Text

Emergency Plan Implementing Procedure Update
	ML083380204
Person / Time
Site:	Diablo Canyon
Issue date:	11/19/2008
From:	Persky M; Pacific Gas & Electric Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	DCL-08-096, GL-81-027
	Download: ML083380204 (120)
	v • d • e

{{#Wiki_filter:Pacific Gas and ElectricCompany' Diablo Canyon Power Plant P.0. Box 56 Avila Beach, CA 93424 November 19, 2008 PG&E Letter DCL-08-096 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 Emergency Plan Implementinq Procedure Update

Dear Commissioners and Staff:

In accordance with Section V, "Implementing Procedures," of 10 CFR 50, Appendix E, enclosed are updated Emergency Plan (E-Plan) Implementing Procedures (EPIPs) for Diablo Canyon Power Plant, Units 1 and 2, as indicated in the Enclosure. 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 E-Plan. The revised EPIPs continue to meet the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E. The procedure changes are identified by revision bars in the right margin. This update does not contain privacy/proprietary information identified in accordance with NRC Generic Letter 81-27. If there are questions regarding this update, please contact me at (805) 545-6275. Sincerely Mark S. Persky Manager- Emergency Services ddm/1345/50078107 Enclosure cc: Michael S. Peck, NRC Senior Resident Inspector Alan B. Wang, NRC Project Manager cc/enc: Elmo E. Collins, NRC Region IV Senior Emergency Preparedness Inspector (RGN-IV/DRS) A member of the STARS (Strategic Teaming and Resource Sharing) Atliance Callaway

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Enclosure PG&E Letter DCL-08-096 DIABLO CANYON POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table of Contents - Emergency Plan Implementing Procedures Volume 1A (OM10.1D1 only), Volume 1B (OM10.DC1 only), and Volume 3B Proc. No. Rev. Title OM10.1D1 8 Maintaining Emergency Preparedness OM10.DC1 4 Emergency Preparedness Drills and Exercises EP G-1 37 Emergency Classification and Emergency Plan Activation EP G-2 31 Interim Emergency Response Organization EP G-3 50 Emergency Notification of Off-Site Agencies EP G-4 22 Assembly and Accountability EP G-5 10 Evacuation of Nonessential Site Personnel EP R-2* 26 Release of Airborne Radioactive Materials Initial Assessment EP R-3 8C Release of Radioactive Liquids EP R-7 15A Off-Site Transportation Accidents EP OR-3 6B Emergency Recovery EP RB-1 5B Personnel Dosimetry EP RB-2 5 Emergency Exposure Guides EP RB-3 5 Stable Iodine Thyroid Blocking EP RB-4 4A Access to and Establishment of Controlled Areas Under Emergency Conditions EP RB-5 6 Alternate Personnel Decontamination Facilities EP RB-8 20 Instructions for Field Monitoring Teams EP RB-9 12 Calculation of Release Rate EP RB-10 13 Protective Action Recommendations EP RB-11 12 Emergency Offsite Dose Calculations EP RB-12* 7 Plant Vent Iodine and Particulate Sampling During Accident Conditions EP RB-14 8A Core Damage Assessment Procedure EP RB-14A* 1A Initial Detection of Core Damage EP RB-15 11 Post Accident Sampling System EP RB-16 1 Operating Instructions for the EARS Computer Program EP EF-1* 35 Activation and Operation of the Technical Support Center EP EF-2 28 Activation and Operation of the Operational Support Center EP EF-3 31 Activation and Operation of the Emergency Operations Facility EP EF-4 15 Activation of the Off-Site Emergency Laboratory EP EF-9 10 Backup Emergency Response Facilities EP EF-10 9 Activation and Operation of the Joint Media/Information Center

Procedure included in this submittal

- - ISSUED FOR USE BY: " DATE: EXPIRES:____

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 NUCLEAR POWER GENERATION REVISION 26 DIABLO CANYON POWER PLANT PAGE 1 OF 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Release of Airborne Radioactive Materials Initial AND Assessment 1 2 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED I1. 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 may 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 Procedures for the particular 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 specified in the EP G-1 shall require a prompt initial assessment by the operating staff. This initial release rate and dose assessment is performed using either the Plant Data Network (PDN) program "EPR2net", or manually using Section 7 of this procedure.

2.2 This procedure shall only be used by Control Room personnel to perform initial accident dose assessments. This procedure shall not be used to evaluate compliance with. Technical Specification limits during planned effluent releases conducted as part of normal plant operations. The methodology contained in this procedure 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-1I 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 radioactive material by an individual during the 50 years following the intake. 3.3 Committed Effective Dose Equivalent (CEDE): The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the CDE to these organs or tissues. EP R-2u3r26.DOC 03B 1023.0724

PACIFIC GAS AND ELECTRIC COMPANY NUMBER iEP R DIABLO CANYON POWER PLANT REVISION 26 PAGE 2 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 3.4 Deep Dose Equivalent (DDE): Dose associated with exposure of the whole body (depth of 1 cm). 3.5 Total Effective 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 (ISEC) is responsible for determining when an assessment is needed and directing the EEC to implement this procedure based on emergency evaluation priorities.

5. PREREQUISITES 5.1 Unified Dose Assessment Center (UDAC) is not activated and performing the function of radiological assessment.

5.2 Interim Site Emergency Coordinator (ISEC) has determined, based on plant accident conditions or symptoms of an accidental radiological release, that an initial assessment of projected off-site doses has priority over other actions being performed by the EEC. The following listed symptoms indicate that an airborne release may be occurring from within the RCA as guidance to the ISEC:

                  "    There is actual or suspected leakage of water, steam, or noncondensible gases from any vessel or piping system containing primary coolant, liquid radwaste, or gaseous radwaste.

Damage occurs to a submerg6d, irradiated fuel assembly with the resultant release of significant quantities ofnoncondensible gases.
Alarms occur on in-plant continuous air monitors (CAM)s.

                  " A fire occurs involving radioactive materials.Ref118

Verified alarm on radiation monitors RE-14/14R, RE-28/28R, RE-29, RE-15/I 5R, or RE-24/24R.

                  "    A major radioactive material spill occurs.

EP R-2u3r26.DOC 03B 1023.0724

PACIEFIC GAS AND XELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 26 PAGE 3 OF 5 TITLE: Release of Airborne Radioactive Materials Initial 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 Itfthe 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 until the affected SG is isolated. The MSL monitor reading on the affected steam generator encompasses the total release rate of the simultaneous release paths. 6.3 Default release rates are extremely conservative and may result in higher classifications or PARs than would be warranted if actual release indications were available. 6.4 N-16 will be detected on the MSL Radiation Monitors while at power and may cause a false high off-site dose calculation. 6.5 This procedure shall not be used to evaluate compliance to Technical Specifications during planned effluent releases. Such evaluations shall be performed by the Chemistry Department. 6.6 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 directly to EP G-I for comparison to the Emergency Action Levels (EALs). 6.7 For plant vent releases, including short duration puff releases such as a ruptured gas decay tank, TRS values for RM-14/14R (cpm) and RM-87 (amps) should be verified and the peak value used for performing the long hand EP R-2 calculation using attachments to this procedure.

7. INSTRUCTIONS This calculation can be performed using the Plant Data Network (PDN) program "EPR2net" or by long hand, as follows:

7.1 Release Rate Calculations 7.1.1 Obtain a working copy of Attachment 10.1. 7.1.2 Determine release source location as Plant Vent, Atmospheric Steam Release, or Unmonitored. CAUTION: Do NOT use SPDS to obtain radiation monitor readings. 7.1.3 Gather and record the 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 Monitors 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. EPR-2u3r26.DOC 03B 1023.0724

PACIFIC GAS AND ELECTRIC COMPANY NUMBER --EP R-2 DIABLO CANYON POWER PLANT REVISION 26 PAGE 4 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 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 Attachment 10.1 and go directly to EP G-1 for comparison to the EALs. 7.2 Off-Site Dose Calculations Calculations may be performed using the Plant Data Network (PDN) program "EPR2net," or by long hand, as follows: 7.2.1 Obtain a working copy of Attachment 10.2. 7.2.2 Gather and record the required information in accordance with the appropriate section 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 Dose Conversion Factor (DCF) 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 input to determining projected doses. 7.2.6 If a duration cannot be projected, use the Default Duration of 3 hours. 7.2.7 Perform the required calculations to determine the TEDE and Thyroid CDE at the Site Boundary (800 meters). 7.2.8 Obtain an independent verification of your calculation whenever time permits to confirm no errors or incorrect assumptions about plant conditions. 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-10 and compare the results of the dose calculations with the PAR determination criteria. 7.4 Advise the ISEC of any EAL thresholds that are exceeded based on site boundary dose rates and doses, or the need to revise PARs due to changing conditions. 7.5 Continuous Actions 7.5.1 As directed by the ISEC, continue to perform assessment of airborne releases to support evaluation 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.

EP_R-2u3r26.DOC 03B 1023.0724

PACIFIC GAS AND-ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 26 PAGE 5 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment

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 for three years.

8.2 All checklists generated during activation of the EOF for a real event are non-quality records and shall be retained in RMS in accordance with ADIO.ID2.

9. APPENDICES None

10. ATTACHMENTS 10.1 "Release Rate Calculations," 04/21/08 10.2 "Off-Site Dose Calculations," 08/05/94 10.3 "EPR2NET Application," 10/20/08 10.4 "Plant Vent Release," 10/20/08 10.5 "Atmospheric Steam Release," 10/20/08

11. REFERENCES 11.1 EP G-1, "Accident Classification and Emergency Plan Activation."

11.2 EP G-2, "Activation and Operation of the Interim Site Emergency Organization (Control Room)." 11.3 EP M-6, "Fire." 11.4 EP RB-9, "Calculation of Release Rate." 11.5 EP RB-10, "Protective Action Recommendations." 11.6 EP RB-I 1, "Emergency Off-site Dose Calculations." 11.7 EP RB-12, "Mid and High Range Plant Vent Radiation Monitors." 11.8 AR A0595224, "PPC EPR-2 Not Valid for FHA in Containment with Hatch Open" 11.9 PG&E Calculation PAM-0-04-517, Rev. 4, 4/6/97 "Steam Generator Narrow Range Level Uncertainty." 11.10 PG&E Calculation STA-160, Freq., "Estimate of Expected Exposures Associated with a Fuel Handling Accident with Containment Open." 11.11 NRS-RES Calculation No. RA 93-12, New Dose Conversion Factors for EP R-2 and RB-11, Validation and Verification, Rev. 1, 12/15/93. 11.12 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. 11.13 SH&ES Calculation No. EP-94-01, Rev 0, EP R-2, Release of Airborne Radioactive Materials, Rev 17, Validation and Verification. EP R-2u3r26.DOC 03B 1023.0724

04/21/08 Page 1 of 3 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.1 TITLE: Release Rate Calculations PLANT VENT RELEASE

1. GENERAL INFORMATION Date: Time: Assessment No.

Assessment By: Unit Releasing

2. PLANT VENT FLOW RATE DETERMINATION 4 (CFM)

A. " DIRECT- Plant Vent Flow Rate FR-12 (0-30x10 CFM (CFM) - OR 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) GEIGW Area (1) x 25,000 = (CFM) Cont. Purge (1) x 55,000 = (CFM) Cont. Hydrogen (1) x 300 = (CFM) Plant Vent F 7 Flow Rate (CFM)

3. RELEASE RATE CALCULATION CAUTION: Do NOT use SPDS to obtain monitor readings.

A. NOBLE GAS RELEASE RATE Circle Reading (Units) Conversion Plant Vent Noble Gas Monitor Factor Flow Rate Release Used (CFM) Rate (Ci/sec) Primary RE-14/14R/87 _ _ _Ci/cc x 4.72E-04 x Backup RE-29 mR/hr x 4.72E-06 x B. TOTAL EFFLUENT RELEASE RATE NOTE: Refer to Page 3 for criteria in choosing RCS, GAP, or CORE below. Noble Gas Release Total Effluent Total Effluent Rate (Ci/sec) Conversion Factor Release Rate (Ci/sec) 1.00 (RCS) = x 1.11 (GAP) 1.50 (CORE) I NOTE: Ifit is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3 of this attachment. GO TO ATTACHMENT 10.2 EP_R-2u3r26.DOC 03B 1023.0724

04/21/08 Page 2 of 3 EP R-2 (UNITS I 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 ifthe 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 SIG LvI Level SIG Flow Flow Rate Ruptured SIG Monitor (cpm) Narrow (%) Rate (Ibs/hr) Range If <4E5 use 4E5

          .1]     SG 1            RE-71                                LI-517                      FI-512
              ]   SG 2            RE-72                                LI-527                      FI-522

[ SG 3 RE-73 LI-537 FI-532 [ SG 4 RE-74 LI-547 FI-542 B. Alternate Steam Flow Rate (Only if the RUPTURED SIG Flow Rate is otherwise not available) Valve Type # Valves Lifted Capacity (Ibs/hr) Flow Rate (lbs/hr) 10% Steam Dump (1 per SIG) x 4.OE+05 = Safety Reliefs (5 per S/G) x 8.5E+05 = Total Steam Flow Rate (Ibs/hr) EZIIZ (Ibs/hr)

3. RADIATION MONITOR FACTORS (Determined based on SIG NR Level indication) (Enter in Section 4 below.)

S/G Level EMPTY NORMAL FLOODED Narrow Range < 4% Unit 1 4% - 96% Unit 1 > 96%

                                                         < 13% Unit 2         13% - 96% Unit 2 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) x x __ GO TO ATTACHMENT 10.2 EP R-2u3r26.DOC 03B 1023.0724

               "   04/21/08                                                                       Page 3 of 3 EP R-2 (UNITS 1 AND 2)

ATTACHMENT 10.1 TITLE: Release Rate Calculations

1. SOURCE TERM SELECTION AND DEFAULT RELEASE 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 closely resembles the current event. Default Release Source Rate (Ci/sec) Term Accident Source Condition LOCA (w/ core melt) 1.74 E+1 RE-30 or 31 >300R/hr CORE [ LOCA (w/o core melt) 5.74 E+0 RE-30 or RE-31 <300R/hr GAP RE-30 or RE-31 not on scale RCS Main Steam Line Break 8.61 E-3 RCS 1] Feedwater Line Break 8.61 E-3 RCS Blackout 8.62 E-1 RCS [] Locked Rotor 1.57 E-2 GAP [ FHB Accident 1.45 E+1 GAP Rod Ejection 1.08 E-2 GAP GDT Rupture 4.14 E+1 RCS LHUT Rupture 3.10 E+1 RCS [] VCT Rupture 8.29 E-2 RCS U1 S/G Tube Rupture 1.65 E+0 NR S/G Level <4% SG - Empty NR S/G Level 4-96% SG - Normal NR S/G Level >96% SG - Flooded U2 S/G Tube Rupture 1.65 E+0 NR S/G Level <13% SG - Empty NR S/G Level 13-96% SG - Normal NR S/G Level >96% SG - Flooded Containment FHA S.B. Dose TEDE = 13.4 mrem/hr Go Accident with Equip. Rates Thy. CDE = 51.4 mremlhr 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 EP.R-2u3r26.DOC 03B 1023.0724

08/05/94 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE: Off-Site Dose Calculations EP R-2 ATTACHMENT 10.2 1 AND 2

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" IPrimary Data) or "METB" (Back-up Data) Parameter Reading Units DEFAULT Wind Speed (10 Meter Level) metersisec Wind Direction (10 Meter Level) Degrees Site Boundary XIQ 10.8 kin) Sele/m 5.29E-04

3. DCF Determination. Select the most appropriate source term for the DCF using the criteria inAttachment 10.1. 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 Boundary Projected TEDE Default Release XIQ (0.8 kin) DCF TEDE Release (Wrem) Rate (Sec/m') (circle one) Rate Duration (hr) (Cilsec) (mremlhr) (DEFAULT 3 hrs) 1.1E + 05 (RCS) 3.OE + 06 (Gap I x x 1.1E + 07 (Core) 1.1E + 05 (SG-Empty)

                                                                                                 "lx Attachment 10.1 4.3E + 04 ISG-Normal) 9.3E + 05 (SG-Flooded)

B. THYROID COMMITTED DOSE EQUIVALENT (CDE) (DO NOT COMPLETE FOR GOT, LHUT, DR VCT RUPTURE) Total Effluent or Site Boundary Projected Default Release XIO (0.8 km) DCF Thyroid Release ThYToId Rate (Secim3) (circle one) CDE Rate Duration ()r) COE (Cilsec) (mrem/hr) (DEFAULT 3 hrs) Irmremi) 1.5E + 08 (RCS) 6.5E + 07 (Gap) x 7.7E + 07 (Core) IZmx Attachment 10.1 1.5E + 06 (SG-Empty) 1.5E + 05 (SG-Normal) 1.4E + 07 (SG-Flooded)

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 EPR-2u3r26.DOC 03B 1023.0724

10/20/0 8 Page I of I DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.3 1AND TITLE: EPR2NET Application

1. Start EPR2NET

a. OPEN the epr2net application:

1) Click on the "epr2net" icon on the PDN Console

2) IF icon is unavailable, TENtyp e <http:H1172.16.20.2/epr2net> in the Internet Explorer "address" field and press E*NTERl.

b. Select the Unit Specific release path button Flant Vený or Steam Releasi

c. For Plant Vent Release data entry, GO TO Attachment 10.4.

d. For Atmospheric Steam Release data entry, GO TO Attachment 10.5.

EPR-2u3r26.DOC 03B 1023.0724

10/20/08 Page I of 2 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.4 1AND TITLE: Plant Vent Release PLANT VENT RELEASE DATA ENTRY:

1. General Information

a. Enter the "Assessment" number

2. Plant Vent Flow Rate Determination:

a. Validate "DIRECT" plant vent-flow rate indicates "OK" in the box to the right of the flow rate.

b. IF the box says: "UNREL" instead of "OK",

THEN Click on "ALTERNATE", and Place a check mark in the box next to all the fans that are operating.

3. Release Rate Calculation:

a. Noble Gas Release Rate For Ongoing Release:

I) LF on scale, AND indicates "OK" to the right of the activity value, THEN select RM-14 or RM-14R, which ever is higher

2) IF both RM-14 and RM-14R indicate "UNREL" AND RM-87 equals 1E-12 amps THEN select RM-29.

3) IF RM-14 or RM-14R is off scale (5E6 cpm is top of scale)

AND indicates "OK" to the right of the activity value, THEN select RM-87 if it indicates "OK" to the right of the RM-87 activity value.

4) IF RM-87 indicates "UNREL" instead of "OK",.

THEN select RM-29. For a Fuel Handling accident or Tank Rupture Release:

1) Attempt to perform the calculation at the peak monitor reading (RM-14, RM-87 or RM-29 as appropriate) for the duration of the release.

b. Release Rate Calculation, Total Effluent Release Rate

1) Select the appropriate source term (click on "HELP" for guidance).

2) Single Click the "NEXT" button at the bottom of the page. This will open a Dose Calculations window.

CAUTION: Every time you click the "N14EXT" button at the bottom of this page, the program creates another Dose Calculations window.

3) IF more than one Dose Calculations window is open, THEN close all open Dose Calculations windows and click the "NEXT" button at the bottom of the Plant Vent Release page. This will open a Dose Calculations window.

EP R-2u3r26.DOC 03B 1023.0724

10/2.0108 Page 2 of 2 EP R-2 (UNITS 1 AND 2) ATTACHMENT 10.4 TITLE: Plant Vent Release DOSE CALCULATIONS DATA ENTRY:

1. General Information

a. Validate current date and time, assessment number, and unit releasing number are the same as the Plant Vent Release page.

2. Meteorological Data - PPC

a. Select Desired Met Data (Primary or Backup)

1) Primary is preferred to backup.

2) Do not select if any of the 3 parameters indicates "UNREL"

3) If both met towers have "UNREL" data, perform a long hand calculation using Attachment 10.1.

3. DCF Determination

a. This carries over from the Plant Vent Release page (do not edit).

4. Dose Calculations, Total Effective Dose Equivalent(TEDE)

a. Total Effective Dose Equivalent (TEDE)

1) Verify the projected release duration (default 3 hours).

a) Enter 0.25 hours for a release under 15 minutes.

2) Enter the calculated TEDE rate in block 10 of the ENF if off-site dose rates are not available form FMTs or PICs.

3) Compare the release duration "Total TEDE" against dose values in EALs RG1.2 and RS.1.2 for classification.

b. Thyroid Committed Dose Equivalent (CDE)

1) Compare the release duration "Total CDE" against dose values in EALs RG1.2 and RS.1.2 for classification.

5. Print the Plant Vent Release page and the Dose Calculations page.

6. Enter the Assessors name at the top of each page.

7. Submit the calculation to the ISEC for approval. Signature on each page.

EP-R-2u3r26.DOC 03B 1023.0724 12372

10/20/08 Page I of 2 DIABLO CANYON POWER PLANT EP R-2 ATTACHMENT 10.3 1AND2 TITLE: Atmospheric Steam Release ATMOSPHERIC STEAM RELEASE DATA ENTRY: I1. General Information

a. Enter the "Assessment" number.

2. Steam Release Rate

a. Select the faulted ruptured SG.

b. Type in the number of relief "valves lifted"

3. Radiation Monitor Factors

a. This section is Information only - no editable fields.

4. Release Rate Calculations

a. No entry required in this section. The monitor factor is changed based on SG level ()indication in Section 2, Steam Release Rate above. This carries over to the DCF section on the Dose Calculations page.

5. Single click the "NEXT" button at the bottom of the page. This will open a Dose Calculations window.

CAUTION: Every time you click the "NEXT" button at the bottom of this page, the program creates another Dose Calculations window.

6. IF more than one Dose Calculations window is open, TEEN close all open Dose Calculations windows and click the "NEXT" button at the bottom of the Atmosphere Steam Release page. This will open a new Dose Calculations window.

EPR-2u0r26DOC 03B 12304 1023.0724

                                                                                                               . I . ý 10/20/08                                                                     Page 2 of 2 EP R-2 (UNITS 1 AND 2)

ATTACHMENT 10.5 TITLE: Atmospheric Steam Release DOSE CALCULATIONS DATA ENTRY:

1. General Information

a. Validate current date and time, assessment number, and unit releasing number are the same as the Atmospheric Steam Release page.

2. Meteorological Data- PPC

a. Select Desired Met Data (Primary or Backup)

1) Primary is preferred to backup.

2) Do NOT select if any of the 3 parameters indicates "UNREL"

3) If both met towers have "UNREL" data, perform a long hand calculation using Attachment 10.1.

3. DCF Determination

a. This carries over from the Atmospheric Steam Release page (do not edit). It is based on the PDN input for SG Narrow Range (NR) water level

4. Dose Calculations, Total Effective Dose Equivalent(TEDE)

a. Total Effective Dose Equivalent (TEDE)

1) Verify the projected release duration (default 3 hours) a) Enter 0.25 hours for a "puff' release under 15 minutes.

2) Enter this calculated TEDE rate in block 10 of the ENF if off-site dose rates are not available from FMTs or PICs

3) Compare the release duration "Total TEDE" against dose values in EALs RG 1.2 and RS. 1.2 for classification.

b. Thyroid Committed Dose Equivalent (CDE)

1) Compare the release duration "Total CDE" against dose values in EALs RG1.2 and RS.1.2 for classification.

5. Print the Atmosphere Steam Release page and the Dose Calculations page.

6. Enter the Assessors name at the top of each page.

7. Submit the calculation to the ISEC for approval. Signature on each page.

EPR-2u3r26.DOC 03B 1023.0724

ISSUED FOR USE BY: DATE: EXPIRES:____ PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 NUCLEAR POWER GENERATION REVISION 7 DIABLO CANYON POWER PLANT PAGE 1 OF 34 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Plant Vent Iodine and Particulate Sampling During AND Accident Conditions 12 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE SC O PE .............................................................................................................................................................. 2 D ISC U SSIO N ..................................................................................................................................................... 2 RE SPON SIB ILITIE S ........................................................................................................................................ 5 PRE REQU ISITES ............................................................................................................................................ 6 PRE CAUTIO N S ................................................................................................................................................ 7 IN STRU CTIO N S ............................................................................................................................................... 8 Method For Plant Vent Mid-to-High Range Iodine (1-131) Monitoring Using RE-24R .......................... 8 Plant Vent Redundant Normal Range (RNR) Skid - Reactivation ....................................................... 8 Mid Level Iodine "li.Ci/ce" Monitoring From the Control Room ....................................................... 10 High Level Iodine "CPM" Monitoring From the Control Room (RE-24R Only) .............................. 12 Plant Vent Redundant Normal Range (RNR) Skid RE-24R's Cartridge (RF-24R) Changeout ...... 14 Method For Plant Vent High Range Iodine and Particulate Sampling Using RF-87A and RF-87B Filters 16 Plant Vent Extended Range (PVER) Skid Sampling - Initial Collection ............................................ 16 Plant Vent Extended Range (PVER) Skid Sampling - Continued Collection ..................................... 18 TSC Analysis of the RF-87's Sample Cartridge ................................................................................ 20 Method For Plant Vent High Range Iodine Sampling Using RF-24R Cartridge ................................... 23 RF-24R - Initial C ollection ...................................................................................................................... 23 RF-24R - Continued Collection ............................................................................................................... 26 TSC Analysis of the RF-24R Sample Cartridge ................................................................................ 27 ACCEPTANCE CRITERIA ............................................................................................................................ 30 REFEREN CES ............................................................................................................................................... 30 RE CO RD S ....................................................................................................................................................... 31 APPEN D IC E S ................................................................................................................................................. 31 A TTA CH M ENT S ............................................................................................................................................ 31 EPRB-12u307.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION '7 PAGE 2 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

1. SCOPE This procedure provides the Plant Vent Iodine and Particulate Sampling (and/or monitoring)

Instructions for assessing radioactive iodine and particulate effluents in the event of a severe plant emergency.

2. DISCUSSION 2.1 Instructional steps are provided for intermediate range monitoring using RE-24R and high range sampling utilizing RF-87A and RF-87B or RF-24R.

2.2 When the Plant Vent Extended Range (PVER) skid's RE-87 "switchover" point occurs on the plant vent's RE-14, both the Plant Vent Normal Range (NR) and Plant Vent Redundant Normal Range (RNR) skids' sampling lines are isolated and their skid pumps shut down. This action also starts the PVER skid sampling pump directing the plant vent air sample through either the RF-87A or RF-87B filter then into the RE-87 noble gas detection chamber. Button switches for either of these filters will light up on the Remote Display Unit (RDU) in the Control Room and on the Local Radiation Processor (LRP) at the NR skid. At that time high range iodine and particulate sampling starts with either RF-87A or RF-87B. The sample pump light also switches from NR/RC-14 to ER/RC-87 on the NR's RDU and LRP. 2.3 Prior to severe accident conditions, the low (normal operations) to mid range radiation detectors RE-14, RE-24, and RE-28 on the NR skid and RE-14R, RE-24R, and RE-28R on the RNR skid monitor respectively noble gases, iodines, and particulates continuously. Their ranges are seen in Figure 6 (Attachment 11.6). RE-14/14R are 2" beta scintillators each viewing a pressurized chamber of continually flowing noble gases. RE-24/24R are 2" sodium iodide (AM-241 seeded for gain stabilization) gamma scintillators each viewing a fixed Ag Zeolite cartridge and "windowed" to see 1-13 l's photo peak. RE-28/28R are 2" beta scintillators each viewing a fixed filter paper. All of these detectors have their analog signals amplified, converted to digital pulses, mathematically smoothed and analyzed as well as archived at the nearby LRP. 2.4 In order to use RE-24R (and optionally RE-28R) for intermediate to high range monitoring, the shutdown of the RNR skid by RE- 14 (during the switchover to the PVER skid) must be overridden, the RNR skid's sample line un-isolated, and the RNR skid's sample pump re-started. 2.5 Reactivating RE-24R (and optionally RE-28R) or RF-24R (with RF-28R) and the RNR skid pump after the high range "switchover" requires at least one visit to the plant vent skid room to perform this manual "switchback" operation. EP-RB-12u3r07.D0C 03B 1021.1031 0103

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 3 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 2.6 The "switchoVer" by RE-14 to the PVER skid is triggered by high noble gas activities. The "switchover" protects RE-14 (and normally RE-14R). Activities of the iodines and particulates will probably not have reached similar high levels. So, RE-24R and RE-28R could probably still read on scale. RE-24 and RE-28 are isolated along with RE-14, but RE-24R and RE-28R can be brought back into service with disregard to RE-14R. When RE-24R (and optionally RE-28R) is used in this manner there are two possible paths of operation described in that which follows. 2.7 Using the ¶RE-24R' method requires someone in attendance at the RDU in the Control Room after the RNR skid has been reactivated in order to relay readings and to turn the skid pump on and off. There are two advantages to this method. Obtaining iodine and, optionally, particulate release information via the Control Room is not only less manpower intensive, but also keeps personnel exposures to a minimum. Also recycling the skid pump on and off gets more use out of the cartridges and filters. 2.8 In the 'UCi/cc' readout (see EP RB-9) portion of the 'RE-24R' method there's the extra advantage of having the microprocessor automatically perform the calculation (i.e., integrations) of a release concentration directly in PCi/cc. This makes the measurements the least labor intensive and the least error prone. However, it takes 20 minutes or more for the LRP's microprocessor to reach an integrated reading of RE-24R (and RE-28R) in jiCi/cc. If the activity concentrations are high, a 20 minute collection interval (between turning on and off the skid pump) may not accommodate a detector reading 'on-scale' (i.e., <lE7 cpm). Also, whenever RE-24R reads near 2 E-4 pCi/cc or the raw countrate on RE-24R or RE-28R reads 1E7 cpm it's time to change out the iodine cartridge and/or the particulate filter (RF-24R and/or RF-28R). 2.9 When the intervals between cycling the RNR skid pump (off-on-off) have to be less than 20 minutes then the 'RE-24R' method must shift to the cpm' readout (see EP RB-9) operation. This requires a precise Control Room readout of not only the time but beginning cpm when the RNR skid pump is turned on then the time and ending cpm when the pump is turned off for each cycling of the pump. Also RE-24R must be in the "DISP OP", "3_", "DISP" keypad readout option. Since releases of iodines are of a higher priority, a reading of the particulate channel RE-28R will not be pursued in the 'cpm' readout operation. This is because the left-most or 'particulate' channel display accommodates only one reading at a time for a "DISP OP" reading. Either iodine or particulate, but not both. 2.10 When the pump cycling intervals and cartridge changeout times become too short to keep ahead of detector countrate saturation then this method must shift away from Control Room operation and resort to sample collection and TSC counting with RF-87A&B or RF-24R (below). EPRB-12u3r07.D0C 03B 1021.1031 10.03

PACIFIC GAS AND ELECTRIC COMPANY NUMBER -.EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE- 4 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 2.11 The High Range Plant Vent Sampling System using RF-87A&B or RF-24R is designed to reliably collect samples of plant vent iodine and particulate effluents. For RF-87A&B, a 1-inch diameter particulate filter pasted onto a 1-inch diameter Ag Zeolite cartridge is used to collect the samples. For RF-24R, the standard 2-inch filter/cartridge is used. These samples are then analyzed using the Gamma Spectroscopy System in the Technical Support Center (TSC) Laboratory. 2.12 High Range sampling with RF-87A/B is set up to give both iodines and particulate release assessments. If however, RE-87's sample pump is down, or RF-87A and RF-87B filters are unobtainable, or electrical Bus "G" is out, then RF-24R cartridge is available for high range iodine sampling only (see instructional step 6.3.1). 2.13 High range sampling and analysis is to be performed within the General Design Criteria (GDC) 19 dose limits for Reg Guide 1.4 source terms referenced in Reg. Guide 1.97 and NUREG 0737 for PWRs. GDC 19 imposes a 5 rem whole body dose limit and a 75 rem extremity dose limit on any one individual. When these limits are approached, the procedure allows for more than one individual to perform the steps collectively. The dose limits are also met for DCPP's most severe Design Base Accident (D.B.A.) case as described in the FSAR. This case is the major LOCA with Reg. Guide 1.4 releases. 2.14 During a severe accident condition two high range radiation detectors also monitor the plant vent. These are RE-29, an 8 decade (0.1 to 1E7 mR/hr) ion chamber viewing directly the plant vent and RE-87, a cadmium sulfide scintillator viewing a sampled stream of noble gases from the plant vent. Their ranges are also seen in Figure 6 (Attachment 11.6) with an overlap shown to the low-(mid) range monitors. Theii response curves are shown, respectively in Figures 4 and 5 (Appendix 10.2) and in Figure 3 (Appendix 10.1) as reproduced from EP RB-9. RE-29's readings are dominated by noble gases but could have small contributions due to the accompanying iodines and particulates, whereas RE-87's readings are confined strictly to the noble gases. However, both monitors are intended to accompany this sampling procedure for indications on the conditions. Their readings are formally utilized for quantitative analysis in EP RB-9 for release rate determinations. EPRB-12u3r07.DOC 03B I021.I031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 5 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

3. RESPONSIBILITIES 3.1 The Radiological Advisor (RA) has the ultimate responsibility for invoking this procedure.

3.2 The Site Chemistry Coordinator is responsible for coordinating and interfacing with the ERA or an appointed assistant to the ERA in invoking this procedure. 3.3 The Site Chemistry Coordinator (SCC) and the Site Radiation Protection Coordinator are responsible for interfacing with each other to ensure this procedure is properly performed. 3.4 The Site Radiation Protection Coordinator is responsible for accessing radiological conditions of the various plant locations used for the particular sampling method being executed by this procedure. Upon assessment the Site Radiation Protection Coordinator is responsible for providing radiological protection controls and ensuring a radiological briefing tailboard is conducted. 3.5 The Site Chemistry Coordinator (SCC) is responsible for the selection of qualified individuals to perform the tasks described in this procedure and that a technical briefing tailboard is conducted. 3.6 The Site Chemistry Coordinator (SCC) is responsible for reviewing the sampling and analysis data for verification and validation purposes. 3.7 Upon review of the sampling data and analysis results, the Site Chemistry Coordinator (SCC) is responsible for communicating this information to the ERA or an appointed assistant to the ERA. 3.8 Personnel assigned to collect samples and radiation monitor data or perform handling and analysis on the samples in the TSC lab are responsible for adhering to the procedural requirements described herein. EP_Rfl-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER . EP RB-12 DIABLO CANYON POWER PLANT REVISION' 7 PAGE 6 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

4. PREREQUISITES 4.1 The personnel responsible for performing this procedure must have had prior training in its implementation.

4.2 The following tools and associated equipment must be available: 4.2.1 Equipment and tools kept in the TSC Laboratory

a. Modified carrier cask with large and small shield plugs

b. Transfer cage

c. Extractor bar

d. Push stick

e. Extra filter/cartridge ingot

f. Extra 1-inch (RF-87) and 2-inch Ag Zeolite cartridges, 1-inch particulate filter (RF-87), and 47mm particulate filters

g. Spare 0-rings for the ingot

h. Pair of pliers

i. Wipe rags

j. Small sample bags

k. Sample labels

1. Tape

m. Medium size screwdriver

n. RF-24R cartridge holder cap grip/removal tool NOTE: The next item may be kept in P.V. Skid Room.

o. Carrier cask for RF-24R EPRB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUM1?BER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 7 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 4.2.2 Equipment and tools kept near the Chemistry Foreman's Office

a. Pair of pliers

b. Tongs

c. Keys to unlock transport dolly in the Plant Vent Skid Room (Key Id.

XAA)

d. Local Radiation Processor (LRP) keys

e. Wipe rags

f. Small sample bags

g. Sample labels hi. Tape

i. Medium size screwdriver 4.2.3 Equipment from Radiation Protection

a. One contamination survey meter (TSC Lab Use)

b. Two Dose Rate Meters (one for sample collection, one for TSC lab use) 4.2.4 Equipment and tools kept in the Plant Vent Skid Room

a. Carrier casks for RF-87A and RF-87B

b. An extractor bar C. Push stick

d. Transport dolly

e. 2 inch Ag zeolite cartridges

f. 47mm filters NOTE: The next item may be kept in the TSC.

g. Carrier cask for RF-24R NOTE: The next item may be kept in the I&C Training Lab.

h. Spare RF-24R cartridge 'holder/plug' assembly

5. PRECAUTIONS 5.1 The RF-87A/B Carrier Cask, Modified Carrier Cask, and RF-24R carrier cask are heavy, 96 lbs and 55 lbs and 47 lbs respectively. When lifting or moving these items be especially careful to know the proper lifting techniques to avoid back strain.

5.2 The exposure levels on the route map, Figure 1 (Attachment 11.4) are from the Design Shielding Review with Reg. Guide 1.97 limits as inputs. When collecting samples using the transport dolly move as expeditiously as possible and assume these exposure rates do exist. EPRB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUIMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION. 7 PAGE 8 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

6. INSTRUCTIONS 6.1 Method For Plant Vent Mid-to-High Range Iodine (1-13 1) Monitoring Using RE-24R NOTE 1: This part of the procedure requires a Chemistry Supervisor to be in the Control Room at the PV's RNR's RDU. It also requires Chemistry personnel to make at least one trip to the Plant Vent Skid Room in order to reactivate the RNR skid.

NOTE 2: All key pad entries involving "ISP.OP," "_," "DISP" must include the program mode key switch going from "ENTER DATA" position to the "RUN" position after the entry, then back to "ENTER DATA." 6.1.1 Plant Vent Redundant Normal Range (RNR) Skid - Reactivation

a. Chemistry person in Control Room obtains keys from Shift Foreman to operate PV's RNR's RDU.

b. Insert keys into the RDU, ensuring the Local Power keylock switch is in the "ON" position and turn the program mode keylock switch to the "ENTER DATA" position.

C. Key in on the keypad:

1. "DISP OP"

2. "3"

3. "DISP" and read the raw countrate on RE-24R's cartridge, (RF-24R). (The analog output to an EARS reading may be sufficient.)

d. Read RE-34's recorder, (RR-34), on the PAM panel and report this reading along with RE-24R's raw countrate to the Site Chemistry Coordinator (SCC).

NOTE 1: RE-34 indicates the dose rate in the area of the PV skid room. NOTE 2: The highest reading from RE-24R occurs at 1E7 cpm. If the raw countrate on RE-24R is greater than 5E6 the SCC may also want to request a cartridge change out. NOTE 3: The following balance of steps apply to personnel going to the plant vent skid room. EP-RB-12u~07DOC 03B 1021.1031 10.03

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 9 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

e. Obtain a dose rate meter to check radiation levels enroute to and at the PV skid room.

f. Obtain a set of keys from the Chemistry Foreman's office to operate the RNR skid's LRP panel in the event local operation of the skid pump is necessary.

g. Proceed expeditiously to the PV skid room (85' level - "L" area) upon receiving instructions from the SCC.

h. Check RE-34's remote readout (just outside the door) prior to entering the PV skid room.

i. Approach the termination enclosure (Panel BTR-P14) at the end of the LRP on the NR skid in the PV skid room.

j. Turn the switch labeled "RE-87/SS" from the "RE87 Norm-OFF" position to the "ER Calib'n-ON" position. This overrides the PVER switchover and removes isolation of the RNR skid.

k. Ensure the Control Mode keylock switch is in the "CR PNL" position.

1. Call Chemistry personnel at the Control Room PV RNR RDU to report the RNR skid is back in service but with the sample pump still turned off.

Inquire as to whether the iodine cartridge or particulate filter need to be changed out at this time.

m. Go to Section 6.1.4, if the cartridge and or filter need to be changed out, OTHERWISE continue.

n. Report to the SCC and leave the PV skid room.

EP_RB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION '7 PAGE 10 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.1.2 Mid Level Iodine ".tCi/cc" Monitoring From the Control Room NOTE: The information determined here supports Section 5 of EP RB-9.

a. Notify the SCC when the PV RNR skid has been reactivated.

b. Go to Section 6.1.3 for "CPM" monitoring if the last "jiCi/ce" RE-24R reading is greater than 2.OE-4 jtCi/cc, OTHERWISE continue.

c. Key in on the RDU keypad:

I. "CH"

2. 1"2"1

3. "FUNC"

4. "13"

5. "DISP" and record from the left most LED (RE-28R's) the time in minutes the RE-24R existing cartridge sampled. Assume this is the same for particulates.

d. Start the RNR skid pump by depressing theFSkid Pump ] button (after OK from PV skid room if cartridge and/or filter had to be changed out).

e. Key in on the keypad: (Only if the cartridge RF-24R was changed out.)

1. "CH"

2. "2"

3. "FUiNC"

4. "13"

5. "DATA"

6. "0"

7. "0"

8. "01

9. "EXP"

10. "0"

11. "01"

12. "ENTR" This restarts the iodine timer.

EP.RB-12u~07DOC 03B 1021.1031 12.0

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 11 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

f. Key in on the keypad: (Only if the filter RF-28R is changed out.)

1. "CH"

2. "0"

3. "FUNC"

4. "13"

5. "DATA"

6. "0"

7. 11011

8. "0"

9. "EXP"

10. "0"

11. " _0"

12. "ENTR" This restarts the particulate timer.

g. Return the keylock switch for program mode back to "RUN".

h. Wait at least 20 minutes, then record RE-24R's and RE-28R's gCi/cc reading.

i. Key in on the keypad:

1. "DISP OP"

2. "3"

3. "DISP" and record the raw counts per minute reading RE-24R from the left most LED (RE-28R's).

j. Key in on the keypad:

1. "DISP OP"

2. "12" I

3. "DISP" and record the sample flowrate reading from the left most particulate LED (RE-28's).

EP.RB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COXIPANY NUMMBER EP RB-12, DIABLO CANYON POWER PLANT REVISION '7! . PAGE 12 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

k. Depress the ISkid Pump button to STOP the sample flow through the cartridge and filter then wait until the SCC clears for another cycling of the sample flow pump.

I. Notify the SCC of the time sampled by RF-24R/28R and the pCi/cc and raw countrate readings on RE-24R and gCi/cc reading on RE-28R. NOTE 1: This information coupled with that from the TSC enables the SCC to decide whether this method can be utilized and/or whether the existing cartridge can still be used. NOTE 2: Again, if the raw countrate on RE-24R is approaching (or exceeds) 1E7 cpm or the last 'gCi/cc' readout on RE-24R is near 2 E-4 pCi/cc, then the cartridge needs to be changed out.

m. Go to Section 6.1.3 for "CPM" readings if the SCC decides or RE-24R indicates that the sample pump cycling time needs to be shorter than 20 minutes. OTHERWISE continue.

n. Go to Section 6.1.4 if the SCC decides or RE-24R indicates the cartridge needs to be changed out. OTHERWISE continue.

o. Return to step 6.1.2c if the SCC gives the clearance for another cycling of the sample pump.

6.1.3 High Level Iodine "CPM" Monitoring From the Control Room (RE-24R Only) NOTE 1: The information determined here supports Section 6.0 of EP RB-9. NOTE 2: Arriving at this point from 6.1.2 or 6.1.4 finds: the sample pump is already off, interest is only on iodines (RE-24R) and microprocessor derived "p.Ci/cc" values are no longer relevant.

a. Key in on the keypad:

1. "DISP OP"

2. "31"

3. "DISP" and record a raw countrate in "cpm" on RE-24R from the left most LED (particulate) for an incremental countrate determination.

b. Immediately depress ISkid Pump Ibutton to START the sample flow and record a beginning time toward an incremental time determination (after OK from PV skid room if the RF-24R cartridge was changed out).

EPRB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 13 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

c. Key in on the keypad:

1. "DISP OP"

2. "12"

3. "DISP" and record the sample flowrate (cfm) reading of RE-24R from the left most LED (RE-28R's).

d. Allow to run for a time recommended by the TSC, anywhere between 1 and 20 minutes while continually observing the flowrate at LED.

e. Depress the I Skid Pum button switch to STOP the sample pump and record the increment ending time after running for an arbitrary length of time around the value recommended by the TSC's Rad. Data Processor.

f. Key in on the keypad:

1. "DISP OP"

2. 11311

3. "DISP" and record this increment's ending raw countrate in "cpm" on RE-24R from the left most LED (particulate channel).

g. Divide the difference in raw countrate readings between a. and f. by the difference in incremental time readings between 6.1.3b and 6.1.3e. This gives the "cpm/min" value, CR (see Form 69-13226).

h. Call the Rad. Data Processor in the TSC and report the result of 6.1.3g. in "cpmlmin" for a "1 min" time interval on the EP RB-9 Section 6.0 Data Sheet.

i. Repeat steps 6.1.3a through 6.1.3h until:

I. the "DISP OP", "3", "DISP" reading indicates 1E7 cpm, or

2. the time intervals between the increments become too short to manage, or

3. the SCC instructs the changeout of the cartridge.

j. Go to Section 6.1.4 if the SCC decides or RE-24R indicates the cartridge needs to be changed out.

k. Terminate the "RE-24R" Method portion of this procedure and go to the

                                   .instructional steps under 6.2 or 6.3 if the incremental time intervals are too short to manage, or if directed by the SCC.

1. Ensure the ISkid Pum button switch was last depressed to STOP by checking the skid pump light being gff.

EPRB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP .RB..-12. DIABLO CANYON POWER PLANT REVISION 7 PAGE 14 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.1.4 Plant Vent Redundant Normal Range (RNR) Skid RE-24R's Cartridge (RF-24R) Changeout NOTE 1: Arriving here from 6.1.1 skip over to step 6.1.4d. NOTE 2: Arriving here from 6.1.3 skip step 6.1.4e.

a. Obtain a hand-held dose rate meter to check radiation levels enroute to the PV skid room. (Applies only to RP escort for Chemistry personnel changing out RF-24R cartridge and/or RF-28R filter).

b. Obtain from the Control Room an advance reading of RE-34.

c. Proceed to PV skid room.

d. Changeout existing RE-24R's cartridge (i.e., RF-24R):

1. Loosen the wing-bolts which secure the cartridge 'holder/lead plug' combination down at RE-24(R)s shielded "pig."

2. Rotate the 'holder/plug' until the four slotted retaining ears clear the studs with the wing-bolts.

NOTE: The 'holder/plug' is heavy and its 0-ring makes a tight seal. It is difficult to pull out. Also loosened wing-bolts should be aligned parallel to the plug's edge so they won't snag on the

                                         'holder/plug' and break off. If any wing-bolts are broken, replace with spares kept in Chemistry P.V. locker.

3. Firmly pull and support the 'holder/plug' out of the "pig."

4. Place the entire 'holder/plug' assembly on the slotted support platform.

5. Unscrew the cartridge holder end cap.

6. Dispose of the cartridge as directed by supervision.

7. Install cartridge into the holder end cap taking particular care to ensure that the airflow 'arrow' is lined up in the direction of flow (same direction as the cartridge that was just removed). The arrow should be pointed toward the handle of the holder.

8. Screw the holder end cap back onto the threaded 'plug' until just snug. The Molykote 55 lubricant may be needed for coating the 0-rings.

EPRB-1203r07.DOC. 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 15 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

9. Slide the entire iodine 'holder/plug' back into RE-24(R)'s "pig" taking care that the O-ring seal is not damaged.

10. Rotate the 'holder/plug' until the slots in the four retaining ears engage the studs.

11. Tighten the wing-bolts finger tight.

12. Notify Control Room of cartridge changeout and return to the procedure step that initiated this changeout.

e. Changeout existing RE-28R's filter (i.e., RF-28R) - (OPTIONAL):

1. Loosen the wing-bolts which secure the cartridge 'holder/lead plug' combination down at RE-28(R)s shield pig.

2. Rotate the 'holder/plug' until the four slotted retaining ears clear the studs with the wing-bolts.

NOTE: The 'holder/plug' is heavy and its O-ring makes a tight seal. It is difficult to pull out.

3. Firmly pull and support the entire particulate 'holder/plug' out of the "pig."

4. Place the entire 'holder/plug' assembly on the support slotted platform.

5. Unscrew the holder end cap taking care that the two concentric spacer rings holding the filter do not drop.

6. Dispose of the filter as directed by supervision.

7. Place a new filter paper on top of the grid face of the smaller spacer ring.

8. Slide outer (or larger) spacer ring over the smaller ring.

9. Screw the end cap back onto the threaded 'plug' u*ntil snug, taking care not to bump the two spacer rings or filter paper off-center. The Molykote 55 lubricant may be needed for coating the 0-rings.

10. Slide the entire 'holder/plug' back into RE-28(R)'s "pig." Take care that the O-ring seal is not damaged.

11. Rotate the 'holder/plug' until the slots of the four retaining ears engage the studs.

12. Tighten the wing-bolts finger tight.

13. Inform Control Room of filter changeout.

f. Leave PV skid room and report to the SCC.

EP-RB-12u~07DOC 03B 12.0 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7,.. PAGE 16 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.2 Method For Plant Vent High Range Iodine and Particulate Sampling Using RF-87A and RF-87B Filters 6.2.1 Plant Vent Extended Range (PVER) Skid Sampling - Initial Collection NOTE: All actions described in this section are performed manually. This includes the switching to the redundant RF-87B filter (or RF-87A filter) and vice-versa.

a. Obtain from the Control Room and record the time of the NR to ER switchover (i.e., activation of RE-87's sample pump).

b. Obtain from the Control Room and record the reading of RE-34 (ALARA area monitor of the plant vent skid room). Communicates this to the Site Radiation Protection Coordinator.

c. Obtain a dose rate survey meter to keep track of dose rates.

d. Obtain a set of keys from Chemistry Foreman's office to operate the NR (and RNR) skid's LRP panel.

e. Obtain any special instructions and controls from the Site Chemistry Coordinator and the Site Radiation Protection Coordinator.

f. Proceed expeditiously to the plant vent skid room (85' level - "L" area) upon receiving instructions from the Site Chemistry Coordinator and the Site Radiation Protection Coordinator.

NOTE 1: Check RE-34's remote readout just outside PV skid room. NOTE 2: If the PVER skid is unavailable then proceed to subsection 6.3 of the Instructions to use RF-24R.

g. Insert a key in the NR skid's LRP panel Control Mode switch and turn to Local in order to operate the pump and filter switches locally.* (Refer to Figure 2 of Attachment 11.5)

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 17 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

h. Record:

1. the time

2. " RE-87 reading

3. sample flowrate The latter can be obtained from either the Hastings flow meter LCD inside the Hoffman termination enclosure on the PVER skid or by:

1. Inserting other key in program mode switch and turning to ENTER DATA

2. Key in "DISP OP" on keypad

3. Key in "1I" on keypad

4. Key in "DISP" on keypad

5. View from RE-28's LED (left most, data is in <units of liters/min).

i. At the NR skid's LRP panel push the RF-87B filter button switch if the sample is being collected via RF-87A or push the RF-87A filter button switch if the sample is being collected via RF-87B. This transfers the RE-87 pump on the PVER skid to stop collection on one filter cartridge and to start collection on the other filter cartridge (i.e., RF-87A vs.

RF-87B).

j. Check that:

1. The ERIRC-87 pump light is o,

2. The previous Filter used (A or B) light goes off,

3. The selected Filter (A or B) light comes on.

k. Mate the desired RF-87A (or B) filter carrier cask up to its respective filter holder on the PVER skid.

1. Lift the pin on the rear of the filter holder.

m. Screw in the extractor bar through the carrier cask and into the threads of the filter ingot of the desired RF-87A (or'B) filter holder.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION " PAGE 18 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

n. Push down on the filter holder's orange handle located on the top rear of the filter holder. The top of the filter holder will pop up and release the filter ingot.

o. Using the extractor bar, transfer the filter ingot from the filter holder into the carrier cask.

p. Push the retaining pin (on front of carrier cask) into the slot of the ingot to hold the ingot in place while transporting.

q. Unscrew the extractor bar and place beside RF-87B's (or A's) filter holder.

r. Survey the carrier cask with the hand-held meter. The dose rate should be less than 0.4 R/hr at 1 foot from contact. If greater, inform the Site Chemistry Coordinator and obtain further instructions.

s. If the dose rate is less than 0.4 R/hr, lift the carrier cask and place in the transport dolly.

t. Unlock the dolly (if it is locked).

u. Proceed to the TSC with the dolly and cask along the route shown in Figure 1 (Attachment 11.4).

v. Unload the cask into the TSC's transfer cage with the restrained end pointing outward.

w. Transfer all initial sample collection data onto Form 69-13224.

x. For radionuclide analysis instructions proceed to step 6.2.3 (unless directed otherwise by the Site Chemistry Coordinator).

6.2.2 Plant Vent Extended Range (PVER) Skid Sampling - Continued Collection

a. Obtain, in the TSC, the extra ingot, a fresh 1" silver zeolite cartridge, particulate filter and new 0-rings.

b. Install the new silver zeolite filter cartridge into the ingot receptacle with the particulate filter on top, taking care that the smaller of the two 0-rings is inserted first and that the other larger O-ring is inserted last.

C. Slide the fresh ingot assembly into the empty carrier cask and reinsert the retaining pin.

d. Proceed back to the plant vent skid room with the carrier cask in the transport dolly.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 19 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

e. Check RE-34's local readout (just outside door) for exposure rate.

f. Mate the carrier cask up to the desired RF-87A's (or B's) filter holder.

g. Screw the extractor bar into the ingot of the carrier cask and lift the cask's retainer pin.

h. Push the ingot back into the desired RF-87A's (or B's) filter holder.

i. Restore the pin in the rear of the filter holder (may have to jostle the ingot until the pin drops into the ingot).

j. Pull up on the filter holder's orange handle to seal and secure the ingot into the desired RF-87A's (or B's) flow path.

k. Unscrew and withdraw the extractor bar.

1. Record the time and step up to the NPR skid's LRP.

m. Push the RF-87A's (or B's) filter button switch and record the sample flowrate in cc/min. from the Hastings flow meter's LCD inside the Hoffman termination enclosure of the PVER skid, or key in "DISP OP,"

                                     "11", "DISP" on the NR skid's LRP keypad and read RE-28's (left most)

LED display for RE-87's flowrate (in liters/min).

n. Check that RF-87B's (or A's) filter light goes out and that RF-87A's (or B's) light comes on again.

o. Mate the RF-87B (or A) filter carrier cask up to its filter holder.

p. Lift the pin on the top rear of the filter holder.

q. Screw the extractor bar through the carrier cask and into the threads of the filter ingot of the RF-87B (or A) filter holder.

r. Push down on the filter holder's orange handle on the top rear of

                                   -RF-87B's (or A's) filter holder.

s. Using the extractor bar transfer the filter ingot from the filter holder into the carrier cask.

t. Push the carrier cask's pin (on front of cask) into the slot of the ingot to hold ingot in place while transporting.

u. Unscrew the extractor bar and place beside RF-87A's (or B's) filter holder.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER , EPRB-12 DIABLO CANYON POWER PLANT REVISION!" 7 PAGE 20 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

v. Survey the carrier cask with the hand-held meter. The dose rate should be less than 0.4 R/hr at 1 foot from contact. If greater, inform the Site Chemistry Coordinator and obtain further instructions.

w. Lift RF-87B's (or A's) carrier cask and place in the transport dolly.

x. Proceed to the TSC with the dolly and cask along the route shown in Figure 1 (Attachment 11.4).

y. Unload the cask into the TSC's transfer cage with the restrained end pointing outward.

z. Transfer any sample collection data onto Form 69-13224.

aa. For radionuclide analysis instructions proceed to step 6.2.3 unless directed otherwise by the Site Chemistry Coordinator to repeat the instructions of 6.2.2. 6.2.3 TSC Analysis of the RF-87's Sample Cartridge

a. Mate the carrier cask up flush against the modified carrier cask which already resides in the transfer cage ensuring that the unrestrained end meets the unrestrained end of the modified carrier cask.

b. Ensure the small shield plug is in the top of the modified carrier cask.

C. Lift the carrier cask's retaining pin.

d. Using the TSC's extractor bar or the push stick, push the ingot into the modified carrier cask.

NOTE: The cask might have to be rotated slightly to facilitate ingot transfer.

e. Insert the ingot retaining pin into the modified carrier cask.

f. Lift the carrier cask out of the transfer cage and give it to the personnel retrieving the samples from the PV Skid Room along with the extra ingot, cartridge, filter and 0-rings.

g. Lift the modified carrier cask out of the transfer cage and set it on the floor leaving the large shield plug aside.

h. Place the TSC's survey meter: first, in contact centered on top of the modified carrier cask; then one foot above it after lifting (temporarily) the small shield plug.

i. Record the readings and replace the small shield plug.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 21 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

j. Select the best collimating aperture out of the five from the following table based on the contact exposure reading or the 1 foot above (with the small shield plug removed) exposure reading.

Open Cask (small plug Closed Cask (small plug Use Collimating removed) 1' above Reading in place) Contact Reading Aperture, "d" less than 32 mR/hr less than to 2.0 mR/hr 3/4" 32 mR/hr to 640 mR/hr 2.0 mR/hr to 45 mR/hr 1/4" 640 mRlhr to 8 R/hr 45 mR/hr to 560 mR/hr 1/8" 8 R/hr to 200 R/hr 560 mR/hr to 14 R/hr 1/16" greater than 200 R/hr greater than 14 R/hr 1/32"

k. Remove the lead plug (same size as a collimating aperture but without the hole) from the center of the GE detector's shield doors.

1. Insert the collimating aperture selected from step 6.2.3j into the vacated hole in the GE detector shield doors.

CAUTION: The modified carrier cask weighs approximately 55 lbs and may require 2 TSC personnel to provide the lifting.

m. Lift the modified carrier cask containing the ingot with the hot cartridge and place on top of the GE detector shield doors.

CAUTION: Steps 6.2.3n through 6.2.3o must be performed quickly and at arms length away from the body and face, since the highly radioactive sample cartridge is momentarily exposed while only partially shielded.

n. Remove the small shield plug and flip the modified carrier cask upside down and over the collimating aperture.

o. Place the large shield plug in the bottom cavity of the modified carrier cask.

p. If the collimating aperture is out of range based on the Canberra's count rate meter or dead time meter, then lift the modified carrier cask off of the collimating aperture and place to one side of the GE detector's shield doors. Immediately, reselect the next larger or smaller aperture, replace the modified carrier cask over it and continue.

q. Commence the radionuclide analysis using the Canberra System as per procedures CAP B-53 and CAP B-53:I.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 22 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

r. For each cartridge sampled, ehter the following data as inputs in the Canberra program as extracted from Sample Collection Data:

1. Sample Description (from Form 69-13224)

(i.e., RF-87A or B, Cartridge #, etc.)

2. Sample start date/time (from Form 69-13224)

3. Sample stop date/time (from Form 69-13224)

4. Sample flowrate, F(lpm) (from Form 69-13224)

5. Collection factor (includes plate-out and cartridge retention combined) CF depending on sample flowrate, from the following table:

Sample Flowrate Collection Factor, CF nearest to 1 1pm 0.724 nearest to 0.79 Ipm 0.678 nearest to 0.51 1pm 0.568 nearest to 0.41 1pm 0.508

6. Collimating aperture Geometry Code used, (i.e., "d").

CAUTION: High noble gas concentrations trapped in the cartridge may interfere with the resolution of iodine peaks. The cartridge may require a reverse purge using air or nitrogen. A minimum purge volume of 18 liters is needed to reduce the entrained gas concentration.

s. All results concerning high range iodine and particulate concentrations as determined by this procedure should be reviewed by the Site Chemistry Coordinator and should be communicated as soon as possible to the ERA's staff in the TSC.

t. At the end of the Canberra analysis remove the large shield plug, flip modified carrier cask over, restore small shield plug, and lift modified carrier cask off and onto the floor near the shielded radioactive sample storage pig at the Northeast entrance area of the TSC lab.

u. Lift the pin retaining the ingot.

EP RB-12037DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 23 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions CAUTION: Steps 6.2.3v through 6.2.3z expose the iodine cartridge momentarily. This may cause a very High Radiation Area. Good ALARA practices are important.

v. Using the extractor bar or the push stick, push the ingot out of the modified carrier cask.

w. Lift the ingot to the edge of the shielded sample storage pig.

x. Using the push stick, push the iodine cartridge and particulate filter out of the ingot (even the O-rings) and into an opened pre-labeled bag that is in the radioactive sample storage pig. Then cover the sample storage pig.

y. Return the modified carrier cask to the transfer cage with the unrestrained end pointing outward.

z. Wipe the push stick and ingot clean; check the wipe for contamination, set the ingot (this becomes the extra ingot) aside with new O-rings, cartridge, and filter for use by the personnel collecting the samples.

aa. Report to the Site Chemistry Coordinator for continued instructions. 6.3 Method For Plant Vent High Range Iodine Sampling Using RF-24R Cartridge 6.3.1 RF-24R - Initial Collection NOTE: Arrival here is either external because of RF-87A&B being un-available (i.e., RE-87 pump O.O.S., Bus "G" down, SCC preferred selection, etc.) or internal from instructional step 6.1.3.

a. Obtain from Control Room or SCC (or TSC Rad. Data Processor) and record on Form 69-13225 the following:

                                    *1. Time of NR to ER "switchover" (i.e., isolation of NR and RNR skids) Er time RNR skid pump was last shut off (if arriving here from step 6.1).

2. Last known sample flowrate through RNR skid.

3. Estimate of time RE-24R began viewing this last increased level of iodine or time RNR skid pump was last cycled on (if arriving here from step 6.1).

4. Cartridge # (if arriving here from step 6.1) OTHERWISE write cartridge #0.

5. Reading of RE-34 (As read on RR-34 on PAM panel.)

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PACIFIC GAS AND ELECTRIC COMPANY NIJMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 24 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

b. Obtain dose rate meter to check radiation levels enroute to and at the PV skid room.

C. Obtain a set of keys from the Chemistry Foreman's office to operate the RNR skid's LRP panel.

d. Obtain any special instructions, precautions, or controls from the SCC and SRPC.

e. Proceed expeditiously to the PV skid room (85' level -- "L" area) upon receiving clearance from the SCC.

f. Check RE-34's remote readout Oust outside the door) prior to entering the PV skid room.

NOTE: The next two steps apply to arriving here externally wherein the RNR skid has not vet been un-isolated and the NR to ER "switchover" has not been over-ridden. They do not apply to arriving here from step 6.1.

g. Approach the termination enclosure (Panel BTR-P 14) at the end of the LRP on the NR skid in the PV skid room. (Applies only if arrival here is not from step 6.1).

h. Turn the switch labeled "RE-87/SS" from "RE87 Norm-OFF" position to the "ER Calib'n- ON" position. This overrides the PVER switchover and removes isolation of the RNR skid. (Applies only if arrival here is not from step 6.1.)

i. Insert a key in the RNR skid's LRP panel Control Mode keyswitch and turn it to LOCAL in order to operate the skid locally.

j. Insert the other key in the RNR skid's LRP panel program mode keyswitch and turn it to ENTER DATA in order to key in for sample flowrate readings.

NOTE: The spare RF-24R cartridge "holder/shield plug" assembly may not be available in the PV skid room. In this case, the one kept in the I&C Training Lab must be retrieved before proceeding with the next step.

k. Fit the spare RF-24R cartridge "holder/plug" assembly with a fresh 2" Ag-Zeolite iodine cartridge and lay beside RE-24R.

1. Loosen the four wing bolts retaining the existing "holder/plug" assembly in RE-24R's detection chamber on the RNR skid.

m. Rotate the "holder/plug" assembly counterclockwise in RE-24R's detection chamber until the slotted ears clear the wing bolts.

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PACIFIC GAS AND ELECTRIC COMPANY NUM13ER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 25 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions NOTE: The RF-24R carrier cask used in the next step may be stored in the TSC lab instead of the PV skid room. In this case, it must be retrieved before proceeding with the next step.

n. Pull the entire "holder/plug" assembly containing the existing RF-24R iodine cartridge out of RE-24R's detection chamber and place it, very quickly, in the RF-24R carrier cask (which is sitting in the transport dolly).

o. Slide the spare RF-24R "holder/plug" assembly containing the fresh iodine cartridge into RE-24R's chamber and turn clockwise until the slotted ears engage the wing b6lts.

p. Tighten the wing bolts with fingers only.

q. Push the ISkid Pump] button on the RNR LRP panel to start the skid's sample pump.

r. Record the start/sample time on Form 69-13225 for this, the next sequential cartridge number (which will be cartridge #1 if arrival here is not from step 6.1).

s. Key in on the RNR LRP keypad the following:

I. "DISP OP"

2. "12"

3. "DISP" This gives the RNR skid sample flowrate (cfm) displayed in the left most LED (i.e., the RE-28R - particulate window).

t. Read and record the beginning sample flowrate on Form 69-13225 for this new sampling cartridge.

u. Proceed to the TSC Lab with the dolly and cask along the route shown in Figure 1 (Attachment 11.4).

v. Unload the cask with RF-24R to the TSC counting personnel.

w. Go to step 6.3.2 but wait for Continued Collection directions from the SCC.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 26 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions 6.3.2 RF-24R - Continued Collection

a. Proceed expeditiously to the PV skid room with the spare RD-24R "holder/plug" assembly containing the fresh Ag-Zeolite iodine cartridge furnished by TSC personnel, if the SCC directs that sample collection be continued.

b. Check RE-34's remote readout prior to entering the PV skid room.

NOTE: The keys were left in the RNR's LRP panel with LOCAL control and ENTER DATA program mode still selected; the skid's sample pump still running; and the left most LED (RE-28R window) still reading skid sample flowrate. C. Read and record the ending sample flowrate on the Form 69-13225 (from the previous trip to the PV skid room) relating to the existing RF-24R in RE-24R's chamber.

d. Push the "skid pump" button on the RNR LRP panel to STOP the skid's sample pump.

e. Record the stop/sample time on the same Form 69-13225 relating to the cartridge still in RE-24R's chamber.

f. Remove the spare RF-24R "holder/plug" assembly (containing the fresh iodine cartridge) from the RF-24R carrier cask (in the transport dolly) and lay beside RE-24R.

g. Loosen the four wing bolts retaining the existing "holder/plug" assembly in RE-24R's chamber.

h. Rotate the "holder/plug" assembly counterclockwise in RE-24R's chamber so the slotted ears clear the wing bolts.

i. Pull the entire "holder/plug" assembly containing the spent RF-24R iodine cartridge out of RE-24R's chamber and quickly place it in the RF-24R carrier cask.

j. Slide the spare RF-24R "holder/plug" assembly containing the new iodine cartridge into RE-24R's chamber and turn clockwise until the slotted ears engage the wing bolts.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 27 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

k. Tighten the wing bolts with fingers only.

1. Push the FSkid Pump] button on the RNR LRP panel to START the skid's sample pump.

m. Read and record on a new Form 69-13225 the beginning sample flowrate for this new cartridge from the RNR's LRP left most LED (RE -28R -

particulate window.)

n. Record the sample/start time on this new Form 69-13225 for this sequentially next cartridge (now in RE-24R).

o. Return to the TSC Lab with the dolly, cask containing the spent RF-24R, and data sheets for turnover to TSC personnel and await SCC directions to return to Step a. and continue collection.

6.3.3 TSC AnalysisT of the RF-24R Sample Cartridge

a. Obtain from the Site Chemistry Coordinator (or PV sampling personnel) for each cartridge the following RF-24R sample information:

1. Sample collection start date/time.

2. Sample collection stop date/time.

3. Sample collection flowrates (default = 2.0 CFM)

b. Using the hand-held survey meter, obtain a contact dose rate measurement at the bottom of the carrier cask (opposite of the side with the handle) with the small lead shield plug in place.

c. Transfer this information onto Form 69-13225.

d. Select the initial collimating aperture based on the reading obtained from step 6.3.3c. above using the following table:

Contact Readin2 of the Use Collimating Bottom of the Hand-held Pi Aperture, "d" less than 0.2 mR/hr 3/4" 0.2 mR/hr to 2 mR/hr 1/4" 2 mRnhr to 22 mR/hr 1/8" 22 mRhr to 220 mRJhr 1/16" greater than 220 mR/hr 1/32"

e. Remove the lead plug (same size as a collimating aperture but without the hole) from the center of the GE detector's shield door.

f. Insert the collimating aperture selected from step 6.3.3d. into the vacated hole of the GE detector's shield doors.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER . EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 28 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions CAUTION: Steps 6.3.3g thru 6.3.3k can cause a Very High Radiation Exposure. Keep the exposed cavity on the bottom of RF-24R carrier cask pointed away from the body and extremities.

g. Lift the RF-24R carrier cask containing RF-24R and its entire "holder/lead plug" assembly out of the transport dolly and up on the GE detector's shield doors.

h. Leave behind (in the dolly) the small shield plug covering the bottom cavity of the RF-24R carrier cask.

i. Quickly but carefully, place the RF-24R carrier cask with "holder/lead plug" assembly cavity side down and centered, on top of the collimating aperture on the GE detector's shield doors.

j. If the collimating aperture is out of range based on the Canberra's count rate meter or dead time meter reading on RF-24R, lift the carrier cask off of the aperture and place to one side on the GE detector's shield doors.

Immediately, reselect the next larger or smaller aperture. Replace the carrier cask with RF-24R centered over the new aperture then continue.

k. Commence the radionuclide analysis using the Canberra System as per procedures CAP B-53 and CAP B-53:I.

1. For each cartridge sampled, enter the following data as inputs in the Canberra program as extracted from the Sample Collection Data:

I. Sample Description (from Form 69-13225) (i.e., cartridge #, etc.)

2. Sample start date/time (from Form 69-13225)

3. Sample stop date/time (from Form 69-13225)

4. Sample flowrate (CFM) (from Form 69-13225)

(e.g., default 2.0 cfm)

5. Sample collection factor, 0.92 (includes plate-out and cartridge retention factors combined) depending on the sample flowrate.

6. Collimating aperture Geometry code used (i.e.,"d").

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 29 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions CAUTION: High noble gas concentrations trapped in the cartridge may interfere with the resolution of iodine peaks. The cartridge may require a reverse purge using air or nitrogen. A minimum purge volume of 18 liters is needed to reduce the entrained gas concentration.

m. All results concerning the high range iodine concentrations as determined by this procedure should be reviewed by the Site Chemistry Coordinator and should be communicated as soon as possible (not more than 10 minutes after the start of analysis) to the ERA's staff in the TSC.

CAUTION: Steps 6.3.3n. thru 6.3.3t. can cause Very High Radiation Exposure. Keep the exposed cavity of the hand-held pig pointed away from the body and extremities.

n. At the end of the Canberra Analysis perform the following:

I. Lift the RF-24R carrier cask with the "holder/lead plug" assembly off the GE detector's aperture and shield doors and place back in the transport dolly down over the small shield plug.

2. Rotate carefully counterclockwise the RF-24R "holder/lead plug" assembly by its handle in the carrier cask until the protruding lug of the "holder/lead plug's" end cap engages the slot in the small shield plug in the transport dolly.

3. Continue to rotate counterclockwise after the engagement until the "holder/lead plug's" end cap is loosened allowing easy removal of RF-24R.

o. Open the top of the radioactive sample storage pig at the Northeast entrance area of the TSC Lab.

p. Lift quickly the RF-24R "holder/lead plug" assembly out of the RF-24R carrier cask and transport dolly and place on the edge of the storage pig with the "holder's end cap" facing out and upward (but away from your face).

q. Grasp the RF-24R "holder end cap" with the RF-24R cartridge holder cap grip/removal tool keeping a handle's distance away from the end cap.

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r. Rotate counterclockwise with the handle until the "holder end cap" and RF-24R are free of the lead plug assembly.

s. Using the push stick, push the RF-24R cartridge out of the "holder end cap" and down into the storage pig.

t. Replace cover over the storage pig.

u. Wipe all tools and the RF-24R "holder end cap" assembly, decontaminating if necessary.

v. Reassemble the RF-24R "holder/lead plug" assembly with a fresh cartridge placed in the end cap and turn over along with the transport dolly to the personnel collecting samples.

w. Report to the SCC with the sample analysis results and for continued instructions.

7. ACCEPTANCE CRITERIA Satisfactory performance of data collection by procedural steps.

8. REFERENCES 8.1 CAP B-53, "Gamma Spectroscopy System Equipment (Canberra PROcount System)"

8.2 CAP B-53:I, "Gamma Spectroscopy System (PROCount Technician Software Operation)" 8.3 CAP E-19, "Routine Plant Vent Radioactive Effluent Sampling" 8.4 EP EF-1, "Activation and Operation of the Technical Support Center" 8.5 EP G-1, "Emergency Classification and Emergency Plan Activation" 8.6 EP RB-2, "Emergency Exposure Guides" 8.7 EP RB-9, "Calculation of Release Rate" 8.8 Diablo Canyon Power Plant Unit I and 2 Emergency Plan 8.9 Regulatory Guide 1.97, "Instrumentation for Light - Water Cooled Nuclear Power Plants to Access Plant and Environs Conditions During and Following an Accident" 8.10 Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors" 8.11 Regulatory and Technical Basis and recommended response to AR A0489282 arid A0489299, Henry Fong, 2/29/2000 8.12 NUREG-0737, "Clarification of TMI Action Plan Requirements" 8.13 General Design Criteria 19 EP-RB-12u~07DOC 03B 1021.1031 12.0

PACIFIC GAS AlND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 31 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions

9. RECORDS Data Sheets and records will be maintained in the Records Management System (RMS) in accordance with AD I 0.ID 1.

10. APPENDICES 10.1 Figure 3, RE-87 Response Curve 10.2 Figure 4 and Figure 5, RE-29 Response Curves

11. ATTACHMENTS 11.1 Form 69-13224, "RF-87A or B Sample Collection Data Sheet," 05/13/93 11.2 Form 69-13226, "RE-24R'RE-28R Monitor Data Sheet," 10/07/93 11.3 Form 69-13225, "RF-24R Sample Collection Data Sheet," 11/25/93 11.4 "Figure 1, Route Map," 08/22/00 11.5 "Figure 2, NR/PVER LRP/RDU Panel of Button Switches and Keypad," 08/22/00 11.6 "Figure 6, Plant Vent Radiation Monitor Ranges," 08/22/00 11.7 "Figure 7, Source of Power to Sampling Skids," 08/22/00 EP-RB-12u3r07.DOC 03B 1021.1031 12.0

PACIFIC GAS AND ELECTRIC COM[PANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 32 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions APPENDIX 10.1 RE-87 Response Curve Figure 3 I 00E 000 E fie c tie A ge Hr s 120 40 - 80 Soo Amps per 1.00E-09 I41 - --L - - - -- if oc 1ic C

~Y Yf:

W7 4-Ml 3: 3- - 1.00E -10 0.1 10 100 1000 Time After Shutdown, Hrs T:G R A PH IC S %00 2833 03 EP RB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 33 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS I AND 2 Accident Conditions APPENDIX 10.2 RE-29 Response Curves Figure 4 1.00E- 04 1 .00E 03 m RIHr per 1.00F- 02 DC I/c O 1.002. 01 I OOE* 00 0.1 10 100 1000 Time After Shutdown. Hrs EPRB-12u3r07.DOC 03B 1021.1031

PACIFIC GAS AND ELECTRIC COM[PANY NUM[BER EP RB-12 DIABLO CANYON POWER PLANT REVISION 7 PAGE 34 OF 34 TITLE: Plant Vent Iodine and Particulate Sampling During UNITS 1 AND 2 Accident Conditions APPENDIX 10.2 (continued) Figure 5 106 10

     *o .L                                                                              104 a) 1031 CO 00 0-.

10-1 ) g= 102

102 0E 10 0

Swo C)¢ 10 1 100 Iii e-.- -

    *- C SE" 10-4 107      106      105      10 4 103      102    101 10o 10-D Net Gross Gamma Monitor Response, Net ER (mR/hr)

EPRB-12u3r07.DOC 03B 1021.1031

69-13224 05/13/93 Page I of I DIABLO CANYON POWER PLANT TITLE: EP RB-12 ATTACHMENT 11. 1 RF-87A or B Sample Collection Data Sheet I1AN2 Unit No.: Performed by: Date/Time NR Switched over to PVER: / Initial RE-34 Reading (near time of switch): mR/hr Initial RE-87 Reading (near time of switch): _iCi/cc Initial RF-87 Sample Flowrate: Ipm or cc/min (circle one) Initial Sampling Started with RF-87A or RF-87B (circle one) Cartridge No.: RF-87A or RF-87B (circle one) Sample Flowrate: lpm (1000 cc/min equals 1 lpm) Filter Collection Start Date/Time: / Filter C611ection Stop Date/Time: / Cask Dose Rate: Method Used: A or B (circle one) Method A: Contact Dose Rate Reading of Closed Cask (small lead plug in place) Method B: 1 foot Dose Rate Reading of Open Cask (small lead plug removed) Cartridge No.: RF-87A or RF-87B (circle one) Sample Flowrate: _ _ lpm (1000 cc/min equals 1 1pm) Filter Collection Start Date/Time: / Filter Collection Stop Date/Time: / Cask Dose Rate: Method Used: A or B (circle one) Method A: Contact Dose Rate Reading of Closed Cask (small lead plug in place) Method B: 1 foot Dose Rate Reading of Open Cask (small lead plug removed) Reviewed By: Date: Site Chemistry Coordinator or designee EP RB-12u3r07.DOC 03B 1021.1031

69-13226 10/07/93 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 ATTACHMENT 11.2 1JO2 TITLE: RE-24R/RE-28R Monitor Data Sheet Unit No.: Date/Time NR. to PVER Switchover / Initial RE-34 Reading _ mR/hr (i.e., near switchover) Initial RE-14R Reading _ ptCi/cc (i.e., near switchover) Initial RE-87 Reading (if available) _ .tCilcc (i.e., near switchover) Previous sample flowrate (if available) _ cfm (i.e., near switchover) Previous RE-24R reading gCi/cc (prior to but near switchover) Previous RE-28R reading_ gCi/cc (prior to but near switchover) Initial Raw Countrate Reading by RE-24R (prior to but near switchover) (i.e., "DISP OP"1, "3", "DISP" cpm (if applicable) Cartridge # Iteration # on this cartridge (if applicable)

a. RE-24R Start CPM _ _cpm e. Skid pump stop time

("DISP OP", "3", "DISP") (hr) : (min)

b. Skid pump start time f. RE-24R Stop CPM cpm

("DISP OP", "31","DISP") (hr) : (min)

c. RE-24R reading in piCi/cc g. CR- I{}e, {f)}-{a}

                                                                                 -{b.} =               cpm/min (if applicable)

d. Sample Flowrate cfm h. RE-34 Reading mR/hr RE-28R reading in i-tCi/cc (if applicable)

Filter # Cartridge # Iteration # on this cartridge (if applicable)

a. RE-24R Start CPM cpm e. Skid pump stop time

("DISP OP", "3T', "DISP") (hr) : (min)

b. Skid pump start time f. RE-24R Stop CPM cpm (hr) : (min) ("DISP OP", "3", "DISP")

c. RE-24R reading in jtCi/cc cpm/min

g. CR= {f'}-{a) =

(if applicable) {e,} -{b.}

d. Sample Flowrate cfm h. RE-34 Reading mR/hr RE-28R reading in gCi/cc (if applicable)

Filter # EPRB-12u3r07.DOC 03B 1021.1031

69-13225 11/25/93 Page I of I DIABLO CANYON POWER PLANT EP RB-12 ATTACHMENT 11.3 AN2 TITLE: RF-24R Sample Collection Data Sheet Unit No. Performed by: Initial RE-34 Dose Rate Reading: Date/Time: NR to PVER Switchover: Date/Time / Increase in iodine activity prior to switchover: Date/Time Cartridge No.: RE-34

1. Begin Sample Flow: cfm 2. End Sample Flow: eCfim Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: / Average Sample Flowrate = 12-} _fm c1.)+(default value equals 2.0 cfm) 2 Cask dose rate (bottom side) Cartridge No.: RE-34

1. Begin Sample Flow: cfm 2. End Sample Flow: cfm Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: / Average Sample Flowrate = + f2.f _em c1.) (default value equals 2.0 cfm) 2 Cask dose rate (bottom side) Cartridge No.: RE-34

1. Begin Sample Flow: cfm 2. End Sample Flow: cfm Filter Collection Start Date/Time: /

Filter Collection Stop Date/Time: / Average Sample Flowrate = (1.)+ 2.) cfm (default value equals 2.0 cfm) 2 Cask dose rate (bottom side) Reviewed By: Date: Site Chemistry Coordinator or designee EPRB-12u3r07.DOC 03B 1021.1031

Page 1 of 1 DIABLO CANYON POWER PLANT Figre01/Roue/Ma 1 AM TITLE EP RB-12 ATTACHMENT 11.4 AND ld TITLE: Figure 1, Route Map

                                                                    .3  .3       .3  -  .3  .i.3..A.3.3           .3  2       .3      J3   a 2 o0jmPJhr 5

2160mR/hr~ 1700 mR~r 1700 mR/hr MAXIMUMPREDICTED DOSE RATES (mRAnr)AT 1 HOUR POST LOCA NOTE: EXPOSURE RATES SHOWN FOR UNIT 1 ACCIDENT FOR UNIT 2 ACCIDENT USE MIRROR IMAGE OF UNIT 1 EPRB-12u3r07.DOC 03B 1021.1031

08/22/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 1 A91%k ATTACHMENT 11.5 AND 2 TITLE: Figure 2, NR/PVER LRP/RDU Panel of Button Switches and Keypad RM-28/25R RM-24/24R RM-14/14R RN-87(on NR) PARTICULATE IODINE GAS r-RADIATON-1

                     --RADIATION--           V RADIATION-1                               STATUS
                                                                                                     --~2"TBflmI nO Inn 0

0M1I E137 4 n15 0

                                                                                                             "-1-1n
                        -.              4         -.             I--

oK°A A SI "3

                                                                                                   ,    2 Ro        in, NOT ON

4o a

RNR SKID

4 emu pm L ____________ .1____________
NOTE: ALL PERIPHERAL INFORMATION ON: CHANNELS, FUNCTIONSP AND DATA ARE READ IN THE LEFT MOST LED (NAMELY THE 'PARTICULATE' WINDOW)

EP-RB-12u3r07.DOC 03B 1021.1031

08/22/00 Page 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 ATTACHMENT 11.6 1ld2 TITLE: Figure 6, Plant Vent Radiation Monitor Ranges MOI-,1TOR RANGES EFFLUENT TYPE NORMAL MIDRANGE HIGH RANGE RE 14/14R NOBLE GAS L...... RE-87 RE-229 RE 241/24P RADIOIOESINES RX '10 (Gro:b Sc-mng.I.) Useu -0,Ip'don T-l F:F 37 AID3 (t0nL s,impI-,) Us~eful rnnv. de*isrn nn RE 23/23R I'AIRICULATES RX 40 (Czreb sornpIr) Us~eful ronc~l depends on Tuii RI' 87 A/B (Grob. stimpIer) Us~eful eiiiqe cIfpncls Il EFFLUE14TCOI1CEIJTRATIC'14 ( /.ci/cc) EPl_R1-12u3r07.DOC 03B 1021.1031

08/22/00 Pagc 1 of 1 DIABLO CANYON POWER PLANT EP RB-12 ATTACHMENT 11.7 AND TITLE: Figure 7, Source of Power to Sampling Skids r~rom Meso Sub station

                                                                                                                      ' 230 - KV Swiych-Syard V. SKIDS    2I10/120v ,Eo

LLIOVP rv1RE 4 P -1 FgR)__4a0j 2L40ý/1:20V RE -24R P4,0 RE-14

                                        -%mlr(RF-24R)                          RE-2                    RE-S7 rE-23                  ER  RF-37A/B)       00233308 EPRB-12u3r07.DOC  03B         1021.1031

*** ISSUED FOR USE BY:                                  DATE:                    EXPIRES:____

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14A NUCLEAR POWER GENERATION REVISION 1A DIABLO CANYON POWER PLANT PAGE 1 OF 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Initial Detection of Core Damage 1 2 EFFENUIVh DATE PROCEDURE CLASSIFICATION: QUALITY RELATED I1. SCOPE 1.1 This procedure provides guidance to be used for assessment of fuel damage using installed plant instrumentation for the purposes of event classification. 1.2 EP RB-14, "Core Damage Assessment Procedure," provides guidance for detailed assessments of post accident core damage.

2. DISCUSSION 2.1 Initial indication of fuel damage can be determined by measuring the external radiation dose rate at a distance of one (1) foot from the center of the letdown line in the letdown heat exchanger room with letdown in service. See Attachment 7.1 for dose rate measurement requirements.

2.1.1 An external radiation dose rate exceeding 3 R/hr indicates fuel clad degradation greater than Technical Specification allowable limits, and would meet UNUSUAL EVENT SU5.1 classification requirements. 2.1.2 An external radiation dose rate exceeding 15 R/hr indicates Fuel Clad Barrier Loss. EP G-1 Table F-1, Fuel Cladding Barrier Loss Item C.4 would require entry into at least ALERT FAI .1. 2.2 In the special case of a steam generator tube rupture (SGTR) with a monitored steam release, indication of fuel damage can be determined by a sudden increase on the main steam line monitor reading (RM-71 to RM-74) to greater than 50,000 cpm, along with a notable increase in dose rate on the containment low range monitor (RM-2) due to RCS piping shine. Fission Product Barrier EALs, Table F-1, D, 5 in the Fuel Cladding Barrier column would be met, and would require entry into at least SITE AREA EMERGENCY FS1.1. 2.3 Initial indication of fuel damage during a LOCA can be determined by RM-30 or RM-31 reading >20 R/hr. EP G-1 Table F-I, Fuel Cladding Barrier Loss Item C.3 would require entry into at least ALERT FA1.1. 2.4 RM-30 or RM-31 reading >80 R/hr meets the criteria for Containment Barrier Potential Loss due to fuel damage. EP G-1 Table F-I, Containment Barrier Potential Loss Item C.4 would require entry into at least SITE AREA EMERGENCY FS 1.1.

3. RESPONSIBILITIES 3.1 The Shift Manager is responsible for the implementation of this procedure until the TSC or EOF is activated.

3.2. Once the TSC is activated, the TSC Reactor Engineer is responsible for the implementation of this procedure. EPRB-14Au3rO1.DOC 03B 1006.1153

t PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14A DIABLO CANYON POWER PLANT REVISION 1A -, PAGE 2 OF 3 TITLE: Initial Detection of Core Damage UNITS 1 AND 2

4. INSTRUCTIONS 4.1 IF fuel damage is suspected, AND CVCS letdown is in service, THEN perform the following:

4.1.1 Contact RP and instruct them to implement Survey and Posting Guide, SPG-1 1, "Obtaining the EP RB-14A Dose Rate". 4.1.2 Record the dose rate reported by radiation protection (RP) at the "RB-14A Dose Rate Point" in the Letdown Heat Exchanger Room. R/hr 4.1.3 IF dose rate above is greater than 15R/hr, THEN classify the event per EP G-1 Table F-I, with Fuel Cladding Barrier Loss Item C.4 met. 4.1.4 IF dose rate above is greater than 3R/hr, THEN classify the event per EP G-1 UNUSUAL EVENT SU5.1. 4.2 IF a SGTR is in progress, AND the affected S/G is releasing steam (faulted or used for cooldown), AND. greater than 5 minutes has elapsed since reactor shutdown, THEN perform the following: 4.2.1 Monitor affected S/G Steamline Radiation Monitor RM-71, RM-72, RM-73 or RM-74. 4.2.2 IF affected Steamline Radiation Monitor countrate is greater than 50,000 counts, AND RM-2 dose rate has a notable increase, THEN classify the event per EP G-1 Table F-i, with Fuel Cladding Barrier Loss Item D.5 met. 4.3 RM-30 and RM-3 1, high range containment radiation monitors, should be monitored for indication of fuel damage when ever the potential for fuel damage exists. 4.3.1 IF RM-30 or RM-31 dose rate is greater than 6 R/hr, THEN classify the event per EP G-I Table F-1, with Reactor Coolant Barrier Loss Item C.1 met. 4.3.2 IF RM-30 or RM-3 ldose rate is greater than 20 R/hr, THEN classify the event per EP G- I Table F-I, with Fuel Cladding Barrier Loss Item C.3 met. 4.3.3 IF RM-30 or RM-3 ldose rate is greater than 80 R/hr, THEN classify the event per EP G-1 Table F-i, with Containment Barrier Potential Loss Item C.4 met. EPPB-14Au3r1DOC 03B 1006.1153

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP RB-14A D/AILO CANYON POWER PLANT REVISION 1A PAGE 3 OF 3 TITLE: Initial Detection of Core Damage UNITS 1 AND 2

5. REFERENCES 5.1 PG&E Calculation EP-95-02, Rev. 0.

5.2 EP RB-14. "Core Damage Assessment Procedure"

6. APPENDICES None

7. ATTACHMENTS 7.1 "Initial Detection of Fuel Damage - RCS Letdown," 06/02/08 EP.RB-14Au3rO1.DOC 03B 1006.1153

06/02/08 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE: EP RB-14A ATTACHMENT 7.1 Initial Detection of Fuel Damage - RCS Letdown I1AN2 Measure and record the external radiation level one (1) foot from the center of line S 1-26-211IP, using survey and posting guide SPG-1 1, "Obtaining the EP RB-14A Dose Rate." An external radiation dose rate exceeding 3 R/hr indicates fuel damage (reactor coolant activity >60 uCilcc DEI-13 1), meeting emergency action level (EAL) SU5. 1. An external radiation dose rate exceeding 15 R/hr indicates fuel damage (reactor coolant activity > 300 uCi/g DEI-131), meeting the need to evaluate for FA1.1, FS1.1 or FGI.1 emergency action level (EAL) criterion. EP.RB-14Au3rO0.DOC 03B 1006.1153

  ***ISSUED FOR USE BY:                                                                     DATE:                                     EXPIRES:______

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-1 NUCLEAR POWER GENERATION REVISION 35 DIABLO CANYON POWER PLANT PAGE 1 OF 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Activatior aand Operation of the Technical Support Center I EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE SC O PE ............................................................................................................................................................... I D ISCU SSIO N .................................................................................................................................................... 1 RE SPO NSIB IL ITIE S ......................................................................................................................................... I IN STRU C TION S ............................................................................................................................................... 3 R E C O RD S ......................................................................................................................................................... 3 ATTA CHM EN TS ............................................................................................................................................. 4 REFEREN CES .................................................................................................................................................. 5

1. SCOPE 1.1 This procedure specifies Technical Support Center (TSC) actions during a declared emergency.

2. DISCUSSION 2.1 The TSC provides an on-site location, independent of the control room, for overall coordination of the on-site emergency response. The TSC staff supports the control room, diagnoses plant conditions, recommends corrective actions, and coordinates site emergency activities.

2.2 The combined maximum occupancy limit for the TSC and OSC is posted at the TSC entry door and the OSC 104' turbine building entry door.

3. RESPONSIBILITIES 3.1 Site Emergency Coordinator (SEC)

Assigns overall command and control of the emergency response effort. Prior to activation of the EOF with the Recovery Manager in command and control, the SEC is responsible for on-site emergency management. 3.1.1 Prior to EOF activation with the Recovery Manager in command and control, the SEC shall:

a. Declare emergency classifications.

b. Recommend protective actions to off-site authorities.

c. Direct assembly and accountability.

d. Authorize extraordinary emergency measures such as emergency response personnel exceeding Annual Administrative Exposure Limits.

EPEF-1u3r35.DOC 03B 1015.0933

PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP EF-71 DIABLO CANYON POWER PLANT REVISION 35 PAGE 2 OF 5 TITLE: Activation and Operation of the Technical Support Center UNITS 1 AND 2

e. Authorize KI administration to on-site personnel until relieved by the Recovery Manager.

f. Provide direction for emergency response operations.

g. Authorize site access for non-plant personnel.

h. Maintain liaison with off-site authorities.

i. Develop a recovery action plan.

j. Approve information for news releases.

k. Ensure County and State notifications.

3.2 Assistant Site Emergency Coordinator (ASEC) 3.2.1 Assists the SEC with plant conditions assessment and TSC coordination. 3.3 Liaison Advisor (LA)

3.3.1 Coordinates

a. Off-site notifications (prior to EOF activation).

b. Emergency response staff notifications.

c. Contact of on-site and off-site emergency support groups.

3.4 Engineering Advisor (EA) 3.4.1 Coordinates plant technical support. 3.4.2 Evaluates event safety consequences. 3.5 Electrical Engineer 3.5.1 Provides plant electrical equipment status. 3.6 Radiological Advisor (RA) 3.6.1 Coordinates emergency radiological response effort. 3.7 Radio Operator 3.7.1 Provides instructions to the on-site radiological field monitoring teams. 3.8, Radiological Data Processor (RDP) 3.8.1 Enables TSC radiation monitors and verifies habitability. 3.8.2 Trends radiation levels in the plant. 3.8.3 Serves as primary contact for Site RP Coordinator in the OSC. 3.8.4 Receives EARS dose calculations from UDAC for on-site FMT data comparison and FMT guidance. EPEF-1u3r35.DOC 03B 1015.0933

PA,ýdIICGAS AND ELECTRIC COMPANY NUMBER EP EF-1 DIABLO CANYON POWER PLANT REVISION 35 PAGE 3 OF 5 TITLE: Activation and Operation of the Technical Support Center UNITS 1 AND 2 3.9 Liaison Assistants 3.9.1 Establish and maintain constant communications with the control room. 3.10 Operations Advisor (OA) 3.10.1 Provides general operational advice and assistance to the SEC. 3.11 Security Advisor (SA) 3.11.1 Coordinates security activities. 3.11.2 Performs accountability in the TSC. 3.11.3 Coordinates evacuation or early dismissal of nonessential site personnel. 3.11.4 Oversees the fitness for duty program in the TSC. 3.12 Maintenance Logistics Advisor (MLA) 3.12.1 Advises the TSC staff on plant equipment repairs assessment, site materials capabilities and resource status as required. 3.13 Administrative Advisor (AA) 3.13.1 Provides administrative support. 3.13.2 Directs clerical staff to requested emergency response facilities. 3.13.3 Establishes 24 hour shift schedules for all emergency response facilities. 3.13.4 Executes administrative/logistical functions as directed. 3.14 Mechanical and Electrical Engineer(s) 3.14.1 Performs engineering assessments, trends and recommendations. 3.15 Reactor Engineer(s) 3.15.1 Performs reactor assessments, trends and core damage assessment. 3.16 PPC Operator 3.16.1 Assists the reactor engineer in reading the PPC and preparing release pathway information for dose assessment purposes. (No checklist required.)

4. INSTRUCTIONS 4.1 The position checklists are guidance and may be performed out of the listed order, unless specifically noted.

4.2 TSC personnel shall perform checklist instructions and guidance and other functions as directed.

5. RECORDS 5.1 Completed forms and documents generated during drills are non-quality records and should be retained within department files for a minimum of 3 years.

5.2 Completed forms and documents generated during real events are non-quality good business records and shall be retained in RMS in accordance with AD 10.ID2. EPEF-1u3r35.DOC 03B 1015.0933

PACIFIC GAS AND ELECTRIC COMPANY NUMBER. -EP EFy1 ... DIABLO CANYON POWER PLANT REVISION 35 PAGE 4 OF 5 TITLE: Activation and Operation of the Technical Support Center UNITS I AND 2

6. ATTACHMENTS 6.1 Form 69-20436, "Site Emergency Coordinator (SEC) Checklist," 04/15/04 6.2 Form 69-20437, "ISEC / SEC / Recovery Manager Turnover Checklist," 01/10/05 6.3 Form 69-20438, "Plant PA Announcement," 04/15/04 6.4 Form 69-20439, "Assistant SEC (ASEC) Checklist," 04/15/04 6.5 Form 69-20440, "Liaison Advisor (LA) Checklist," 01/28/06 6.6 Form 69-20441, "TSC Liaison Assistant (TSC to Control Room) Checklist," 04/15/04 6.7 Form 69-20442, "CR Liaison Assistant (Control Room to TSC) Checklist," 04/15/04 6.8 Form 69-20443, "NRC Liaison Assistant (NRC Continuous Communicator) Checklist,"

04/15/04 6.9 Form 69-20444, "Engineering Advisor (EA) Checklist," 04/15/04 6.10 Form 69-20445, "Radiological Advisor (RA) Checklist," 10/14/08 6.11 Form 69-20448, "Radiological Data Processor (RDP) Checklist," 07/23/08 6.12 Form 69-20449, "Radio Operator Checklist," 07/23/08 6.13 "Operation of the TSC Radiation Monitors," 04/15/04 6.14 "NCPM To Mu Ci/cc Conversion for Radiation Monitors," 04/15/04 6.15 Form 69-2045 1, "Field Monitoring Team Exposure Tracking Sheet," 07/23/08 6.16 Form 69-20452, "Reactor Engineer Checklist," 06/21/02 6.17 Form 69-20453, "Mechanical Engineer Checklist," 06/21/02 6.18 Form 69-20454, "Electrical Engineer Checklist," 07/23/08 6.19 Form 69-20455, "Operations Advisor (OA) Checklist," 07/23/08 6.20 Form 69-20456, "Security Advisor (SA) Checklist," 10/14/08 6.21 Form 69-20457, "Maintenance Logistics Advisor (MLA) Checklist," 04/15/04 6.22 Form 69-20458, "Administrative Advisor (AA) Checklist," 06/21/02 6.23 Form 69-20459, "Operation of the TSC Ventilation System," 10/14/08 EPEF-1u3r35.DOC 03B 1015.0933

PACIFIC GAS AND ELECTRIC COMPANY NUMIBER EP EF-1 DIABLO CANYON POWER PLANT REVISION 35 PAGE 5 OF 5 TITLE: Activation and Operation of the Technical Support Center UNITS 1 AND 2

7. REFERENCES 7.1 EP EF-3, Form 69-20788, "Emergency Response Facility Tailboard Checklist" 7.2 EP RB-1 1, "Emergency Off-Site Dose Calculations" 7.3 OP H-5:IV, "Control Room Ventilation System Mode Changes" 7.4 OP K-9, "Instructions for Operation of DCPP Radio Systems" 7.5 PEP EN-1, "Plant Accident Mitigation Diagnostic Aids and Guidelines" 7.6 SP 603, "Security During Operational Emergencies" 7.7 STP M-9M, "Verification of Auto-Connected Loads Less Than 2750 kW" 7.8 DCPP Emergency Plan 7.9 AR A0559390, "ECG 39.1 Alternate Monitoring Requirements" 7.10 Severe Accident Management "DFC-TSC Diagnostic Flow Chart" Plant Manual Volume 3E 7.11 Calculation No. 93-02, "TSC Occupancy" 7.12 Vendor Instruction Manual, Eberline Instrument Corporation, DC 696216-8, "Area Gamma and Air Particulate/Iodine/Noble Gas Monitors" EPEF-1u3r35.DOC 03B 1015.0933

69-20436 04/15/04 Page 1 of 2 DIABLO CANYON POWER PLANT EP EF-1 ATTACHMENT 6.1 AN2 D TITLE: Site Emergency Coordinator (SEC) Checklist Name: Date The steps in this attachment may be performed in any sequence, may be modified, or may be considered N/A at the discretion of the Site Emergency Coordinator, unless specifically prohibited.

1. Initial Actions

[ ] a. Sign in on the Assembly and Accountability Checklist form. [ ] b. Sign in on the TSC sign-in board. [ ] c. Use Form 69-20437, "ISEC/SEC/RM Turnover Checklist", to conduct a briefing with the ISEC and/or Recovery Manager. [ ] d. Within approximately 60 minutes of the initiation of the ERO notification, the TSC is required to be staffed by the following positions. NOTE: Qualified individuals not already filling a minimum staff position may fill vacancies. [ ] Site Emergency Coordinator [ ] Operations Advisor [ ] Reactor Engineer [ ] Maintenance Logistics Advisor [ ] Electrical Engineer [ ] TSC Liaison Advisor [ ] Mechanical Engineer [ ] (2) - FMT Members [ ] e. When minimum staffing is achieved, declare the TSC activated. Ensure PA announcement is made to declare the TSC activated:

           "Attention all personnel. This is__                           the Site Emergency Coordinator. The TSC is operational and has been activated."

[] f. If the Recovery Manager is unavailable, assume responsibility for overall management of Diablo Canyon's emergency response activities. [] g. Consider Assembly & Accountability (refer to EP G-4). EPEF-1u3r35.DOC 03B 1015.0933

69-20436 04/15/04 Page 2 of 2 . EP EF-I (UNITS 1 AND 2) ATTACHMENT 6.1 TITLE: Site Emergency Coordinator (SEC) Checklist

2. Prior to Recovery Manager arrival at the EOF

[ ] a. Establish communications with the Advisor to the County and direct all emergency response operations performed by PG&E in the San Luis Obispo area. [ ] b. Approve Protective Action Recommendations to the County. [ ] c. Change the emergency classification as necessary. [ ] d. Approve "DCPP Emergency Notification," Form 69-20596. [ ] e. Ensure the Liaison Advisor notifies required off-site agencies, until relieved by EOF Agency Liaison. [ ] f. Authorize extraordinary emergency measures such as emergency response personnel exceeding Annual Administrative Exposure Limits (Refer to EP RB-2). [ ] g. Authorize KI issuance to on-site and off-site personnel (Refer to EP RB-3). [ ] h. Authorize information for incorporation into event news releases.

3. Continuing Actions

[ ] a. Upon the arrival of the NRC Initial Site Team, brief the NRC Reactor Safety Operations Coordinator. [ ] b. Ensure the NRC Co-locator is familiar with telephone use, information flow, and has copies of the same documents used for your position. [ ] c. IF a radiological release is imminent or actually occurring, THEN direct Operations to secure Turbine Building ventilation supply fans. [ ] d. Consult with the Radiological Advisor for on-site radiological protective measures and the EOF Radiological Manager for off-site radiological protective measures. [ ] e. Implement EP G-5 to assess the need for evacuation or early dismissal of non-essential personnel. [ ] f. Implement EP EF-9 if the TSC becomes uninhabitable. [ ] g. Perform periodic status briefings to key TSC staff.

                " Assistant SEC

Operations Advisor
Radiological Advisor 0 Maintenance Logistics Advisor
Engineering Advisor 0 Security Advisor

[ ] h. Perform periodic TSC status update by PA announcement. [ ] Perform site wide PA announcements after each significant incident or at least hourly. "Plant PA Announcement" Form 69-20438 may be used. [ ] j. Perform periodic intra facility videoconference or teleconference tailboards using Form 69-20788, "Emergency Response Facility Tailboard Checklist." NOTE: Each facility should complete their applicable section prior to a tailboard. The controlling facility should complete all sections and ensure distribution. EPEF-Iu3r35.DOC" 03B 1015.0933

69-20437 01/10/05 Page 1 of 1 DIABLO CANYON POWER PLANT EP EF-1 2 ATTACHMENT 6.2 A,\ TITLE: ISEC / SEC / Recovery Manager Turnover Checklist Name Date Time [ ] Time of Event: [ ] Time ERO Notified: [ Time Facility must be Activated: [ Current Classification: [ Reason for Classification: (See Notification form) [ ] Affected Unit: [ ] Unit I [] Unit 2

   ] Unit I Status         Mode:                                      Power:

[ ]Unit 2 Status Mode: Power: [ ] Fission barriers challenged: [ ] Fuel [ ] RCS [ ] Containment Radiological Release Status (choose one of the following):

      ] Release to the environment remains within normal operating levels, and effluent radiation monitors did not alarm.

[ I There is a release to the environment, effluent radiation monitors alarmed, but radiation levels are background at the site boundary. [ ] There is a release to the environment, effluent radiation monitors alarmed, and radiation levels are above background at the site boundary. [ A release did occur but is now terminated. [ ] Release source: Last Notification number: Time it was completed: Next Notification number: Time it is required: Who will do it? [ ]CR [ ]TSC [ ]EOF Site accountability status [] Complete [ ] In Progress Due: Early work release initiated [ Yes [ ] No Status: Plant evacuation initiated [ ] Yes [ ]No Status: NOTES EPEF-1u3r35.DOC 03B 1015.0933

69-20438 04/15/04 Page I of 1 DIABLO CANYON POWER PLANT TITL n PA E: Plant noncmn A Announcement EP EF-1 ATTACHMENT 6.3 1N 2 Nam e Date

1. Attention Plant Personnel: [ ] This is a Drill. OR [ ] This is an Emergency Announcement.

2. This is (your name).

3. I am the: [ ] Site Emergency Coordinator [ Assistant Site Emergency Coordinator

4. UNIT: [11 [12 []1 and2

5. Is currently in: [ an ALERT []a SITE AREA EMERGENCY [ a GENERAL EMERGENCY

6. This emergency action level is based upon (state the conditions):

7. 1] There is NO release in progress at the present time.

OR I I There has been a radiological release. Radiation levels have increased. Please stay clear of the following areas:

8. The following actions have been taken to mitigate the event:

9. [1 This is a Drill OR [ ] This concludes the Announcement.

EP EF-1u3r35.DOC 03B 1015.0933

69-20439 04/15/04 Page I of I DIABLO CANYON POWER PLANT EP EF-1I ATTACHMENT 6.4 1AND TITLE: Assistant SEC (ASEC) Checklist Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [] b. Sign in on the TSC sign-in board. [ ] c. Assist SEC with the SEC Checklist.

2. Continuing Actions

[I ] a. IF abnormal TSC ventilation line up is indicated (Mode 2, 3 or 4), THEN ensure the Engineering Advisor implements "Operation of the TSC Ventilation System" checklist. [] b. IF personnel injury occurs on-site, THEN provide status to the Liaison Advisor for transmission to the EOF Agency Liaison. [] c. Assume timekeeping and process driving responsibilities for the following.

PA announcements
Round-table status updates

                 " Emergency notification, PAR formulation and approval

[ ] d. Assist the SEC with the timing of TSC and Site PA announcements. These PA announcements should be made hourly to update staff on the emergency status, OR as soon as possible for the following.

A significant change in plant radiological conditions
A change in Emergency Action Level (up or down)

[ ] e. If requested, assist the SEC with written scripting or notes for upcoming PA announcements. [ ] f. Assist the SEC with preparing for intra facility videoconference/teleconferences. NOTE 1: Try to synchronize status meetings prior to hourly intra facility conferences. NOTE 2: Each facility should complete their applicable section prior to a tailboard. The controlling facility should complete all sections and ensure distribution. [] g. Assist SEC with the timing of DCPP emergency notifications and PARs and their formulation and approval. NOTE: Ensure issuance of DCPP emergency notifications and PARs within 15 minutes following changes to the event classification or new PAR at the GE level. Follow-up notifications should be made approximately every 45 minutes. [ ] h. Assist SEC with communications, assessing need for emergency classification changes, and maintaining cognizance of in-plant repair and assessment activities. [] i. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. EPEF-1u3r35.DOC 03B 1015.0933

69-20440 01/28/06 Pagel1 of 2 Page(1Cofl2 DIABLO CANYON POWER PLANT TITLE: Liaison Advisor (LA) Checklist EP EF- 1 ATTACHMENT 6.5 I1AN2 Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [ ] b. Sign in on the TSC sign-in board. [ ] c. Contact the ELC in the Control Room to determine the status of event classification level, PARs and notifications. [] d. Perform the TSC accountability actions, if not done and no clerk is available. [ ] e. Ensure Liaison Assistants have established the following communications: [] 1) Communications with Emergency Public Information Manager (EPLM). [] 2) Communications with the Control Room on 2002 bridge line. [ ] 3) DCPP emergency notifications to SLO County Sheriff Watch Commander and State OES, until relieved by the EOF. [ ] 4) Communications with the NRC. [ ] f. Phone emergency notification information to the SLO County Sheriff Watch Commander and State OES within 15 minutes of emergency classification or PAR changes.

Follow-up notifications should be made within approximately 45 minutes.

                "     NRC notifications should be made as soon as possible, following notification of State and County, within one hour.

[1 g. Send emergency notifications to the EOF (Agency Liaison, if available, OR Sheriff Watch Commander), NLC, State OES and NRC. [] h. Establish communications with EOF Agency Liaison to ascertain UDAC status and prepare for emergency notification form origination turnover when appropriate. [ I i. Ensure notification of the Sheriffs Watch Commander or the Advisor to the County of any plant evacuation (See EP G-5). 2 Continuing Actions [] a. Until relieved by the EOF, ensure the State and County are notified of new classification levels or PARs within 15 minutes of declaration (one hour for NRC), and updated on 45 minute intervals. [ ] b. Keep the EOF Agency Liaison informed of notifications status and ensure a smooth turnover upon EOF activation. [] c. If requested by the Radiological Advisor, assist with KI and dosimetry issuance and exposure limit authorizations for site personnel. [ ] d. Maintain a chronological file of completed DCPP emergency notification forms. [ ] e. Maintain separate files for EARS printouts, Log Sheets, and any other significant paperwork.

EP.EF-1u3r35.DOC 03B 1015.0933

69-20440 01/28/06 Page 2 of 2. EP EF-1 (UNITS 1 AND 2)

                                              .ATTACHMENT 6.5 TITLE:       Liaison Advisor (LA) Checklist

3. Tu rnover

a. Give a verbal turnover to your shift relief or the EOF Agency Liaison.

b. Instruct your shift relief to complete a new checklist for their shift, entering "N/A" for items that are Not Applicable.

[I c. Turnover Time: Turnover Date: EPEF-1u3r35.DOC 03B 1015.0933

69-20441 04/15/04 Page I of I DIABLO CANYON POWER PLANT 1 AD2 EP EF- 1 ATTACHMENT 6.6 TITLE: TSC Liaison Assistant (TSC to Control Room) Checklist Nanne: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [] b. Sign in on the TSC sign-in board. [ cc. Establish constant communications with the Control Room Liaison Assistant.

2. Continuing Actions

[] a. Coordinate bridge phone activity. [I] b. Retain all past notification forms.

3. Turnover

[ ] a. Give an oral turnover to your shift relief. [] b. Instruct your shift relief to complete a new checklist for his/her shift, entering "N/A" for items that are Not Applicable.

c. Turnover Time: Turnover Date:

EPEF-1u3r35.DOC 03B 1015.0933

69-20442 04/15/04 Page 1 of 1 DIABLO CANYON POWER PLANT EP EF-1 ATTACHMENT 6.7 CR Liaison Assistant (Control Room to TSC) Checklist 1 2 TITLE: Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [] b. Sign in on the TSC sign-in board. [] c. Establish constant communications with the TSC Liaison Assistant. [] d. Ensure initial notifications are complete and fax to the TSC and EOF. [] e. Ensure initial plant status form is complete and fax form to TSC.

2. Continuing Actions

[] a. Provide technical assistance via the bridge network.

3. Turnover

[ ] a. Give an oral turnover to your shift relief. [] b. Instruct your shift relief to complete a new checklist for his/her shift, entering "N/A" for items that are Not Applicable. [] c. Turnover Time: Turnover Date: EPEF-1u3r35.DOC 03B 1015.0933

69-20443 04/15/04 Page I of I DIABLO CANYON POWER PLANT EP EF-lI ATTACHMENT 6.8 1AND TITLE: NRC Liaison Assistant (NRC Continuous Communicator) Checklist Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [] b. Sign in on the TSC sign-in board. [] c. Establish and maintain constant communications with the NRC. [] d. Operate the local PC to obtain plant status.

2. Continuing Actions

[ ] a. Provide technical assistance via the bridge network.

3. Turnover

[] a. Give an oral turnover to your shift relief. [] b. Instruct your shift relief to complete a new checklist for his/her shift, entering "NIA" for items that are Not Applicable. [ ] c. Turnover Time: Turnover Date: EP.EF-1u3r35.DOC 03B 1015.0933

69-20444 04/15/04 Page I of 2 DIABLO CANYON POWER PLANT EP EF-1I ATTACHMENT 6.9 1AND TITLE: Engineering Advisor (EA) Checklist Name Date

1. Initial Actions

[1 a. Sign in on the Assembly and Accountability Checklist form as applicable. [3 b. Sign in on the TSC sign-in board. [ 3 c. Determine the nature of emergency from the Emergency Evaluation Coordinator or from the SEC/ISEC turnover information. [ 3 d. Ensure Mechanical, Electrical, and Reactor Engineers sign in on staffing board in management area of the TSC.

2. Continuing Actions CAUTION: When the TSC is switched from non-vital to vital power, the load on the emergency diesel generator must be monitored after the change. The TSC maximum load is approximately 151 kW.

(Reference STP M-9M.) [3 a. IF normal power to the TSC is lost, THEN request the Control Room to switch the TSC from non-vital to vital power (specify Unit I or Unit 2). The switches are located in the Unit 2 480V Switchgear Room (Panels EPTSN and EPTSC). Evaluate whether EFRDS UPS should also be switched to vital power. [] b. Keep the SEC and the Radiological Advisor informed of plant equipment status, personnel status and recommendations regarding plant response actions. [] c. If TSC ventilation is lost or if other than normal ventilation modes are required, assign an Engineer to perform actions in accordance with the "Operation of the TSC Ventilation System" checklist. [ ] d. Maintain awareness of Control Room activities. [ 3 e. Evaluate plant status, using data from the Engineers: [ ] f. Assist the SEC in determining changes in emergency classification. [ 3 g. Assist the SEC in developing plans for returning the plant to a safe condition. [ 3 h. Determine engineering evaluations required to support the recovery plan using data from the Engineers in the TSC. [] i. Assist the Operations Advisor with development of procedural guidance for abnormal operation of systems or components. [] j. Provide Mechanical Engineers direction and assistance [ ] k. Upon direction from the SEC, direct the Reactor Engineer to enter the SAM "DFC-TSC Diagnostic Flowchart" (Plant Manual Volume 3E). [ ] 1. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. EPEF-1u3r35.DOC 03B 1015.0933

69-20444 04/15/04 :., Page' 2 of 2 EP EF-1 (UNITS 1 AND 2) ATL'ACHMENT 6.9 TITLE: Engineering Advisor (EA) Checklist TSC Engineering Request /Response Tracking Date: ___________ Time Requestor Assigee Request/esp onse Closed EPEF-lu3r35.DOC 03B 1015.0933

69-20445,;*.i- 10/14/08 Pagel1 of 3 DIABLO CANYON POWER PLANT EP EF-1 ATTACHMENT 6.10 1AND TITLE: Radiological Advisor (RA) Checklist Name Date

1. Initial Actions

[ ] a. Sign in on the Assembly and Accountability Checklist form as applicable. [] b. Sign in on the TSC sign-in board. [ ] c. Obtain a turnover on plant radiological conditions and release status from Emergency Evaluation Coordinator in control room, Liaison Advisor, Operations. Advisor, or from the SEC/ISEC. [ d. Designate a person to complete "Operation of TSC Radiation Monitors" checklist. [] e. Complete. or designate a person to verify the following TSC equipment is operational: [ 3 1) Area Radiation Monitors (ARMs) - a) Operating lights are on at monitoring panel or local readout functions. b) No out-of-service stickers. c) ARMs appear to be functioning properly. (1) If the TSC Area Radiation Monitors are not operating, contact the Engineering Advisor and havethe TSC HVAC immediately placed in Mode 4. (2) If the TSC Area Radiation Monitors are not operating and a Safety Injection (SI) has not occurred, contact the control room and have one Unit's control room ventilation placed in Mode 4. [7] 2) HVAC Air Monitors - a) Operating lights are on at monitoring panel or local readout functions. b) No out-of-service stickers. c) Monitors appear to be functioning properly. [ ] 3) Alternate Monitoring: a) IF any TSC area monitors are OOS (RE 60, 61, 62, and 63), THEN use the dose rate meter in the RP cabinet to periodically check for elevated dose rates. Additional instrumentation may be obtained at 85' access control. b) IF any TSC air monitors are OOS (RE 66, 67, and 82), THEN portable CAM located in the TSC shall be used to alert personnel of elevated airborne conditions. c) IF any of the TSC laboratory monitors are OOS (RE 65, 68, 69, and 83) and the lab is to be used, THEN place an instrument such as an Eberline RM-14 in the room to alert personnel of changing radiological conditions. [7] 4) Portable Radiological Equipment - Satisfactory: a) Visual inspection b) Battery c) Calibration date d) Source checks EPEF-Iu3r3S.DOC 03B 1015.0933

69-20445 10/14/08 Page 2 of 3 EP EF-1 (UNITS 1 AND 2) ATTACHtMENT 6.10 TITLE: Radiological Advisor (RA) Checklist

1. Initial Actions (continued)

[] 5) EARS Computer & RMDDT - a) Computers are powered up. b) Computers are functional. [I] f. Establish or designate a person to establish TSC habitability control by: [ ] 1) Placing a count rate meter at west TSC entrance. [] 2) Closing all airtight doors to the TSC. [] 3) Place the appropriate magnetic signs on doors. [ ] 4) Stage radiological contamination control equipment at main TSC entrance, i.e., step-off pads, yellow booties, signs, etc.

2. Continuing Actions

[1 a. Upon the arrival of the NRC Initial Site Team, brief your NRC Co-locator (NRC Radiation Safety Coordinator, HP Specialist, PMCL Communicator) on the emergency developments, mitigating actions, and current activities. [] b. Ensure the NRC Co-locator is familiar with telephone use, information flow, and has copies of the same documents used for your position. [ ] c. IF the emergency involves unusual radiological conditions, THEN recommend to the Site Emergency Coordinator that personnel dosimetry be used by all emergency response personnel. [ ] d. WHEN the SEC directs the issuance of personnel dosimetry, THEN contact the following locations and direct personnel dosimetry be issued to all personnel in accordance with EP RB-1, "Personnel Dosimetry." [1]1) Control room [] 2) OSC [] 3) Security building [] 4) Medical facility [ ] 5) CAS/SAS [ ] e. Compare radiological data to the Emergency Action Levels in EP G-1 on an ongoing basis to determine if an EAL change is needed. If so, notify SEC immediately. [3 f. Establish radiation protection support. [ ] g. Determine necessary personnel for radiation protection support in-plant on-site and off-site. [1]h. . Establish communications with the Site Radiation Protection Coordinator. [3 i. Provide a list of personnel for radiation protection support to Site RP Coordinator, and advise to contact, coordinate and dispatch personnel. EPEF-1u3r35.DOC 03B 1015.0933

69-20445" -' 10/14/08 Page 3 of 3 EP EF-1 (UNITS 1 AND 2) ATTACIHMENT 6.10 TITLE: Radiological Advisor (RA) Checklist

2. Continuing Actions (continued)

[] j. Advise Site RP Coordinator to inform you of off-site agency RP support needed. [ ] k. Notify SEC if additional RP support is necessary from outside agencies. [ ] 1. Establish communications with the EOF Radiological Manager. [1 m. Provide on-site radiation monitoring data and plant radiological conditions information. [1 n. Notify the EOF radiological manager that field monitoring teams have been dispatched. [ ] o. Keep informed of all entries to the RCA and of the location of response personnel. [] p. Determine whether plant status changes will affect personnel exposure. r] q. Periodically provide the SEC with the following information: [ 1) Appropriate on-site and off-site protective actions. [ ] 2) Radiological exposure status of personnel. [ ] 3) On-site radiological protection decisions. [ ] 4) KI - Whenever a calculated Thyroid CDE of 25 rem or greater is likely to be received by an individual or, if possible, prior to undertaking an emergency response operation where high levels of radio-iodine are suspected, or no current air analysis is available, the administration of KI should be considered in accordance with EP RB-3. [ ] r. Recommend to SEC that KI be issued to site personnel, in accordance with EP RB-3. [ ] s. WHEN directed by the SEC, THEN issue KI in accordance with EP RB-3. [ 3 t. Maintain cognizance of plant status as given in the SEC briefings. [ ] u. EXPOSURE LIMITS - Prior to undertaking any attempted rescue or corrective actions which could potentially or actually result in an individual exposure in excess of established annual exposure limits, obtain SEC/RM authorization per the guidance in EP RB-2. [ ] v. Periodically direct habitability surveys to be conducted of CAS/SAS. [ 3 w. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and other information required for performance of their duties. EP.EF-1u3r35.DOC 03B 1015.0933

69-20448 07/23/08 Page I of 6 DIABLO CANYON POWER PLANT EP EF-1 ATTACHMENT 6.11 1 AND TITLE: Radiological Data Processor (RDP) Checklist Name: Date: Time:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [1 b. Sign in on the TSC sign-in board. [ ]c. Establish contact with the Site Radiation Protection Coordinator (SRPC) in the OSC. Indicate your extension number and that you will be the primary contact for communication to and from the Radiological Advisor (RA). [1 d. Poll the RMS, meteorological (MET), and pressurized ion chamber (PIC) data using 'RMDDT' (Refer to checklist, step 3 below, "Instructions for RMDDT"). Inform the RA of abnormal RMS readings. [] e. Enable the TSC radiation monitor recorders using the "Operation of TSC Radiation Monitors" form. [ ]f. Check TSC habitability by inspecting the TSC area and airborne monitoring channels. [ ] g. Start SPINGNET to poll SPING data on an ongoing basis. [ ] h. Start EARS and get MIDAS results (Refer to checklist, step 4 below, "Instructions for using MIDAS").

2. Continuing Actions

[1 a. Trend the plant radiation monitors (using 'RMDDT'), for changes in plant radiological conditions and release status. [ ] b. Inform the RA immediately if significant changes occur on plant vent, steam line, or containment area monitors. (Refer to the following pages of this checklist.) [ ]c. If RE-14 goes offscale high (shuts down the normal range monitors), inform the RA immediately so that implementation of RB-12 may be considered for quantifying plant vent iodine. [1 d. Consult UDAC to determine the source term category (if there is a release in progress) which applies in "Field Monitoring Team Exposure Tracking Sheet". Communicate this to the RPC. If the source term category changes, inform the RPC. [ ] e. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress, etc. [ ] f. Check habitability periodically, by inspecting the TSC area and airborne monitoring channels, and by surveying the vicinity of the TSC/OSC entryways with the portable count rate meter in the RP equipment cabinet. Install a step-off pad and frisker outside entry door(s) if surface contamination is detected. [ ] g. Compare EARS projections and the On-site FMT analysis results for EDE dose rate (15 minute exposure) and 1-131 air concentration (15 minute exposure). Evaluate agreement between the two sets of data and communicate evaluation to the Rad Advisor and to the UDAC, where the ESE will ilso be comparing this same data. EP.EF-1u3r35.DOC 03B 1015.0933

69-20448 07/23/08 Page1of:6 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.11 TITLE: Radiological Data Processor (RDP) Checklist RADIATION MONITORING SYSTEM POWER SOURCES MONITOR Name/Description BjUýS::EBUS FjBUS GBUSH BUS IBTEY B/U Plant Vent R-14 (LRP) NR Noble Gas _ R-14 (RDU) _ _ R-14R (LRP) RNR Noble Gas _ R-14R (RDU) _ 0 R-24 (LRP) NR Iodine _ R-24 (RDU) _ 0 R-24R (LRP) RNR Iodine 0 R-24R (RDU) 0 0 R-28 (LRP) NR Particulate _ R-28 (RDU) 0 0 R-28R (LRP) RNR Particulate _ R-28R (RDU) 0 0 R-29 PV Gross Gamma 0 S R-34 PV ALA RA (PV skid area) __ _ _ _ _ _ S _ _ _ _ _

  -87 (LRP)                Extended Range Noble Gas                             S Iecondary

_-15 (LRP) Condenser Air Ejector

R-15 (RDU) 0 0 R- 15R (LRP) Redundant CAE
R-15R (RDU) _ 0 R-19 S/G Blowdown Sample Line _ _

R-23 S/G Blowdown 0 R-71 Main Steamline #1 0 0 R-72 Main Steamline #2 0 0

 -73                      Main Steamline   #3                                _       _ _
 -74                      Main Steamline   #4                  _

Containment

 .-2                      Low Range Area                                                 0              0
 -7                       Incore Seal Table Room

0 R-30 High Range Area 0 0 R-31 High Range Area _ 0 R-44A (LRP) Containment Purge Exhaust (CPE) 0

                          - Class IE Train 'A' R-44A (RDU)                 _                                                _

R-44B (LRP) Containment Purge Exhaust - 0 Class 1E Train'B'__ R-44B (RDU) .I _ _ _ _ _ Fuel Handling Building R-58 ISpent"FuelPoolArea I " R-59 lgew Fuel Pit Area I 1 NOTE 1: LRP = Local Radiation Processor; includes detector and local display. RDU= Radiation Display Unit; this is the Control Room display. NR = Normal Range RNR= Redundant Normal Range NOTE 2: There are no unit differences on this table. EP-EF-1u0r5.DOC 03B 0593 1015.0933

69-20448 - ý,%-; 07/23/08 Page 3 of 6 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.11 TITLE: Radiological Data Processor (RDP) Checklist

3. Instructions for Radiation Monitor Display and Trending (RMDDT)

a. On a Plant Data Network (PDN) computer, select the RMDDT shortcut icon located on the main screen.

Rmddt.Ink NOTE: The application will open showing the "RMS Overview" tab.

b. Configure RJMDDT using the following selections:

1) Unit - On the right side of the screen, select the desired Unit (I or 2) to trend.

2) Alarm - On the right-bottom side of the screen, select the "Audible" switch to "On" or "Off."

NOTE: An alarm will sound whenever a monitor exceeds a pre-determined set point. In addition, the monitor window will show a red outline. Selecting Audible to "On" or "Off' is a personal preference. CAUTION: In the following section, DO NOT select "Drill Data" during an actual plant emergency. Only select "Drill Data" during a drill scenario.

3) Options - On the menu-bar, select "Option" to display a list of monitor window configuration options.

NOTE: If an option is has been selected and is active, a check-mark will appear to the left of the option. The only exception is the "Set Time" option, which will never display a check-mark. a) Drill Data (1) If RMDDT is being used during an emergency drill select "Drill Data." If a check-mark appears to the left of this selection, then a plant drill-feeder server will provide pre-determined trends for training/drill purposes. (2) If RMDDT is being used for an actual plant emergency, ensure that there is NOT a check-mark next to "Drill Data." b) Set Time NOTE: The normal default initially provides a two-hour look-back trend. Then a rolling two-hour trend will scroll by. Since the facility is manned in less than two hours, do not adjust the time display. c) Auto Update - make sure this option is selected. Otherwise the trend will not continue. d) Display Values - Selecting this option causes numerical values to be displayed along with the monitor name above the applicable window. e) Autoscale X - This option cannot be changed. It will always display a check mark. f) Autoscale Y - Select this option to adjust the Y scale to a linear display of monitor readings. Otherwise, the Y scale will remain in the Logarithmic (default) scale. EP EF-1u3r35.DOC 03B 1015.0933

69-20448 07/23/08 Page;ý of,6 EP EF-1 (UNITS 1 AND 2). ATTACHMENT 6.11 TITLE: Radiological Data Processor (RDP) Checklist

4. Instructions for Using Midas

a. Discussion Two (2) applications (shortcuts) are normally used by the RDPP during an emergency or drill scenario. These are normally found on the TSC EARS Workstation, which is part of the Plant Data Network (PDN).

Shortcut to GetMidas.Ink MIDAS Accident CaIcs.Ink Unless directed otherwise by Emergency Planning personnel, or Emergency Response Organization Management, DO NOT OPEN EARS (Emergency Assessment and Response System). Doing so may interrupt the calculation process being conducted by the Unified Dose Assessment Center (IDAC) Health Physicist. The main objective for the RDPP, using MIDAS, is to compare On-Site Field Monitoring Team analysis results with EARS projections for:

            "     Effective Dose Equivalent rate (general area dose rate in mrem/hr or rem/hr)

Iodine air concentration (pCi/cc).

b. Instructions

1) Preparing The System a) Contact UDAC and ensure that the Health Physicist using EARS is saving each MIDAS run upon exiting the program (e.g. "Update 1" etc), and then clicking "Share MIDAS" to distribute the files over the PDN.

NOTE: If either step above is not performed, then the TSC will not be able to use MIDAS to view dose projection information performed by UDAC. b) Periodically contact UDAC to determine when each EARS update is completed. c) After an EARS update has been completed, perform the following, as necessary or as requested by the TSC Radiological Advisor. d) On the TSC EARS workstation, double-click on the "Shortcut to GetMidas" shortcut. This application will update the workstation with the latest EARS update information.

2) Opening MIDAS a) Double-click on the "MIDAS Accident Calcs" icon.

b) On the opened window, select "Recap Previous Run." c) From the list of recap files displayed, select the desired recap. Select by placing the cursor over the desired row's button, on the left side of the "Description" column. Normally, the most recent recap file (shown at the top of the list) should be selected. d) If the "Date" column for the selected recap does not reflect the expected date/time, contact UDAC to ensure EARS updates are being performed in the "share" mode. If the date/time is not current, a proper evaluation cannot be performed in the TSC. e) When the recap information is determined to be correct, select the green OK button on the bottom-right of the window. EP_EF-1u3r35.DOC 03B 1015.0933

69-20448 '.` 07/23/08 Page 5 of 6 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.11 TITLE: Radiological Data Processor (RDP) Checklist

4. Instructions For Using (MIDAS) (continued)

3) Display the EDE map a) Normally, the window opens showing the TEDE 4-Day Projected Dose Plume.

b) On the screen's bottom button menu, select "EDE." c) Ensure the "Dose Rate" button is highlighted d) Toggle the Exposure duration button (below the Thyroid CDE button) until it reads "Exposure at 0.25 hr." e) Toggle the button below the EDE button until it displays "Graphic." f) On the bottom-right side of the screen, select the flashing "confirm" button. NOTE: This will update the display using the parameters selected above. The displayed map is normally set to a 20 mile span. g) Zoom in on the site plume by selecting the "Mile" button on the bottom-right of the screen. h) This will open up a calculator-type screen that allows a specific screen size to be input. Normally, a 0.8 mile size works well. i) Open the "Map Features" button (bottom-left of screen) and select "PICS" and "RMPs - On Site" and then press "OK." j) Select the "POI" (points-of-interest) button. This allows specific points on the map to be selected to show the dose rate at that location. k) Using the pointer, select the desired points. Normally, the location of the On-Site FMT's sample point should be selected for comparison of projected and actual conditions. NOTE: Pressing POI will erase the selected points.

1) When desired, press the printer button (lower-right of screen).

m) Follow the on-screen display to either print, save to file, or email the map.

4) Display the Iodine Concentration Map a) On the screen's bottom button menu, select "Ingestion Pathway."

b) The "1-131" and "Air Conc" buttons below Ingestion Pathway should both highlight automatically. If not, toggle each button until they read as desired.' c) Using the POI button, highlight any desired areas for comparison with FMT data (this should be the same as for the EDE map). d) As desired, re-size the map using the "Mile" button on the lower-right of the screen. e) When desired, press the printer button (lower-right of screen). f) Follow the on-screen display to either print, save to file, or email the map.

5) Exit MIDAS by selecting either "End Run" in the lower-left corner of the screen, or the "X" on the upper-right of the screen.

EP.EF-1u3r35.DOC 03B 1015.0933

69-20448 07/23/08 Page 0 of 6 EP EF-1 (UNITS I AND 2) ATTACHMENT 6.11 TITLE: Radiological Data Processor (RDP) Checklist

4. Instructions for Using (MIDAS) (continued)

6) A prompt will ask "Do you want to terminate this run?" Select "Yes."

7) If MIDAS is to be used again after the next EARS projection is performed, run "Shortcut to GetMidas" first to update the workstation with the proper files for viewing by MIDAS.

8) Review the two printed plots with the Radio Operator and Radiological Advisor to determine if On-site FMT data matches the projections performed by EARS.

9) Communicate this information to UDAC

10) If projections and FMT data do not agree within a factor of five, assist UDAC in troubleshooting the reasons.

11) Retain all data for archiving.

EPEl-1u3r35.DOC 03B 1015.0933

69-20449,E-.'ý! 07/23/08 Page I of 2 DIABLO CANYON POWER PLANT ATTACHMENT 6.12 1 AND2 TITLE: Radio Operator Checklist Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [ ] b. Sign in on the TSC sign-in board. [] c. Contact the Radiological Advisor (RA) or Site Radiation Protection Coordinator (SRPC) at the OSC upon arrival at the TSC and determine if a radiological release has occurred or in progress. [ ] d. Obtain the -wind speed and direction from the Plant Rad Data Processor (RDP-Plant). [ ] e. At an ALERT or greater classification, THEN dispatch on and off-site field monitoring team (FMT) personnel in accordance with EP RB-8. [ ] f. Provide the combination key code for the OEL garage to the off-site FMT if requested. The key code is located in the RA's top left desk drawer, 85' Access Senior, or Radiological Manager's top drawer. [ ] g. Evaluate the need for any vehicles in excess of C&RP trucks and coordinate with the SRPC in the OSC. [ ] h. Establish communication with the On-site FMTs by calling FMT satellite telephones using the plant phone (preferred) on the radio operator desk. The Globalstar base station satellite phone is a backup.

                 " FMT satellite phone numbers and calling instructions are in Attachment 7.6 of EP RB-8.
                 " The primary mode of communication with On-site FMTs is portable Iridium satellite telephone, with cell phones as the backup for communication with the TSC.
                 " On-site FMTs can communicate with the EOF using Brown net radios as an alternate backup, but can not communicate with the TSC on the Brown net radios.

[ ] i. Assign team call names as follows: [ ] 1) On-site teams use numbers, i.e., "Team ONE," "Team TWO," etc. [] 2) Off-site teams use phonetic names, i.e., "Team ALPHA," "Team BRAVO," etc.

2. Continuing Actions NOTE: The Controlled Area refers to on-site locations outside of the Protected Area.

[] a. IF there is a release in progress, instruct the on-site FMTs to perform habitability surveys of the following controlled area assembly areas: [ ] 1) Maintenance Shop Bldg Rooms [1]2) Parking Lot #7 [ ] 3) Security Bldg Lobby [ ] 4) 500 kV Switchyard [ ] b. Direct placement of FMTs to verify: [ ] 1) Plume trajectory and spatial distribution. [ ] 2) Direct exposure, airborne radioiodine and particulate concentrations. EP.EF.1u3r35.DOC 03B 1015.0933

69-20449 07/23/08 Page 2 of.2. EP EF-l (UNITS 1 AND 2) ATTACHMENT 6.12 TITLE: Radio Operator Checklist [1]3) Deposition of radioiodines and particulates. [1 c. Record FMT data and calculate particulate and iodine concentrations in the table below. Notify the RDPP and UDAC that this data is available for validating actual FMT data with EARS plume data. Field Monitoring Data Ground Sky Dose Rate Smear Air Particulate

Iodine Monitor Time net' Shine net mR/hr dpm / ft3 net net u cpm cpm WO/WC 100 cm2 cpm uci/ml cpm

                                *Particulat      u_ */
                                        = (1.613-10                     _*             d___*

Particulate uCi/ml = (1.6E-10) * (net cpm)/ Airut ** Iodine uCi/mlum(5.6E-09) * (net casamipt NOTE: Potentially high iodine releases should be suspected for: steam generator tube rupture with condenser unavailable, LOCA with plant vent iodine filtration unavailable, or known/suspected fuel damage.

[3] d. Prior to initial plume entry, the FMT members should be directed to take Thyroid Blocking (KI) in accordance with EP R.B-3, if necessary. [ ] e. Initial TURNBACK VALUE is 500 mR/hr (instrument reading) for plume entry and air sampling. This value may be adjusted by the RA based on iodine and particulate concentration data. [1] f. The "Field Monitoring Team Exposure Tracking Sheet" may be used for interim guidance prior to sample analysis. [ ] g. Maintain FMT status board and maps in the radiological assessment area. [ 3 h. Update teams at least once per hour or whenever there is a change in the following: [ ] 1) Event status - plant conditions including loss of fission product barriers [1 2) Release status [ ] 3) Tum back dose rates [] 4) Weather conditions [ 3 5) Personnel protective actions [ ] i. Provide the RA with the Team location. [] j. Provide the RA with the Team movement. [] k. Provide the RA with the Monitoring results and personnel exposures. [] 1. Monitor and record team members' exposures. [ ] m. Provide shift relief with tumover of important information. Include logs, plant status summaries, protective action summaries, activities in progress, etc. EPEF-1u3r35.DOC 03B 1015.0933

69-20450 " -.. 04/15/04 Page I of 2 DIABLO CANYON POWER PLANT EPEF-11 ATTACHMENT 6.13 AND 2 TITLE: Operation of the TSC Radiation Monitors

1. Placing the Radiation Monitor Recorders in Service CAUTION: When removing or replacing the pens in the recorders, the recorder must be turned off and use the pulleys located at the top rear area of the recorder to move the pen off the left stop. Attempting to move the pen by hand or by pulling the drive cord can cause the recorder to become un-calibrated.

Perform the following steps to place each recorder; 0-11, 0-12, 0-13 and 0-14, in service: NOTE: There are two power switches on each recorder. The one closest to the front of the recorder is the power switch for the chart drive. The rear switch is the main power. [ ] a. Unlatch and pull the recorder out of the cabinet to the second stop. Latch is located at the bottom right corner of the recorder housing. [ ] b. Turn off the main power switch, located at the right rear. [ ] c. Remove the dummy pens in the following order: green-blue-red, and store so they can be re-installed after the event or drill. [1 d. Install new pens in the following order: red-blue-green. [1 e. Turn both power switches, located on the right side of the recorder, to the ON position (front switch to the rear and rear switch to the front). [3 f. Slide the recorder into the rack. NOTE: Holding the switch depressed may alarm the monitor. [1 g. Test the response of each channel of the recorder by depressing the green Normal light until deflection of the pen is observed. Recorder Channel 0-11 RE-60 [] RE-61 [] RE-62 [__ 0-12 RE-63 [] RE-64 IA RE-65 [ 0-13 RE-66 [ ] RE-67 [3 RE-82 [ ] 0-14 RE-68 [] RE-69 [] RE-83 [] [] h. Annotate the chart with the date and time the recorder was turned on. [3 i. IF any channel or recorder is not operating properly, THEN inform the Radiological Advisor immediately. EP.EF-1u3r35.DOC 03B 1015.0933

69-20450 04/15/04 Page 2 of 2 EP EF-1 (UNITS I AND 2) ATTACHMENT 6.13 TITLE: Operation of the TSC Radiation Monitors

2. Removing the Radiation Monitor Recorders from Service CAUTION: When removing or replacing the pens in the recorders, the recorder must be turned off. Use the pulley shaft located at the top rear area of the recorder to move the pen off the left stop. Attempting to move the pen by hand or by pulling the drive cord can cause the recorder to become un-calibrated.

Perform the following steps to each recorder; 0-11, 0-12, 0-13 and 0-14 to remove from service: NOTE: There are two power switches on each recorder. The one closest to the front of the recorder is the power switch for the chart drive. The rear switch is the main power. [] a. Unlatch and pull the recorder out of the cabinet to the second stop. [] b. Turn both power switches, located on the right side of the recorder, to the OFF position. [ ] c. Remove the pens in the following order: green-blue-red. [ ] d. Insert the red, then blue, then green dummy pen cartridges into the holders. [ ] e. Turn on (forward) the main (rear) power switch. [] f. Slide the recorder into the rack. [ ] g. Annotate the chart with the date and time the recorder was turned off. Date Time Recorder 0-11 Recorder 0-12 Recorder 0-13 Recorder 0-14

3. Air Monitor Filter Replacement

[ ] a. Obtain two APD filter paper rolls (stock code 62-2044) and two silver zeolite iodine cartridges (stock code 49-7393) from the storage cabinet in the Computation Room of the TSC. [ ] b. In~tall an APD filter paper roll in RE-66 and RE-68, if necessary. [] c. Dispose of the used filter paper in an appropriate location. [1 d. Install an iodine cartridge in RE-82 and RE-83. [ ] e. Ensure the sample pump is running. The pump switch is located adjacent to the pumps and a screwdriver is required to open the box. [ ] f. Take the used cartridges from RE-82 and RE-83 to the Sample Lab. EPEF-Iu0r35.DOC 03B 1015.0933

    * ..          04/15/04                                                          Page 1 of 9 DIABLO CANYON POWER PLANT TITLE:

EP EF- 1 ATTACHMENT 6.14 NCPM To Mu Ci/cc Conversion for Radiation Monitors 1AN2 Figure 1: Particulate Monitors RE-66 and RE-68 (100-1000 NCPM) 4.0e-9 Particulate 3.2e-9 2.8e-9 00O 2.4e-9 C-) 2.0e-9 Z3 1.6e-9 1.2e-9 8e-10 4e-10 r 100 200 300 400 500 600 700 800 900 1000 NCPM EPEF-1u3r35.DOC 03B 1015.0933

04/15/04 Page 2 of 9 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 2: Particulate Monitors RE-66 and RE-68 (1000-10,000 NCPM) 4.0e-8 Particulate 3.6e-B 3.2e-8 2.8e-8 0 2.4e-8 0 C,_) 2.0e-8 1.6e-8 1.2e-8 8.0e-9 4.0e-9 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 NCPM EPEF-1u3r35.DOC 03B 1015.0933

   '- . .1 . . 04/15/04                                                            Page 3 of 9 EP EF-1 (UNITS 1 AND 2)

ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 3: Particulate Monitors RE-66 and RE-68 (10,000-100,000 NCPM) Particulate 5e-7 4e-7 0 3e-7 2e-7 I e-7 0 0 0D 0 0 0 0 0CD E C) 0 0 0 0 0 0* 0 0 0 0

                           -4       CU    (0)    q-     LO   I'      -    a)      U0 NCPM EPEF-Iu3r35.DOC     03B        1015.0933

04/1 5/04 %; ;ý ý-; Page 4 of 9 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 4: Noble Gas Monitors RtE-67 and RE-69 (1e2-1e3 NCPM) Noble Gas 3e-5 2.5e-5 C) 2e-5 0 ()1.5e-5 1e-5 5e-6

                       .00 1e2    2e2     3e2    4e2  5e2    6e2   7e2     Be2   9e2      1e3 NCPM EPEF-1 u3r35.DOC     03B        1015.0933

04/15/04 Page 5 of 9 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 5: Noble Gas Monitors RE-67 and RE-69 (1e3-1e4 NCPM) Noble Gas 3e ,. 2.5e-4 -

                 . 2c-4   ~_,

C-)

                 . 1.5e-4  -

le-4 5e .00 1e3 2e3 3e3 4e3 5e3 6e3 7e3 8e3 9e3 1e4 NCPM EPEF-Iu3r35.DOC 03B 1015.0933

04/15/04 Page 6 of 9 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 6: Noble Gas Monitors RE-67 and RE-69 (1e4-1e5 NCPM) Noble Gas 3e-3 2.5e-3 e-0 C) 2e-3

                                                                     ,0,1-
                                  -l 1e-3 5e-4        -100
                       .00 1e4     Ee4   3e4    4e4  5e4   6e4   7e4   Be4    9e4 1e5 NCPM EPEF-Iu3r35.DOC   03B           1015.0933

04/15/04 Page 7 of 9 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 7: Iodine Monitors RE-82 and RE-83 (100-1000 NCPM) Iodine 3e-9 2.5e-9 o 2e-9 C-) 1.e-1le-9 5e-10 0 100 200 300 400 500 600 700 Boo 900 1000 NCPM EPEF-lu3r35.DOC 03B 1015.0933

04/15/04 Page 8 of 9 EP EF-I (UNITS 1 AND 2) ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 8: Iodine Monitors RE-82 and RE-83 (1000-10,000 NCPM) Iodine 5e-8 o 4e-B o* 3e-8 2e-8 le-B 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 NCPM EPEF-lu3r35.DOC 03B 1015.0933

           *1.
            "      04/15/04                                                               Page 9 of 9 EP EF-1 (UNITS 1 AND 2)

ATTACHMENT 6.14 TITLE: NCPM To Mu Ci/cc Conversion for Radiation Monitors Figure 9: Iodine Monitors RE-82 and RE-83 (10,000-100,000 NCPM) Iodine 3e-7 2.5e-7 2e-7 o1 .5e-7 C) le-7

3 5e-8 0

oý C 03 0 0 0 0 Co 0 0D on C) m CD 0 0 0D n 03 cý CD 0ý ý 0 03 Co C3 ý 0: 03 0 D 0n C 0D CD 0> 0 0

                                  -    cu         C.~ .q-    O   %D      r-      co       0 NCPM EP.EF- u3r35.DOC    03B        1015.0933

69-20451 07/23/08 Page I of 2 DIA13LO CANYON POWER PLANT TITLE: EP EF-1 ATTACHMENT 6.15 Field Monitoring Team Exposure Tracking Sheet 1 AND 2 SRD Dose Conversion Factors TEDE DCF TEDE DCF THY. DCF THY. DCF Source Term No KI With KI No KI With KI CORE 13 5 162 16 GAP 24 3 515 52 DB RCS 3 1 40 4 SG Normal 1 1 4 0.4 SG Empty 3 1 40 4 SG Flooded 15 2 285 29 Use the tables above and below to convert PIC readings to Dose.

1. Record the time and readings for both the high and low range PICs.

2. Multiply by the dose conversion factors (DCFs). If the source term changes, use the new DCF multiplier.

3. If a PIC is re-zeroed, circle the last TEDE and Thyroid CDE values and add the circled values to determine the Cumulative TEDE and Thyroid CDE.

4. Refer to EP RB-2 for emergency worker PAGs.

FMT: Name of Individual:

        , i)). Only use highest onscale                                  :On                         necessary when PIC reading.              See table above.   *,          _____,-__          PIC is re-zeroed.

Time Low Range High Range Thyroid Thyroid Cumulative Cumulative Reported PIC (mR) PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE (Roentgen) DCF DCF (mrem) (mrem) (mrem) (mrem) FMT: Name of Individual: Only use highest onscale " Only necessary when PIC reading. See table above. PIG is re-zeroed. Time Low Range High Range Thyroid Thyroid Cumulative Cumulative Reported PIC (mR) PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE (Roentgen) DCF DCF (mrem) (mrem) (mrem) (mrem) EP.EF-1u3r35.DOC 03B 1015.0933

69-20451 07/23/08 Pagel. of 2 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.15 TITLE: Field Monitoring Team Exposure Tracking Sheet FMT: Name of Individual: Only use highest onscale " " Only necessary when PIC reading. See table above. PIC is re-zeroed. Time Low Range High Range Thyroid Thyroid Cumulative Cumulative Reported PIC (mR) PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE (Roentgen) DCF DCF (mrem) (mrem) (mrem) (mrem) FMT: Name of Individual:

        . .*    Only use highest onscale                                            .      Only necessary when PIC reading.            See table above.  ,.____._____                PIG is re-zeroed.

Time Low Range High Range Thyroid Thyroid Cumulative Cumulative Reported PIC (mR) PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE (Roentgen) DCF DCF (mrem) (mrem) (mrem) (mrem) FMT: Name of Individual: Only s Only necessary when PIC reading. See table above. -.. PIC is re-zeroed. Time Low Range High Range Thyroid Thyroid Cumulative Cumulative Reported PIC (mR) PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE (Roentgen) DCF DCF (mrem) (mrem) (mrem) (mrem) FMT: Name of Individual: Only use highest onscale Only necessary when

                     -PI reading.            See table above. _______   ________          PIC is re-zeroed.

Time Low Range High Range Thyroid Thyroid Cumulative Cumulative Reported PIC (mR) PIC* TEDE CDE TEDE CDE TEDE Thyroid CDE (Roentgen) DCF DCF (mrem) (mrem) (mrem) (mrem)

NOTE: The high range PIC reading must be multiplied by 1,000 to convert from Roentgen to mR.

EP EF-lu3r35.DOC 03B 1015.0933

69-2d*A'2`t;"' 06121/02 Page I of I DIABLO CANYON POWER PLANT EP EF-1I ATTACHMENT 6.16 1 AND TITLE: Reactor Engineer Checklist Name: Date:

1. Initial Actions

[ ] a. Sign in on the Assembly and Accountability Checklist form as applicable. [ ] b. Sign in on the TSC sign-in board. [1 c. Establish communications with the EOF Engineering Liaison. [ ] d. Perform initial core damage assessment calculations.

2. Continuing Actions

[] a. Upon arrival of the NRC Initial Site Team, brief your NRC Co-locator (NRC Rx Systems/Operations Specialist, Senior Resident, RSCL Communicator) on the emergency developments, mitigating actions, and current activities. Ensure the NRC Co-locator is familiar with telephone use, information flow, and has copies of the same documents used for your position. [ ] b. Continue to perform core damage assessments. [ ] c. Provide the results to: [] 1) Electrical Engineer. [ ] 2) Mechanical Engineer for entry in the EN-I data sheet. [] 3) EOF Engineering Liaison.

    ))   d. Perform engineering functions as necessary or as directed by the Engineering Advisor.

[ ] e. Assist in making engineering evaluations to support the recovery plan. [ 3 f. Provide shift relief with turnover of important information. Include logs, plant status summaries, protectiveaction summaries, activities in progress and any other information required for performance of their duties. [ ] g. Upon direction from the Engineering Advisor, assume the role of SAM Evaluator and enter the SAM "DFC-TSC Diagnostic Flowchart" (Plant Manual Volume 3E). [1 h. Maintain communications with Engineering Liaison in the EOF. Discuss plant status, critical parameters, core damage assessment results, potential release pathways, etc. EPEF-1u3r35.DOC 03B 1015.0933

69-20453 06/21/02 Page I of I DIABLO CANYON POWER PLANT EP EF-1I ATTACHMENT 6.17 1 N2 TITLE: Mechanical Engineer Checklist Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [ ] b. Sign in on the TSC sign-in board. [ ] c. Establish communications with the Control Room Liaison Assistant on the x2002 bridge line. [ d. Request current plant status information.

2. Continuing Actions

[] a. Monitor SPDS and PPC for current plant status information. NOTE: Refer to EP EF-3, Attachment 6.21, "Leak Path Flow Chart" as necessary. [] b. Coordinate with the Liaison Advisor to obtain plant equipment status information. NOTE: Plant equipment status information may be provided through the Liaison Assistant in the TSC, or from the Liaison Assistant in the Control Room via the Bridge line (x6002). [] c. Refer to PEP EN-I for specific details on accident types. [] d. If required, perform TSC HVAC abnormal lineup, in accordance with "Operation of the TSC Ventilation System" form. [] e. Assist in making engineering evaluations to support the recovery plan. [] f. If requested, in the event of a steam generator tube rupture, estimate the primary to secondary leakage utilizing STGR.EXE. [] g. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. EPEF-1u3r35.DOC 03B 1015.0933

69-20454 07/23/08 Page I of 3 Pager1hofs DIABLO CANYON POWER PLANT TITLE: Electrical Engineer Checklist EP EF-1 ATTACHMENT 6.18 I1AN2 Name: Date:

1. Initial Actions

[ ] a. Sign in on the Assembly and Accountability Checklist form as applicable.

     ][  b. Sign in on the TSC sign-in board.

[ ] c. Ensure computers are turned on in the TSC engineering area. [ ] d. Consult the PPC to procure current 4kV bus availability information. [ ] e. Determine which unit 4kV bus is out of service (if any). [ ] f. Assess which plant equipment is affected by the bus outage (refer to page 2 of this checklist). [ ] g. Assess which radiation monitors are affected by the bus outage (refer to pages 3 and 4 of this checklist).

     ]   h. Provide the results to the Engineering Advisor.

2. Continuing Actions

[ ] a. Continue to monitor PPC for current electrical equipment status information. [] b. Refer to PEP EN-I for specific details on accident types. [] c. If required, perform TSC HVAC abnormal lineup, in accordance with "Operation of the TSC Ventilation System" Form 69-20459 [ ] d. Perform engineering functions as necessary or as directed by the Engineering Advisor. [] e. Assist in making engineering evaluations to support the recovery plant. [ ] f. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. [] g. Monitor ERDS is transmitting by noting the word, "Transmitting" is displayed on SPDS. NOTE: If connection to the NRC is lost, it is required to wait at least 15 minutes before attempting to re-connect. This is to allow the NRC system automated backup process time to complete. Reconnection within 15 minutes may result in lost data. If Re-connecting, follow these steps:

1. Touch the SPDS Screen in the lower left area until "CANCEL" has a blue background, then remove your finger from the screen. This should result in the SPDS menu.

2. Touch the ERDS Button in the second row from the bottom on the far right side of the screen.

This should result in the ERDS screen.

3. Touch the Activate Button. This should result in a change to the status message.

4. Verify the word "Transmitting" is displayed.

EPEF-1u3r35.DOC 03B 1015.0933

69-20454 07/23/08 -,. %, Page 2 of 3,-ý EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.18 TITLE: Electrical Engineer Checklist SAFETY SYSTEM STATUS (Circle Out of Service Equipment) Unit-i 4kV Loads Component Bus F Bus G Bus H Diesel 1-3 1-2 1-1 SI 1 2 RHR 1 2 CCP 1 2 PDP 3 AFW 3 2 ASW 1 2 CCW 1 2 3 Cont Spray 1 2 CFCU 1&2 3&5 4 Unit-2 4kV Loads Component Bus F Bus G Bus H Diesel 2-3 2-1 2-2 SI 1 2 RHR 1 2 CCP 1 2 PDP 3 AFW 3 2 ASW 1 2 CCW 1 2 3 Cont Spray 1 2 CFCU 1&2 3&5 4 Off-Site Power Available [ ] 230kV ((] 500kV EP.EF-1u3r35.DOC 03B 1015.0933

69-20454 Ž- 07/23/08 Page 3 of 3 EP EF-1 (UNITS I AND 2) ATTACHMENT 6.18 TITLE: Electrical Engineer Checklist RADIATION MONITORING SYSTEM POWER SOURCES MONITOR Name/Description BRUS E BUS FBUS C U U IBTEYB/U Plant Vent R-14 (LRP) NR Noble Gas _ R-14 (RDU) __* R-14R (LRP) RNR Noble Gas _ R-14R (RDU) __ _ R-24 (LRP) NR Iodine _ R-24 (RDU) S S R-24R (LRP) RNR Iodine _ R-24R (RDU) _ 0 R-28 (LRP) NR Particulate

R-28 (RDU) __*

R-28R (LRP) RNR Particulate _ R-28R (RDU) *

R-29 PV Gross Gamma _
R-34 PV ALARA (PV skid area) _

R-87 (LRP) Extended Range Noble Gas

Secondary R-15 (LRP) Condenser Air Ejector
R-15 (RDU) S
R-15R (LRP) Redundant CAE
R-15R (RDU) S
R-19 S/G Blowdown Sample Line S *

 -23                      S/G Blowdown                                          _
 -71                      Main Steamline #1                                              0

R-72 Main Steamline #2 0
R-73 Main Steamline #3 0
R-74 Main Steamline #4 0 f Containment R-2 Low Range Area _ _ _

R-7 [ncore Seal Table Room S S R-30 High Range Area 0

R-31 High Range Area _
R-44A (LRP) Containment Purge Exhaust (CPE) S

                          -Class  IE Train 'A'
 -44A (RDU)                                                            _

R-44B (LRP) Containment Purge Exhaust -

Class 1E Train 'B' R-44B (RDU) _ 0 Fuel Handling Building R-58 jSpent Fuel Pool Area *" r

R-59 Pew Fuel Pit Area
NOTE 1: LRP = Local Radiation Processor; includes detector and local display.

RDU= Radiation Display Unit; this is the Control Room display. NR= Normal Range RNR = Redundant Normal Range NOTE 2: There are no unit differences on this table. EPEF-1 u3r35.DOC 03B 1015.0933

69-20455 07/23/08 Page I of I DIABLO CANYON POWER PLANT EP EF-1I ATTACHMENT 6.19 1 AND TITLE: Operations Advisor (OA) Checklist Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [ ] b. Sign in on the TSC sign-in board.

2. Continuing Actions

[] a. Keep the SEC advised on plant operational activities and any requests for assistance. [] b. Prior to arrival of the Engineering Advisor (EA), assume responsibility for the TSC ventilation system. See "Operation of the TSC Ventilation System" form. [] c. Assist the Engineering Advisor (EA) in assessing SPDS information and plant data as required. [] d. Coordinate off site power issues with Los Padres Emergency Response Coordinator as needed. [ ] e. Coordinate with Industrial Fire Officer and off-site fire response agencies as needed.. NOTE: The Site Emergency Coordinator must approve the operation of systems or components, without written guidance. [ ] f. Coordinate the development of written guidance for operations of systems or components in abnormal configurations. [ ] g. Upon direction from the SEC, assume role of Control Room liaison for SAM Guideline implementation. [ h. Obtain a copy of the Control Room and Turnover logs. [] i. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. EPEF-1u3r35.DOC 03B 1015.0933

69-20456 10/14/08 Page 1 of 2 DIABLO CANYON POWER PLANT EP EF-1 ATTACHMENT 6.20 AND2 TITLE: Security Advisor (SA) Checklist Name: Date:

1. Initial Actions

[ ] a. Sign in on the Assembly and Accountability Checklist form as applicable. [ ] b. Sign in on the TSC sign-in board. [1 c. Establish communications with the Diablo Canyon Watch Commander (DCWC) to initiate SP 603, "Security During Operational Emergencies." [] d. Ensure East water-tight door has the locks and pins removed while the TSC is occupied. [] e. Check for security threat status and advise SEC of threat status. [ ] f. Obtain concurrence to override OMNI LOCK and override OMNI LOCK if necessary. [1 g. Perform TSC accountability in accordance with EP G-4. [ ] h. Refer to EP G-5 for evacuation guide-lines if at ALERT level or higher. [ ] i. Ensure tour personnel and others are notified in accordance with OM I .ID4. [ ] j. Request a Security Officer to determine approximate number of vehicles on site. The Sheriffs Department will need this information to determine traffic control needs if evacuation occurs EPEF-1u3r35.DOC 03B 1015.0933

69-20456 10/14/08 Page-2.of,2 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.20 TITLE: Security Advisor (SA) Checklist

2. Continuing Actions

[] a. Determine the need for additional Security personnel for EOF and JMC security. [ ] b. Perform any required continued behavioral observation. Complete both the "Observed Behavior Checklist," and the "Fitness For Duty Call-Out," forms. [ ] c. Coordinate access of approved personnel through Avila Gate. [ ] d. Obtain SEC approval prior to allowing non-plant personnel through on-site or into PA. [ ] e. Maintain tracking of security officer locations in event of a release. [ ] f. When SEC directs evacuation or early dismissal of nonessential site personnel, then assign a member of the Security force to become the Site Evacuation Coordinator. [ ] g. IF there is a verified bomb threat, THEN direct the security forces to sweep all Emergency Response Facilities. [1 h. Coordinate site access for NRC Relief Teams with NRC Security / Safeguards Coordinator. [] i. Upon receipt of the NRC Initial Site Team from Arlington, Texas: [ ] 1) Brief the SEC/ASEC on the NRC Roster and ETA. [ ] 2) Advise the Facilities Liaison about the NRC Roster and ETA so that the Liaison can keep the EOF informed. [] j. Upon the arrival of the NRC Initial Site Team: [ ] 1) Brief your NRC Co-locator (NRC Safeguards/Security Coordinator) on the emergency developments, mitigating actions, and current activities. [ ] 2) Ensure the NRC Co-locator is familiar with telephone use, information flow, and has copies of the same documents used for your position. [] k. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. EPEF-1u3r35.DOC 03B 1015.0933

69_ý04ýV-13 " 04/15/04 Page I of I DIABLO CANYON POWER PLANT EP EF-1I ATTACHMENT 6.21 1 AND TITLE: Maintenance Logistics Advisor (MLA) Checklist Name: Date:

1. Initial Actions

[] a. Sign in on the Assembly and Accountability Checklist form as applicable. [1 b. Sign in on the TSC sign-in board. [] c. Determine the nature of the emergency and prepare for emergency repair work or mitigating actions by the Maintenance Department. [ 3 d. Contact the OSC Emergency Maintenance Coordinator and determine maintenance staffing. [ ]e. Use the NERC to Contact On-Call Warehouse (Site Materials) representative, if materials assistance is required. [ ] f. Determine the required Maintenance craft personnel needed for response to the event. [] g. Request that the Administrative Advisor verify call-out of necessary maintenance craft personnel.

2. Continuing Actions

[] a. Assist in coordinating team assignments with the SEC. [ ] b. Inform the OSC of team priorities. [ ] c. Inform the OSC of changes in plant status, emergency classification or plant conditions that may impact in-plant emergency response team activities. [ ] d. Keep the SEC informed of significant in-plant team activities, such as dispatch of a team, or reporting of results by a team. [ ] e. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and any other information required for performance of their duties. EP EF-1u3r35.DOC 03B 1015.0933

69-20458 06/21/02 Page I of I DIABLO CANYON POWER PLANT ATTACHMENT 6.22 1 AND2 TITLE: Administrative Advisor (AA) Checklist Name: Date:

1. Initial Actions

[ ] a. Sign in on the Assembly and Accountability Checklist form. [ ] b. Sign in on the TSC sign-in board. [ ] c. Determine clerical staffing needs in each of the following facilities by contacting the: [] 1) OSC - OSC Access Supervisor [ ] 2) EOF - Advisor to the County [ ] 3) UDAC - Radiological Manager [ ] 4) JMC - Emergency Public Information Manager [ ] d. Ensure TSC sign-in staffing board has been signed by all TSC personnel present. [ ] e. Assign clerical personnel to: [] 1) Telephone Operator/Administrative Advisor's area [] 2) Radiological area [ ] 3) Management area [ ] 4) Ensure office equipment (fax, copy machines) is working and functional [ ] f. Develop plans for providing food and water to emergency response facilities for a long-term event. [] g. Establish 24-hour shift manning schedules (12 hour shifts) for the TSC, OSC, EOF, and JMC. Coordinate with each facility. The emergency planning webpage may be used to print out team rosters. [] h. Establish communications with the Nuclear Logistics Coordinator (NLC).

2. Continuing Actions

[ ] a. Ensure copies of shift schedules are faxed to each facility. [1 b. Consider the following factors affecting the ability of second shift personnel to respond to DCPP: [ ]1) Accessible routes to DCPP [ 3 2) Evacuated sectors and associated evacuation time estimates [ 3) Impact of evacuation on families [ ] 4) Relocation Centers and available communications [] 5) Available transportation [ ] c. Arrange for temporary lodging as needed. [ ] d. Develop plans for providing transportation for on and off-site personnel as directed. [ j e. Arrange for janitorial services for emergency response facilities. Plan on a long-term event. [ ] f. Provide shift relief with turnover of important information. Include logs, plant status summaries, protective action summaries, activities in progress and other information required for performance of their duties. EPEF-1u3r35.DOC 03B 1015.0933

69-20459 10/14/08 Page I of 8 DIABLO CANYON POWER PLANT TITLE: EP EF-1 ATTACHMENT 6.23 Operation of the TSC Ventilation System I1AN2 Instructions are provided to establish an abnormal mode of ventilation for the TSC or a loss of the TSC HVAC compressor. TSC alarm panel with the expected alarm responses are also described. Definitions Mode 1 - Normal Operation of the ventilation system in any mode other than Mode I is considered an abnormal operation. Mode 2 - Fire within the Control Room This mode only concerns the control room in the event of a fire. Mode 3 - Recirculation The control room is manually isolated when the operators smell or confirm a toxic or flammable gas entering from outside. The TSC is manually isolated also. Mode 4 - Pressurization Pressurization, Mode 4, is automatically initiated on high radiation or safety injection signals. The TSC ventilation system must be manually aligned for Mode 4. NOTE: Mode 4 may be used after prolonged periods of Mode 3 to purge the C02 which has accumulated in the TSC. Loss of TSC ItVAC (OS-92) compressor The HVAC compressor may trip during operation. Symptoms Mode 3 - Recirculation Mode 4 - High Radiation The following control room main annunciators may sound:

"Control Room Ventilation" (PK15-06)
"High Radiation" (PKI 1-21)
"Containment Isolation Phase A &.B" (PK02-01)

EPEF-1u3r35.DOC 03B 1015.0933

69-20459 10/14/08 Page 2 of 8. EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System The following TSC alarm panel annunciators may sound:

High radiation in TSC area (AA-1)
High radiation in TSC airflow (AA-2)
High radiation in lab area of TSC (AB-1)
High radiation in lab area airflow (AB-2)

Loss of TSC HVAC (OS-92) compressor:

Higher than normal temperatures in the TSC
TSC alarm panel window BF, TSC Area Air Condition Off

1. Automatic Actions The control room ventilation system may transfer to Mode 3 or 4. There are no automatic actions for the TSC ventilation system.

2. Immediate Actions

a. Upon notification of initiation of Mode 3 from the control room perform the following functions to align the TSC for Mode 3 operation:

[ ] 1) Stop the TSC outside (make up) air fan OS-93 using local push button switch. [ ] 2) Start the TSC lead filter supply fan OS-94 using local push button switch. (If not operable, close discharge damper, open discharge damper on OS-95 and start OS-95.) [1 3) Close vent damper 0-18 manually. [ ] 4) Verify that vent damper 0-17 is closed. [ ] 5) Open vent damper 0-26 manually. [ ] 6) Verify the following at the annunciator panel PK-75, located in the TSC computation center: NOTE: If these annunciator lights cannot be verified, consult "TSC Annunciator Panel" table for further instructions. [ ] a) AE "TSC MODE I NORMAL VENT" not illuminated. [] b) BA "NORMAL VENT DAMPER CLOSED" 0-MD-18 illuminated. [] c) BB "CARBON FILTER DAMPER OPEN" 0-MD-26 illuminated. [ ] d) BC "NORMAL VENT ON" OS-93 not illuminated. [] e) BD "CARBON FILTER LOW AIR FLOW" not illuminated. [ ] f) BE "LAB AREA AIR COND. OFF" OS-90 not illuminated. [1 g) BF "TSC AREA AIR COND. OFF" OS-92 not illuminated. [] h) CA "LEAD DUCT HEATER ON" not illuminated. [] i) CC "REDUN DUCT HEATER ON" not illuminated. [ ] j) CE "LEAD SUPPLY FAN ON" OS-94 illuminated. [ ] k) CF "REDUN SUPPLY FAN ON" OS-95 not illuminated. [] 1) DD "PRESS DAMPER OPEN" not illuminated. EPEF-lu3r35.DOC 03B 1015.0933

     ý'V5 69-20
                 'A 10/14/08                                                                     Page 3 of 8 EP EF-1 (UNITS 1 AND 2)

ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System

b. When the TSC ventilation system must be in Mode 4, align the TSC HVAC.

[] 1) Stop the TSC outside (make up) air fan OS-93 using local pushbutton switch. [ ] 2) "Start the TSC lead filter supply fan OS-94. (If not operable, close vent damper 0-24, open vent damper 0-25 on OS-95 and start fan OS-95.) [1 3) Close vent damper 0-18 manually. [1 4) Open vent damper 0-17 manually. [1 5) Open vent damper 0-26 manually. [ ] 6) Verify the following at annunciator panel PK-75, in the TSC computation center: NOTE: If any of these annunciator lights cannot be verified, consult "TSC Annunciator Panel" table for further instructions. [ ] a) AE "TSC Mode 1 Normal Vent" not illuminated. [1 b) BA "Normal Vent Damper Closed" illuminated. [ ] c) BB "Carbon Filter Damper Open" illuminated. [ ] d) BC "Normal Vent Fan On" not illuminated. [ ]e) BD "Carbon Filter Low Air Flow" not illuminated. [1 f) CA "Lead Duct Heater On" illuminated. [ ] g) CC "Redun Duct Heater On" not illuminated. [ ] h) CE "Lead Supply Fan On" illuminated or [ I i) CF "Redun Supply Fan On" illuminated as required. [] j) DD "Press Damper Open" illuminated. [1 7) Close or verify closed the following doors: [] a) Mechanical room outside water tight door (BU 215-2)

Post "Door Closure" sign on outside
Post "Door Closure" sign on inside

[ ] b) Laboratory outside water tight door (West) (BU 219-2)

Post "Door Closure" sign on outside

                    " Post "Door Closure" sign on inside

[] c) Computation center outside water tight door (BU 206-2)

Post "Door Closure" sign on outside
Post "Door Closure" sign on inside NOTE: Obtain permission from RP to exit via the NRC Office outside water tight door (BU 211-2), exit from that door to secure the Laboratory outside water tight door (West)

(BU 216-2) then return via door BU 211-2 securing it behind you as noted in step e) below. [ ] d) Laboratory outside water tight door (East) (BU 216-2)

Post "Door Closure" sign on outside
Post "Door Closure" sign on inside

[ 3 e) NRC Office outside water tight door (BU 211-2)

Post "Door Closure" sign on outside

                    " Post "Door Closure" sign on inside EPEF-1u3r35.DOC        03B       1015.0933

69-20459 10/14/08 iýANýii Page 4ý01f8 EP EF-1 (UNITS I AND 2) ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System Loss of TSC HVAC compressor CAUTION: Do NOT adjust the TSC HVAC thermostat [ ] 1) IF loss of the TSC HVAC compressor is indicated by the TSC alarm panel, window BF, "TSC Area Air Conditioning OFF," THEN attempt to restart the compressor by turning the ON/OFF switch, located at the thermostat next to the main TSC entrance door (Buttress Area), to OFF for 10 seconds, then ON. This action resets the high compressor head pressure trip.

2) IF the previous step did not restart the compressor, THEN dispatch a person to the TSC ventilation room to perform the following;

[ ] a) Remove the lower covers on TSC HVAC A/C unit, OS-92. [ ] b) Depress the reset for the motor high temperature trip, located in the upper left comer of the right opening (red button in a black box). [ ] c) Check the oil level sightglass below the reset switches, there musf be oil visible in the sightglass. [ ]d) IF there is no oil in the sightglass, THEN return to the TSC and notify maintenance for repairs. [ ] e) Depress the reset for the low oil pressure trip, located directly below the motor high temperature trip reset (silver button in a white box). [ ] f) Return to the TSC HVAC thermostat and turn the ON/OFF switch to OFF for 10 seconds, then ON. [ ] g) IF the above actions did not reset the compressor, THEN notify the TSC Maintenance Advisor for assistance. NOTE: High head pressure may be identified by a high outlet temperature, greater than 120'F, or a low outlet/inlet temperature difference of less than 10°F. The thermometers are located to the left of the OS-92 unit. Bubbles in the sightglasses on the liquid lines may indicate low suction pressure. These sightglasses are located in the lower left compartment. Liquid line solenoid failure may be checked by touching the solenoids by the liquid line sightglasses. If they are not warm, then they may not be working. The unit air filter may be clogged. Access is on the right of the front of the unit. EP-EF-106r5.DOC 03B 0.93 1015.0933

69-20459ý;,,-zi 10/14/08 Page 5 of 8 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System

3. Subsequent Actions a) Returning to Mode 1 Operation The control room will place the control room ventilation mode selector switch located at vertical board IVB4 (2VB4) in the Mode I position to return the control room ventilation system to normal operation.

The TSC ventilation system must be manually returned to normal by performing the following: [ ] 1) Stop Lead Supply Fan OS-94 (and OS-95 if started). [ ]2) Start Outside (make up) Air Fan OS-93. [ ] 3) Damper 0-18 opened manually. [ 1 4) Damper 0-17 closed manually. [ ] 5) Damper 0-26 closed manually. [ 1 6) Damper 0-26 closed manually. b) Restoring Door Closure signs to Mode 1 Operation. [ ] a) Mechanical room outside water tight door (BU 215-2)

                 " Restore "Door Closure" to "Do Not Remove" on outside
                 " Restore "Door Closure" to "Do Not Remove" on inside

[ ]b) Laboratory outside water tight door (West) (BU 219-2)

Restore "Door Closure" to "Do Not Remove" on outside

                 " Restore "Door Closure" to "Do Not Remove" on inside

[ J c) Computation center outside water tight door (BU 206-2)

Restore "Door Closure" to "Do Not Remove" on outside

                 " Restore "Door Closure" to "Do Not Remove" on inside

[ ] d) Laboratory outside water tight door (East) (BU 216-2)

                 " Restore "Door Closure" to "Do Not Remove" on outside
                 " Restore "Door Closure" to "Do Not Remove" on inside

[ ] e) NRC Office outside water tight door (BU 211-2)

                 " Restore "Door Closure" to "Do Not Remove" on outside

Restore "Door Closure" to "Do Not Remove" on inside EPEF-1u0r35.DOC 03B 1015.0933

a 69-20459 10/14/08 . Page,6_of 8 EP EF-1 (UNITS 1 AND 2) ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System

b. TSC Annunciator Panel The following is a list of each TSC annunciator panel light with information included on what to do in the event a light does not function properly.

Window Information AA-1 (RED) High radiation in TSC area. If illuminated, notify the Radiological Advisor for evaluation and response. AA-2 (RED) High radiation in TSC airflow. If illuminated, notify the Radiological Advisor for evaluation and response. AB-1 (RED) High radiation in lab area of TSC. If illuminated, notify the Radiological Advisor for evaluation and response. AB-2 (RED) High radiation in lab area airflow. If illuminated, notify the Radiological Advisor for evaluation and response. AC SPARE. Not illuminated. AD SPARE. Not illuminated. AE TSC Mode 1 Normal Ventilation. Illuminated in normal operation Mode 1. AF SPARE. Not illuminated. BA "Normal Vent Damper Closed," 0-MD-18. If illuminated in Mode 1, verify manual operated damper 0-18 is closed. BB "Carbon Filter Damper Open," 0-MD-26. Illuminated when damper 0-26 is open in Mode 1 operation. If illuminated in Mode 1, verify manually operated damper 0-26 is closed. BC "Normal Vent Fan On," OS-93. Illuminated in normal operation Mode 1. Should be off in Mode 3 or 4 operation. BD "Carbon Filter Low Air Flow," FB-94. Illuminated when there is not enough airflow through carbon filters. Check lead and redundant supply fans OS-94 and OS-95 for one of them to be running with corresponding damper open, 0-24 or 0-25 in Modes 3 or 4. Normally illuminated in Mode 1. BE "Lab Area Air Condition Off," OS-90. Illuminated if air conditioning is off. Notify Electrical Maintenance. BF "TSC Area Air Condition Off," OS-92. Illuminated when air conditioner for TSC is not in operation. Notify Electrical Maintenance. EPEF-1u3r35.DOC 03B 1015.0933

69-204,59. - ý 10/14/08 Page 7 of 8 EP EF-1 (UNITS I AND 2) ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System Window Information CA "Lead Duct Heater On," OEH-28A. Illuminated in proper Mode 4 operation. Heater maintains incoming air humidity low for best charcoal filter operation. May not activate if incoming air is sufficiently warm. CB "Lead Duct Heater Malfunction," OEH-28A. Illuminated when a malfunction is triggered in Mode 4 operation. To troubleshoot check the following: [ ] 1) Check circuit breaker panel PPTSC3 to be on. [ ] 2) Check motor starter switch LPTSC3 to be on with green light illuminated. [ ] 3) Check damper 0-17 to be open. [ ] If the lead duct heater still will not function, turn the starter switch LPTSC3 off and energize LPTSC4 for redun. supply heater OEH28B. CC "Redun Duct Heater On" OEH-28B. Illuminated in proper Mode 4 operation. CD "Redun. Duct Heater Malfunction," OEH-28B. Illuminated when a malfunction has tripped a sensor. To trouble shoot, check the following: [1]1) Check circuit breaker panel PPTSC4 to be on. [ ] 2) Check motor starter switch LPTSC4 to be on with green light illuminated. [ 3) Check damper 0-17 to be open. [ ] If both OEH-28A and OEH-28B cannot be energized, notify control room that Mode 4 operation of ventilation system is not functioning. CE "Lead Supply Fan On" OS-94. Illuminated in normal Mode 3 or 4 operation. If inoperable in Mode 3 or 4, check the following: [ ] 1) Check circuit breaker panel PPTSC-6 to be on. [ 2) Check at local disconnect switch LPTSC-5, place in ON position and verify green light is illuminated. [ ] 3) Press start button and verify green light is out and red light is illuminated with fan running. [ 4) Verify corresponding damper is open 0-24 or 0-25. [ 3 If the fan will not operate properly, turn local disconnect switch LPTSC-5 off and LPTSC-6 on for fan OS-95. EP-EF-106r5.DOC 03B 0593 1015.0933

69-20459 10/14/08 Page 8 of 8 EP EF-1 (UNITS I AND 2) ATTACHMENT 6.23 TITLE: Operation of the TSC Ventilation System Window Information CF "Redun. Supply Fan On" OS-95. Illuminated in Mode 3 or 4 when OS-94 is not functioning. Notify the control room of malfunction. DA "TSC Radiation Monitor Failure And Loss of AC Power." Illuminated when the TSC radiation monitor fail or lose AC power. Switch the TSC to vital AC power. If still illuminated, notify the shift foreman. DB "Fire Detector." Illuminated when fire is detected in HVAC Room. DC "UPS Malfunction." Notify Electrical Maintenance. DD "Pressurization Damper Open" 0-MD-17. Illuminated when damper 0-17 is open. Damper 0-MD-17 must be closed in Mode 1, open in Mode 4. DE "TSC Open Ctr Air Cond On," OS-100. Air conditioner in the operations room is on. Notify Electrical Maintenance if not illuminated. EPEF-1u3r35.DOC 03B 1015.0933}}

DCL-08-096, Emergency Plan Implementing Procedure Update

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Dear Commissioners and Staff:

3.3.1 Coordinates

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DCL-08-096, Emergency Plan Implementing Procedure Update

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Dear Commissioners and Staff:

3.3.1 Coordinates

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