOTE:' If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3 of this attachment.
--1 1 GO TO ATTACHMENT 10.2 00358421.DOA 03B Page 1 of3 ANT I
1031.0313
10/31102 Page 2of 3 EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.1 TITLE:
Release Rate Calculations
- 1.
GENERAL INFORMATION ATMOSPHERIC STEAM RELEASE Date:
Time:
Assessment No.
Assessment By:
Unit Releasing CAUTION: WHEN CRITICAL, N-16 ACTIVITY SEEN BY MSL RAD MONITORS CAUSES INVALID READINGS FOR OFFSITE DOSE. POST-TRIP, RE-7X READING IS VALID IF THE RE-7X MONITOR SHOWED AN INITIAL N-16 RESPONSE, OR RESPONDS TO CHECKSOURCE.
NOTE: If it is not possible to calculate a release rate, refer to~the DEFAULT RELEASE RATES on Page 3.
- 2.
STEAM RELEASES - Use this form to calculate steam releases to the atmosphere WHEN NOT critical.
A.
Required Information (RUPTURED GENERATOR ONLY)
Check MSL Rad Reading S/G LvI Level S/G Flow Flow Rate Ruptured S/G Monitor (cpm)
Narrow
(%)
Rate (Ibs/hr)
Range If<4E5 use 4E5 rJ SG 1 RE-71 LI-517 FI-512 use_4E5 M
SG 2 RE-72
__LI-527 FI-522 rJ SG 3 RE-73 LI-537 FI-532 M SG4 RE-74 '
LI-547 FI-542 B.
Alternate Steam' Flow Rate (Only if the RUPTURED S/G Flow Rate is otherwise not available)
Valve Type
- Valves' Capacity (lbs/hr)
Flow Rate (lbs/hr) iUfted.
10% Steam Dump (1 per S/G) x 4.OE+05
=
Safety Reliefs (5 per S/G).....
_x 8.5E+05
=
Total Steam Flow Rate (lbs/hr)
(lbs/hr)
- 3.
RADIATION MONITOR FACTORS (Determined based on S/G NR Level indication) (Enter in Section 4 below.)
S/G Level EMPTY NORMAL FLOODED Narrow Range
<4%
4% - 96%
> 96%
Monitor Factor 6.08E-10 6.75E-10 3.07E-10 (DEFAULT)
- 4.
RELEASE RATE CALCULATIONS A.
TOTAL EFFLUENT RELEASE RATE (RE-7x)
MSL Monitor Reading Flow Rate Monitor Factor Total Effluent Release (cpm)
(Ibs/hr)
Rate (Ci/sec)
GO TO ATTACHMENT 10.2 00358421 DOA 03B 1031.0313
EP R-2 (UNITS I-AND 2)
ATTACHMENT, 10.1 TITLE:
Release Rate Calculations
- 1.
SOURCE TERM SELECTION M6ND bEIAULTRELE*,bE RATES NOTE: Use default release rate only if actual data is not available or if the release is not being monitored.
A.
Check the accident type which most closelyresembles the current event.
. Default Releasb Source Rate (CVsec).
Term Accident Source Condition LOCA (wI core melt)
LOCA (w/o core melt)
Main Steam Line Break
,I!
Feedwater Line Break J Blackout-EJ Locked Rotor SFHB Accident, MJ Rod Ejection MJ GDT Rupture M
LUT Rupture F-- VCTRupture EJ SIG Tube Rupture 1.74 t+1" 5.74 E+0.,,
RE-30 or 31 >300R/hr "
RE-30 or RE-31 <300R/hr RE-30 or RE-31 not on scale 8.61 E-3 8.61 E-3 8.62 E-1 1.57 E-2
.1.45 E+1 1.08 E-2 4.14 E+1 3.10 E+1 8.29 E-2 1.65 E+0 NR'S/G Level < 4%
NR-S/G Level 4-96%
NR SIG Level > 96%
"GAP GAP RCS
- RCS.
RCS SG-Empty SG - Normal SG Flooded Containment FHA S.B. Dose TEDE = 13.4 mrem/hr Go Accident with Equip.
Rates Thy.CDE = 51.4 mrem/hr Directly to Hatch Open S.B. Doses
- TEDE=6.7 mrem EP G-1 Thy. CDE = 25.7 mrem B.
Record the Default Release Rate in Attachment 10.2, Section 4 and use the DCF choice that is listed for the specific accident source above.
GO TO ATTACHMENT 10.2 00358421.DOA 03B 1031 0313 S 10/31/02 Page 3 of 3
DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.2 TITLE:
Off-Site Dose Calculations
- 1.
GENERAL INFORMATION Date:
Time:
Assessment No.
Assessment By:
Unit Releasing
- 2.
METEOROLOGICAL DATA - PPC (Plant Process Computer)
Turn On Codes for Met Data are "METP" (Primary Data) or "METB" (Back-up Data)
Parameter Reading Units DEFAULT Wind Speed (10 Meter Level) meters/sec Wind Direction (10 Meter Level)
Degrees Site Boundary X/Q (0.8 kin) 7 Sec/r 3 5.29E-04
- 3.
DCF Determination -
Select the most appropriate source term for the DCF using the criteria in 0.1. Circle the corresponding DCF in Section 4 below.
- 4.
DOSE CALCULATIONS - (From data calculated using Attachment 10.1)
A.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
Total Effluent or Site Default Release Boundary DCF TI Rate X/Q (0.8 km)
(circle one)
R (Ci/sec)
(Sec/rm)
(mr x
x 0.1 1.1E + 05 (RCS) 3.OE +06 (Gap) 1.1 E + 07 (Core) 1.1 E + 05 (SG-Empty) 4.3E + 04 (SG-Normal) 9.3E + 05 (SG-Flooded)
=DE ate em/hr
),
Projected Release Duration (hr)
(DEFAULT 3 hrs) zzI~x_
B.
THYROID COMMITTED DOSE EQUIVALENT (CDE) (DO NOT COMPLETE FOR GDT, LHUT, OR VCT RUPTURE)
Total Effluent or Site Projected Default Release Boundary DCF Thyroid Release Thyroid Rate X/Q (circle one)
CDE Duration (hr)
CDE (Ci/sec)
(0.8 km)
Rate (DEFAULT 3 hrs)
(mrem)
(Sec/m")
(mrem/h r) x 0.1 1.5E + 06 (RCS) 6.5E + 07 (Gap) x 7.7E + 07 (Core) 1.5E + 06 (SG-Empty) 1.5E + 05 (SG-Normal) 1.4E + 07 (SG-Flooded)
II-Ix
__IZ I
- 5.
REPORTING THE RESULTS - (Refer to Section 7.3 of Instructions for details)
A.
Refer to EP G-1 for EAL criteria.
B.
Implement EP RB-10 for PAR criteria 00358421 DOA 03B 1031.0313 "TEDE (mrem)
Page I of 1 08/05/94 1-AND2,