Text

Licensee Radiation Work Permit No.04-133
	ML050880089
Person / Time
Site:	Point Beach
Issue date:	03/31/2004
From:	; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	FOIA/PA-2004-0282, RWP-04-133
	Download: ML050880089 (54)
	v • d • e

{{#Wiki_filter:Nuclear Power Business Unit RADIATION WORK PERMIT ."A~ cn,H,: Revision: 0 RNN'P Number: 04-133 Controlling Work Document: Various RG 1.16 Class: 2 Estimated Dose: 6.100 rem Job

Title:

BMI Inspection Job Location: Unit I Containment Keyway Job

Description:

Under Vessel Inspection and Associated Activities Radiological Assessment of Work Significant increase in radiation levels is likely? EYes ONo Reason: Significant increase in contamination levels is likely? OYes [No Reason: Insulation Removal/Building Activities Potential for internal dose? ZYes EINo Reason: Building Activities RWA'P Tasks Task 1: Scaffold Installation / Removal Task 2: Remove Old Insulation Task 3: Install New Insulation Task 4: Decon Activities Task 5: NDE Activities Task 6: RP Activities Task 7: Task 8: Task 9: Task 10: Task 11: Task 12: RWP Review and Approval Prepared By: CD 2/24/04 Initials Date ALARA Review By: WWL 2-24-04 ALARA Review No.: 0 N/A 0 2004-0012 Initials /2 Date Approved By: 0 /c.. RP Supenrir Date Terminated By: RP Supervisor Date IPBF-4031 (C 2,- lo Revision 12 12/10/03 IIP l.10.!P6.8 Page I of 13

Nuclear Power Business Unit RADIATION WVORK PERMIT Revision: 0 RWPNumber: 04-133 TASK 1: Scaffold Installation / Removal Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWVP conditions. Stop Work Dose Rate: 10OOmR/hr ED Dose Rate Alarm: 255mR/hr ED Dose Alarm: 100lmRem Radiation Protection Hold Points: ON/A No entry to keyway without RP permission. Perform entry in accordance with HP 2.14. Authorized Radiological Work Areas: Any RWP permits entry into RCA(s), RMA, and RA. 0 HRA ED LIRA E \\'HRA El Ctmt,ReactorCritical 0 CA 0 HCA 0 HPCA 0 AirbomeRadioactivityArca Expected Radiological Conditions: Data From: a] Current Survey 0D Historical Data 0 Estimated Radiation: GA 3 to 200 mrem/hr

Contact:

3 to 500 mren/hr Contamination: 300 to 160k dpmr100cm2 Internal Contamination: 300 to >IE6 dpm/100cm2(0 estirmated) Airborne Radioactivity: <.25 DAC El P El 12 El NG El 'H (0 Estimatcd / El Actual DAC) RP Job Coverage: El Routine 0 Direct El StartofJob D SystemBreach 0 Pre-JobBriefingRequired Special Instructions: Perform entry in accordance with HP 2.14. Direct RP Coverage for all Keyway entries. Camera surveillance may be substituted for direct coverage when keyway is down posted to a LHRA. pagod J d -6 rnloSC-RiO8it y-ia~z*<^,, &,s-fenr zmLoq8 d o, SZJ Av/R VAst. AJ9 Le7L EZ ~-//0Y/ Radiological Survey Requirements: A. Radiation: El Priorto/StartofWork El SystemBreach 0 Other Special Instructions: Conditions to be verified prior to entry. Additional requirements as per RP. B. Contamination: El Prior to/Start of Work EJ System Breach E Other Special Instructions: Conditions to be verified prior to entry. Hot Particle surveys as necessary. Additional requirements as per RP. C. Airborne: El Priorto/StartofWork El SystemBreach 0 Other Special Instructions: As Per RP. PBF-403 1 Revision 12 12/10103 1IP.10.'P1.8 Page 2 Of 13

SJ Nuclear Power Business Unit RADIATION WVORK PERMIT Revision: o 0 {/ ( A I I-III. Dose Assessment: TLD and EPD required. Special Instructions: Whole Body TLD relocation based on survey results. RWVP Number: 04-133 IV. Protective Clothing 0D Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) El Labcoat, Booties, and Rubber Gloves may be used only with RP permission. 0 Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves. ( for HCA entry) D Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots., a Plastic suit, Double Rubber Gloves, Double Booties, Rubber Totes/Boots.' 0 Leather Gloves may be substituted for Rubber Gloves with RP permission. ED Hood and Face Shield required per RP. 0 Other: See Special Instructions ' Safety review may be required for additional coveralls or plastics. Special Instructions: Specific entry requirements per RP based on survey results. V. Respiratory Protection: ON/A E TEDE ALARA Review: NONE Special Instructions: VI. Engineering Controls: Special Instructions: VIl. ALARA Requirements: LDWA: RP to identify E] See ALARA Review Special Instructions: Foreign debris found within the refueling cavity, SIG channel head, or primary systems may be highly radioactive and shall not be handled without RP permission. When working in these areas orhandling equipment from these areas (such as refueling tools) workers shall monitor at least every two hours.. Contact RP immediately if, during monitoring of protective clothing, the worker discovers >10,000 cpm above bkg using a frisker or >5 mRem/hr above bkg using an open window beta instrument. Contact RP immediately if, during monitoring of skin, personal clothing, or modesty garments any contamination above bkg is discovered. PB-403 1 Revision 12 12/10/03 HlP 1.10T'16.8 Page 3 of 13

Nuclear Power Business Unit RADIATION WVORK PERMIT Revision: 0 n RWN'P Number: 04-133 TASK 2: Remove Old Insulation Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWP conditions. a "A Amin i' No 141 1'-' lJm~em Stop WNork Dose Rate: 500mR/hr ED Dose Rate Alarm: 255rnP/hr ED Dose Alarm: Radiation Protection Hold Points: LIN/A No entry to keyway without RP permission. Perform entry in accordance with HP 2.14. Authorized Radiological Work Areas: Any RWP permits entry into RCA(s), RAIA, and RA. 0 HRA 0 LHRA 0 VHRA E] Ctmt, ReactorCritical 0 CA ED HCA 0 HPCA 0 Airborne Radioactivity Area Expected Radiological Conditions: Data From: DI Current Survey 0 Historical Data 0 Estimated Radiation: GA 3 to 200 rnrcm/hr

Contact:

3 to 500 mrem'hr Contamination: 300 to 160k dpm1l00 cm2 Intemal Contamination: 300 to 1E6 dpmV 100 cm2(Z estimated) Airborne Radioactivity: <.25 DAC 0 P 0l 12 El NG El 3H (0 Estimated I El Actual DAC) RP Job Coverage: El Routine Z Direct El StartofJob El SystemBreach 0 Pre-JobBriefingRequired Special Instructions: Perform entry in accordance with HP 2.14. Direct RP Coverage for All Keyway Entries. Camera surveillance may be substituted for direct coverage when keyway is down posted to a LHRA. Radiological Survey Requirements: A. Radiation: Special Instructions: B. Contamination: Special Instructions: C. Airborne: Special Instructions: n Prior to/Start of Work n System Breach E Other Conditions to be verified prior to entry. Additional requirements as per RP. El Prior to/Start of Work a System Breach 0 Other Conditions to be verified prior to entry. Hot Particle surveys as necessary. Additional requirements as per RP. E Prior to/Start of Work al System Breach ED Other As Per R.P. PBFr4031 Revision 12 12/10/03 1IP 1.l0!P6.8 Page 4 of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 P J Z III. Dose Assessment: TLD and EPD required. Special Instructions: Whole Body TLD relocation based on survey results. RX 'P Number: 04-133 IV. Protective Clothing 0 Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) El Labcoat, Booties, and Rubber Gloves may be used only with RP permission. 0 Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves. ( for HCA entry) a Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots.' 0 Plastic suit, Double Rubber Gloves, Double Booties, Rubber Totes/Boots.' 0 Leather Gloves may be substituted for Rubber Gloves with RP permission. 0 Hood and Face Shield required per RP. 0 Other: See Special Instructions ' Safety review may be required for additional coveralls or plastics. Special Instructions: Specific entry requirements per RP based on survey results. V. Respiratory Protection: ON/A 0 TEDE ALARA Review: Special Instructions: Additional requirements as per RP Supervision. VI. Engineering Controls: Special Instructions: HEPA Vac. required for removal activities. VII. ALARA Requirements: LDWA: RP to identify. a See ALARA Review Special Instructions: Foreign debris found within the refueling cavity, S/G channel head, or primary systems may be highly radioactive and shall not be handled without RP permnission. When working in these areas or handling equipment from these areas (such as refueling tools) workers shall monitor at least every two hours.. Contact RP immediately if, during monitoring of protective clothing, the worker discovers >10,000 cpm above bkg using a frisker or >5 mRemlhr above bkg using an open window beta instrument. Contact RP immediately if, during monitoring of skin, personal clothing, or modesty garments any contamination above bkg is discovered. PBF-403 1 Rcvision 12 12!10103 IIP 1.106SPe.8 Page 5 of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 A .3) RXIP Number: 04-133 TASK 3: Install New Insulation Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWP conditions. Stop WVork Dose Rate: 500mR/hr ED Dose Rate Alarm: 255mRJhr ED Dose Alarm: ____Re_____ LI Radiation Protection Hold Points: [EN/A No entry to keyway without RP permission. Perform entry in accordance with HP 2.14. Authorized Radiological Work Areas: Any RWNIP permits entry into RCA(s), RMA, and RA. ED HRA 0 LHRA 0 VHRA a Ctrnt, Rcactor Critical 0D CA 0 HCA 0 HPCA 0 Airborne Radioactivity Area Expected Radiological Conditions: Data From: El Current Survey CD Historical Data 0 Estimated Radiation: GA 3 to 200 mrem1hr

Contact:

3 to 500 mrenihr Contamination: 300 to 160k dpnmlOO cm2 Internal Contamination: 300 to IE6 dpmnI00 cm2 (N estimated) Airborne Radioactivity: <.25 DAC 0 P D 12 0 NG El 'H (09 Estimated / a Actual DAC) RP Job Coverage: E] Routine 0 Direct E] Start of Job El System Breach 0 Pre-Job Briefing Required Special Instructions: Perform entry in accordance with HP 2.14. Direct RP Coverage for All Keyway Entries. Camera surveillance may be substituted for direct coverage when keyway is down posted to a LHRA. _ etfJOMff1 Zul&*r PIL-W&~ pSTh W4MAL C-tf Fropt LEA C-tJML(. 4140t-L% 4Be INVLA sore t9/ Radiological Survey Requirements: A. Radiation: El Prior to/Start of Work E System Breach 0 Other Special Instructions: Conditions to be verified prior to entry. Additional requirements as per RP. B. Contamination: El Prior to/Start of Work a System Breach 0 Other Special Instructions: Conditions to be verified prior to entry. Hot particle surveys as necessary. Additional requirements as per RP C. Airborne: El Priorto/StartofWork E SystemBreach 0 Other Special Instructions: As Per RP. PBF-403 1 Revision 12 12/10!03 HP 1.10 P6.8 Page 6 of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 III. Dose Assessment: TLD and EPD required. RWN'P Number: 04-133 I Special Instructions: Whole Body TLD relocation based on survey results. IV. Protective Clothing ED Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) Ea Labcoat, Booties, and Rubber Gloves may be used only with RP permission. ED Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves. ( for HCA entry) El Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots., D Plastic suit, Double Rubber Gloves, Double Booties, Rubber Totes/Boots.' 0 Leather Gloves may be substituted for Rubber Gloves with RP permission. 0 Hood and Face Shield required per RP. 0 Other: See Special Instructions XSafety review may be required for additional coveralls or plastics. Special Instructions: Specific entry requirements per RP based on survey results. V. Respiratory Protection: O]N/A ED TEDE ALARA Review: Special Instructions: Additional requirements as per RP Supervision. VII. Engineering Controls: Special Instructions: VII. ALARA Requirements: LDWA: RP to identify Cl See ALARA Review Special Instructions: Foreign debris found within the refueling cavity, S/G channel head, or primary systems may be highly radioactive and shall not be handled without RP permission. When working in these areas or handling equipment from these areas (such as refueling tools) workers shall monitor at least every two hours. Contact RP immediately if, during monitoring of protective clothing, the worker discovers >10,000 cpm above bkg using a frisker or >5 mRemnhr above bkg using an open window beta instrument. Contact RP immediately if, during monitoring of skin, personal clothing, or modesty garments any contamination above bkg is discovered. PBF-403 1 Revision 12 12/10103 lip 1.10!1'6.8 Page 7of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 RWP Number: 04-133 TASK 4: Decon Activities Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWP conditions. W _ Stop Work Dose Rate: 500mR/hr ED Dose Rate Alarm: 255mPJRhr ED Dose Alarm: 1O66mRem Radiation Protection Hold Points: EN/A No entry to keyway without RP permission. Perforn entry in accordance with HP 2.14. Authorized Radiological 'ork Areas: Any RWP permits entry into RCA(s), RMA, and RA. 0 HRA 0 LHRA 0 VIHRA Dl Ctmt, Reactor Critical 0D CA 0 HCA 0D HPCA ED Airborne Radioactivity Area Expected Radiological Conditions: Data From: D3 Current Survey 0 Historical Data 0 Estimated Radiation: GA 3 to 200 mremlhr

Contact:

3 to 500 mrem/hr Contamination: 300 to 160k dpm/l00 cm2 Internal Contamination: 300 to IE6 dprn/l00 cm2(2 estimated) Airborne Radioactivity: <.25 DAC 0 P 0 12 0 lNG 0 'H (0D Estimated / a3 Actual DAC) RP Job Coverage: El Routine [ Direct El Start of Job [] System Breach 3 Pre-Job Briefing Required Special Instructions: Perform entry in accordance with HP 2.14. Direct RP Coverage for All Keyway Entries. Camera surveillance may be substituted for direct coverage when keyway is down posted to a LHRA. f&J-f~t QPf-Vkj8A-f12.IbI TV ~)74~u$~.y. 14,c14 r,5 t.1 ~ ~-'7L FoI Itf~4 ~ t~X-~/cL fRfJd iologia _ elp w4 lvA-l4 f rL EVA Surve q / uirem6 Radiological Survey Requirements: A. Radiation: El Prior to/Start of Work E1 System Breach Z Other Special Instructions: Conditions to be verified prior to entry. Additional requirements as per RP. B. Contamination: Special Instructions: C. Airborne: Special Instructions: a Prior to/Start of Work E] System Breach 0 Other Conditions to be verified prior to entry. Hot particle surveys as necessary. Additional requirements as per RP. n Prior to/Start of Work El System Breach Z Other As Per RP. I'IBF-403 1 Rcvision 12 12110/03 fi1' 1.10!1'6.8 Page 8 of 13

Nuclear Power Business Unit RADIATION NWORK PERMIT Revision: 0 o 7 III. Dose Assessment: TLD and EPD required. Special Instructions: Whole Body TLD relocation based on survey results. RNVP Number: 04-133 = IV. Protective Clothing 3 Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) al Labcoat, Booties, and Rubber Gloves may be used only with RP permission. 23 Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves. ( for HCA entry) a Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots. E Plastic suit, Double Rubber Gloves, Double Booties, Rubber Totes/Boots.' 3 Leather Gloves may be substituted for Rubber Gloves with RP permission. %3 Hood and Face Shield required per RP. 3 Other: See Special Instructions 'Safety review may be required for additional coveralls or plastics. Special Instructions: Specific entry requirements per RP based on survey results. V. Respiratory Protection: ON/A E TEDE ALARA Review: Special Instructions: Additional requirements as per RP Supervision. VIII. Engineering Controls: Special Instructions: HEPA Vac to be used as applicable. Keep work wet during decon. 'VII. ALARA Requirements: LDWN'A: RP to identify El See ALARA Review Special Instructions: Foreign debris found within the refueling cavity, S/G channel head, or primary systems may be highly radioactive and shall not be handled without RP permission. When working in these areas or handling equipment from these areas (such as refueling tools) workers shall monitor at least every two hours. Contact RP immediately if, during monitoring of protective clothing, the worker discovers >10,000 cpm above bkg using a frisker or >5 mRemhr above bkg using an open window beta instrument. Contact RP immediately if, during monitoring of skin personal clothing, or modesty garments any contamination above bkg is discovered. PBW4031 Revision 12 12/10/03 VlIP l.10/P6.P Page 9 of 13

Nuclear Power Business Unit RADIATION WVORK PERMIT Revision: 0 /';z 6z 2 RWN'P Number: 04-133 11 TASK 5: NDE Activities Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWP conditions. /00) Stop Work Dose Rate: 500mR/hr ED Dose Rate Alarm: 255mRfhr ED Dose Alarm: JO~mRe 4 Radiation Protection Hold Points: EN/A No entry to keyway wvithout RP permission. Perform entry in accordance with HP 2.14. Authorized Radiological Work Areas: Any RWP permits entry into RCA(s), RMA, and RA. 0D HRA 0 LHRA 0D VHRA

1 Ctmt, Reactor Critical 0D CA 0 HCA 0D HPCA 0 Airborne Radioactivity Area Expected Radiological Conditions:

Data From: [3 Current Survey 0 Historical Data ED Estimated Radiation: GA 3 to 200 mrem/hr

Contact:

3 to 500 mrem/hr Contamination: 300 to 160k dpm/l00 cm2 Internal Contamination: 300 to IE6 dpm/I00 cm2(0 estimated) Airbornc Radioactivity: <.25 DAC 0 P El 12 0l NG T3 3H (ED Estimated / El Actual DAC) RP Job Coverage: El Routine 0 Direct a Start of Job El System Breach 0 Pre-Job Briefing Required Special Instructions: Perform entry in accordance with HP 2.14. Direct RP Coverage for All Keyway Entries. Camera surveillance may be substituted for direct coverage when keyway is down posted to a LHRA. f'o-# izo 6 N,F e., j Di7 .to - rv I IJ-I4L s t%,'L 'A ErJn)L 1. s a g Po A, V V-&4 6. - fY/Ia Radiological Survey Requirements: A. Radiation: Special Instructions: B. Contamination: Special Instructions: C. Airborne: Special Instructions: E Prior to/Start of Work El System Breach 0 Other Conditions to be verified prior to entry. Additional requirements as per RP. El Prior to/Start of Work El System Breach 0 Other Conditions to be verified prior to entry. Hot particle surveys as necessary. Additional requirements as per RP El Prior to/Start of Work E System Breach 0 Other As Per RP PBF403 1 Revision 12 12/10/03 11P 1.10OP6.8 Page 10 of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 (r oQ) i ;-- R-l 1%-~ RWN'P Number: 04-133 III. Dose Assessment: TLD and EPD required. Special Instructions: Whole Body TLD relocation based on survey results. IV. Protective Clothing Z Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) El Labcoat, Booties, and Rubber Gloves may be used only with RP permission. 3 Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves. ( for HCA entry) D Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots.' E Plastic suit, Double Rubber Gloves, Double Booties, Rubber Totes/Boots., Z Surgeon's Gloves may be substituted for Rubber Gloves with RP permission. %3 Hood and Face Shield required per RP. 3 Other: See Special Instructions XSafety review may be required for additional coveralls or plastics. Special Instructions: Specific entry requirements per RP based on survey results. V. Respiratory Protection: ON/A 0 TEDE ALARA Review: Special Instructions: Additional requirements as per RP Supervision. IX. Engineering Controls: Special Instructions: VII. ALARA Requirements: LDWA: RP to identify EJ See ALARA Review Special Instructions: Foreign debris found within the refueling cavity, S/G channel head, or primary systems may be highly radioactive and shall not be handled without RP permission. When working in these areas or handling equipment from these areas (such as refueling tools) workers shall monitor at least every two hours. Contact RP immediately if, during monitoring of protective clothing, the worker discovers >10,000 cpm above bkg using a frisker or >5 mRemfhr above bkg using an open window beta instrument. Contact RP immediately if, during monitoring of skin personal clothing, or modesty garments any contamination above bkg is discovered. PBF-4031 Revision 12 12.10:03 lIP 1.0IOP6.8 Page I11 of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 -no RW'P Number: 04-133 TASK 6: RP Activities Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWP conditions. Stop Work Dose Rate: 500mR/hr ED Dose Rate Alarm: 255mR/hr ED Dose Alarm: lOOmRem Radiation Protection Hold Points: EN/A No entry to keyway without RP permission. Perform entry in accordance with HP 2.14. Authorized Radiological Work Areas: Any RSVIP permits entry into RCA(s), RAIA, and RA. 0 HRA CD LHRA CD VHRA E Ctmt, Reactor Critical 0D CA 0 HCA E0 HPCA 0D Airborne Radioactivity Area Expected Radiological Conditions: Data From: C] Current Survey 0 Historical Data 0 Estimated Radiation: GA 3 to 200 mrem/hr

Contact:

3 to 500 mrem/hr Contamination: 300 to 160k dpm'l00 cm2 Internal Contamination: 300 to IE6 dpmll00 cm2 (Z estimated) Airborne Radioactivity: <.25 DAC 0 P 0l 12 El NG El 3H (0D Estimated / El Actual DAC) RP Job Coverage: 2 Routine 0 Direct El Start of Job M System Breach 0 Pre-Job Briefing Required Special Instructions: Performentry in accordance withHP 2.14. fttiJjla Aoat ote- .') PnaV72 I ) P&JI-1AL L-C. r'on.- I-AVIA 6jr-4.t11 4 K7~1-L-7 F=OfL Vq& I Ltnn' 2 -' mefl- +/-/Y/~5L Radiological Survey Requirements: A. Radiation: El Prior to/Start of Work El System Breach 0 Other Special Instructions: Conditions to be verified prior to entry. Additional requirements as per RP. B. Contamination: E Prior to/Start of Work El System Breach 0 Other Special Instructions: Conditions to be verified prior to entry. Hot particle surveys as necessary. Additional requirements as per RP C. Airborne: EJ Prior to!Start of Work El System Breach 0D Other Special Instructions: As Per RP. I'BF-403 1 Rcvision 12 12/10/r03 IHl) IA.0(r/GS Page 12 of 13

Nuclear Power Business Unit RADIATION WORK PERMIT Revision: 0 (r ()) j III. Dose Assessment: TLD and EPD required. RWP Number: 04-133 = Special Instructions: Whole Body TLD relocation based on survey results. IV. Protectivc Clothing Z Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) El Labcoat, Booties, and Rubber Gloves may be used only with RP permission. N Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves. (for HCA entry) 1 Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots.' 0 Plastic suit, Double Rubber Gloves, Double Booties, Rubber Totes/Boots.1 0 Leather Gloves may be substituted for Rubber Gloves with RP permission. 0 Hood and Face Shield required per RP. 0 Other: See Special Instructions a Safety review may be required for additional coveralls or plastics. Special Instructions: Specific entry requirements per RP based on survey results. V. Respiratory Protection: O]N/A 0 TEDE ALARA Review: Special Instructions: Additional requirements as per RP Supervision. X. Engineering Controls: Special Instructions: VII. ALARA Requirements: LDWA: RP to identify a See ALARA Review Special Instructions: Foreign debris found within the refueling cavity, S/G channel head, or primary systems may be highly radioactive and shall not be handled without RP permission.

When working in these areas or handling equipment from these areas (such as refueling tools) workers shall monitor at least every two hours.

Contact RP immediately if, during monitoring of protective clothing, the worker discovers >10,000 cpm above bkg using a frisker or >5 mRemfhr above bkg using an open window beta instrument. Contact RP immediately if, during monitoring of skin personal clothing, or modesty garments any contamination above bkg is discovered. PBF.4031 Revision 12 12/10,'03 1lP 1.1011'6.8 Page 13 Of 13

Point Beach Nuclear Plant Level 3 Pre-Job ALARA Review rr_'Z1QPY ALARA Review Number: 2004-0012 UIR28 Estimated dose: 1 6.10 I Rem Part 1: Job Description A. Job Description Perform inspection of Reactor Vessel Bottom Mounted Instrumentation to meet the (Attach work list if appropriate) requirements of NRC Bulletin 2003-02. Scope includes: Install temporary platform, prepare existing insulation for removal and inspection, remove existing lower reactor vessel head insulation, performn visual inspection of bottom mounted instrumentation, install new lower reactor vessel head insulation. RP and decon. support as required. B. Controlling job procedures. W.O.(s) 304883 for the visual inspection and 304884 for the removal and replacement of the insulation C. Job History/O.E.ALessons See attached O.E.: "Events Involving Overexposures During Entries Into Undervessel Areas Learned at Pressurized Water Reactors" D. Dose history. During U2R26 the nozzles were inspected and the old insulation was replaced using 10.613 ,rem.tSee ALARA review 2003-0023 for additional information. Part 2: ALARA Checklist NOTE: Ache following exposure reduction measures should be considered during job planning. Section 1: Pre-Job Planning/ E. Designated low dose The designated low dose and staging area is on the 21 ' elevation of U I C near the Keyway waiting/staging areas. entrance. The low dose area in the keyway is near the base of the ladder to the 21'. F. Remote job coverage Audio and video equipment will be used for remote job coverage. equipment. G. Communication devices used. Telex radios H. Services required. (lighting, air, Temporary lighting and electrical services will be required and will be installed by C.E. as electrical) required.

1. Designated work area The Keyway hatch is the only access/exit point. The Keyway is a confined space that will be access/exit points.

posted as a Non-permit Confined Space. A RP tech will be posted as a guard at the entrance. J. Coordination with other groups. Coordination will be required between RP, OPS, CE, ENG, NDE and Security. Decision trees have been created detailing the logic path for inspection and repair. A high impact team was created to handle coordination during the project and representatives will be on-site 24 hours during the project. The decision trees are attached. K. Work performed outside of All insulation prefabrication will be performed at the Transco facility in Streator, Ill. Any radiation areas: field modifications will be made on the 21' elevation of U IC if possible. Prefabrication Disassembly Assembly L. Post-job cleanup requirements. The work site will be returned to the same level of cleanliness as before the job started. Engineering will specify cleaning requirements of the Reactor Vessel after insulation removal and NDE inspection. PBF-4195a Rcvision 5 08/15/03 HIP 15.31P6.8 Page I of 2 Refercnce: NP 4.2.1

Point Beach Nuclear Plant Level 3 Pre-Job ALARA Revievw rrzCs[apy ALARARcview Number: 12004-0012 UIR28 I Estimated dose: l 6.10 Rem M. Special tools/equipment used to The insulators will be using electric shears to cut the old insulation off. minimize time and exposure. (Use contaminated tools when practicable) N. Radwaste minimization. Old insulation will be removed and disposed of as radwaste. Other waste generated should be minimal.

0. Work activities/equipment Pulling incore thimbles creates a Very High Radiation Area in the Keyway. This will not be status that could result in allowed while work is performed in the Keyway. Personnel will also not be allowed to work significant interruption ofjob or in the Keyway if large volumes of water are to be drained to the A sump. This will occur changes in radiological during the under Rx vessel head decon.

conditions. Section 2: Radiological Controls P. Describe temporary shielding to None. be used. Q. What systems/components will None. be filled with water or flushed to reduce job area dose rates? R. Engineering controls to control An air-powered vacuum will be used while cutting insulation. Cavity cooling fans will be airborne activity. (HEPA secured while cutting insulation. filters, glove bags, etc.) S. Attach applicable survey data. See attached. Section 3: Worker Preparation and Training T. Consider the following: All personnel on this job are experienced workers. A mock-up of the reactor vessel bottom head will be used to practice removing and installing Experienced workers selected. insulation. Special training, photos. Photos are available. drawings, video tapes The number of workers has been evaluated and is the minimum required to safely perform available the work. Rehearsal Shifily briefings will be required for personnel to enter the Keyway. Mock-up training Use of fewer workers evaluated Method of shift turnovers ALARA-As Low As Reasonably Achievable RWP-Radiation Work Permit HEPA-High Efficiency Particulate Air Completed By: W.W. Lemerond Date: 1-14-04 Approved By: .2 Date: PBF14 195a RevisionS 08/15/03 lIP 15.3/P6.8 Page 2of 2

Reference:

NP 4.2.1

People TlmeNirs) Dose Rate Dose lthsi Sub-Talik Install temporary scaffold platform Prepare existing Insulation for removal Move material Into containment Move material into heyway Build scaffold platform 6 2 2 4 0.5 12 8 5 80 8 80 1280 Remove/move DMIMMs Remove/move Thermocouples 2 2 i 80 160 80 160 Remove Insulation Break bolts and lower panels Cut panels and remove pieces Bag pieces and remove from keyway 2 2 2 2 80 320 3 80 480 5 S so Perform BMI Inspection Inspect 36 nozzles I 3 80 240 Clean reactor vessel 2 1 80 160 Install insulation frame Move frame into containment Move frame into heyway Install vertical legs Install horizontal connections Install center supports 5 0.5 05 4 0.5 5 6 15 80 3 1 80 3 0.5 80 1.25 10 720 240 120 Install insulation panels Move panels into containment Move panels into keyway Install bottom panels Install side panels 5 0.5 4 0.5 2 0.5 3 3 0.5 1.25 5 10 80 80 80 720 Remove temporary scaffold panel Teardown scaffold platform Remove material from keyway Remove material from containment 2 2 6 5 80 S 5 4 0.5 800 50 12 Worksite cleanup 2 1 80 160 RP setup/teardown and job coverage 250 Total 6116.5

Point Beach Nuclear Plant Fy In-Progress ALARA Review/Assessment ALARA Review Number: 2004-0012 Date: 4-6-04 Review

Purpose:

D In-Progress ALARA Review (No pre-job ALARA Review Performed) El In-Progress ALARA Assessment (Dose Adjustment) 3 In-Progress ALARA Assessment (Job at 50% of Original Dose Estimate) Part 1: Job Description A. Job Description Reactor Vessel BMI Inspection (Attach work list if appropriate) B. Controlling job procedures. W.O.(s) 304883 for the visual inspection and 304884 for the removal and replacement of the insulation C. Job History/O.E./Lessons Learned See attached O.E.: "Events Involving Overexposures During Entries Into Undervessel Areas at Pressurized Water Reactors" D. Dose history. During U2R26 the nozzles were inspected and the old insulation was replaced using 10.613 rem. See ALARA review 2003-0023 for additional information. Part 3: Dose Effectiveness Evaluation Check one or more of the items listed below which may have contributed to higher than expected RWP Person-Rem accumulation. Provide an explanation for all items checked. El

a. Job scope changed/expanded.

El

b.

Job site radiation levels different/changed. El

c. Encountered scheduling/coordination difficulties.

D

d.

Work extended due to tool/equipment failure. El

e. Work extended due to wrong or unavailable parts/tools/material.

El

f. Work extended due to unplanned job site preparation requirements.

l'BF-4 195b Rcvision 4 03/21/03 liP 15.3 Pagae IOf 2 Refcrence: NP 4.2.1

Point Beach Nuclear Plant In-Progress ALARA Review/Assessment 03p4 U

g.

Work extended due to interruptions/interferences caused by other work activities. U

h. Inadequate compliance with radiological controls/requirements.

LI

i. Inadequate consideration of Pre-Job ALARA Worksheet items.

U

j.

Inadequate shielding. 3

k. Other.

This review was written to document the work progress at 50 % of the original dose estimate. This job has been very successful to this point. The inspection has been completed and the new insulation is being installed. If things continue to progress like they have this job could be completed for less dose than the original estimate.

2.

Exposure Reduction Action to Be Implemented N/A (If Applicable).

3.

AR Generated: Z No U Yes AR Number: Completed By: W.W. Lemerond Date:4-6-04 Approved By: Date: 4 6 ol PBF.4195b Revision 4 03121/03 111 15.3 Paoc 2 of 2

Reference:

Nil 4.2.1

e / POINT BEA(' N1"`LEAR PLANT J' RADP1Q0 (, SURVEYS LOCATION: Keyway, Unit DATE 4t 3 oi INSTRUMENTTYPE t6/A^/111 /f'id PURPOSE: Q Daily Survey a PrC-RWP TIME SERIALNO. A"0& /RW 9/'/z/*// RWP# Y iS$ 1 MONITOR /7 '. '.*\\ I).; COUNTED BY /iX.' i -K. REVIEWED BY: NO. MREM/ fly DPM/ aDPM/ t 6.-5^Vr it dl. IJ IIR 100 CM, 100 CM2 REMARKS V R4 I .),^:/If+/-AX /0 I7 //L 4ASJe/ I /Z 'I j-

./1

/ /j 1 i'e L 54 5o J J V f 'I (u Cr-t.- 4,^ c 5~~ F tgW iFo;

sk~.' I,1b, d

_r \\ Y% _0 \\ ~~31o7 3X se./fXJC;,4 / '1 le I 1i-t/ Stt fSIq/ 9 / t; ~ ~~~~ 7 36. -to /- . _f 5{3-73 -i C ;! 13 .L~f lop C>WI ,]. q 1-7 1Ad ZeS Z e, k:5@8 3,w f--. g A 0 _I 7.L' ( Arca -I u PBF4021 Revision 0 01/01/93 lIP 1.9 Notes: I) All readings in mrem/hr

2) 'Designates hot spots

3) 3Designates routinely updated posting

4) 'Potential Hazards' identified are indicated on map

/ I IDI POINT BEACH Y' -`LEAR PLANT RAD1OLOGQT , SURVEYS LOCATION: Keyway, Unit DATE / INSTRUMENT TYPE 6 ') PURPOSE: O Daily Survey [ Pre-RWP TIME /1C' ) -/ SERIAL NO. i RWP# h'1- _ MONITOR 1 /;/.eZ) COUNTED BY '-t REVIEWED BY: NO. MREM/ .B-DPM/ aDPM/ HR 100 CM, 100 CM2 REMARKS / _/cc 1 f// &'62/t/ p~&>) i> N -- '(; c~t /ff~eN '\\ /__ Nuv\\4 R{'- 5Tz .v Area C-IO PBF4021 Revision 0 01/01/93 lHP 1.9 Notes:

1) All readings in mrem/hr

2) *Designates hot spots

3) Designates routinely updated posting

4) 'Potential Hazards' identified are indicated on map

POINT BEACH ? 'LEAR PLANT RADIOLOGI-. SURVEYS LOCATION: Keyway, Unit I(z Qn -I./ DATE INSTRUMENT TYPE eso<JPoak I 'c PURPOSE: O Daily Survey O Pre-RWP TIME SERIAL NO. 86 /

J2.

O RWP_ El Other MONITOR -g COUNTED BY 5 .9 REVIEWED BY: /I-' NO. MREM/ fly DPM/ aDPM/ 4RA HIR 100 CM2 100 CM2 REMARKS J (OC K / .2 t59 Vz 'j2,\\' $I;;.Atts 20c t4Ea SL ( _) 0b:b y1 1R WA 1t-o Di .-20 =I K 70 _8v Tc, rIL, K .f' p Stt~e' b' _____ 4 i-ic K~-k~a~j V'ct / OI ifLi .~ Arca C-10 PBF4021 Revision 0 01/01/93 ilIP 1.9 Notes:

1) All readings in mrem/hr

2) *Designates hot spots

3) fDesignates routinely updated posting

4) 'Potential Hazards' identified are indicated on map

1 ) ' I\\f "

POINT BEA NUCLEAR PLANT RADIOLOGICAL SURVEYS LOCATION: PURPOSE: n Daily Survey 0 Pre-WP OCRWP# -i lQiher1Y I~AA tiO t REVIE:WED BY:_ _ PHI.4021 isimi l 01/01/93 fll 1.9 Notes: I) All readings in nirern/hr

2) *Designates hot spots

3) Designates routinely updated posting

4) "Potential fl~azrds" idlentriXedl >. :-,- :........_

POINT BE, RAD101 A 1\\1e\\//- Ar NUCLEAR PLANT l.C.. CAL SURVE.YS LOCATION: U-1 "Ih v4X V* DAT11 INSMRUMENT TYPH ~ilJ/ 5ec L5 PURPOSE: D Daily Survey n5 Pre-&IM ___1 SU___ SI31IAL NO. -b rIZ /12 7V / 7 Z O7 Z Q RWPN Other

7..

MC)NFIO i..

i COUNTED BY d

REVIETWED) NO. .iREM1 fly D)l'P/ aDl'MI y r' ty4 ?' 4-- ^ Hllt 10 cM, I10 (M' REMARKS 1A Z -4 iA / ) .3 Z X )1 k k qz G//I ,- 1A< '-I zq _c. Z ~q 1K IL, _ _ _ _ _7 _ve .1 E4 t7r 1isscl.leotiArea. V C / ['111:-4()0 1 llevisiot I 01/01/93 III, 1.9 Notes:

1) All readings in turem/hr f

2) 4Designales hot spots

3) Dcsignates routinely updtac(I posling

4) 'Po enIial 71azards" ilentifiel are indica:ted on imp

POINT BEACI' 'UCLEAR PLANT RADIOLOL AL SURVEYS LOCATION: Uj, Ttfr vJQC9 Vie5eQ'- I DATME C2?'O,-b 11 ON I: L x, WNI lt-.O R h INSTRUMENTTYPrE )C z21 /y /rl--,y SCROAL NO. ?tY /c 71 /Avie COUNTED 1BY

S.

-D e-X z

.rfx PURPOSE

O I)aily Survey I [BRWP# o 1'?'3 Other REVIEWEI) BY: c e iC. 10i' 'cc 0 © I (D) 0 '111-4021 R{cvision I 01/01/93 III, 1.9 Notes: I) All readings in nrem/lhr

2)

Designates hot spots

3)

Designates routinely updated posling

4) 'Potential Hazards' identified are indicated on map

0 Ff. POINT BEACH -`'.EAR PLANT RA L _. SEYS LOCATION: Keyway, Unit / DATE s Z/ INSTRUMENT TYPE I. 2 PURPOSE: O Daily Survey O Pre-RWP TIME SERIALNO. 0 c RWP#

c.

9 Other i ';/ te MONITOR

k.

COUNTED BY /Xi.'e REVIEWED BY: 1'2 NO. MREM/ Pry DPM/ aDPM/ %. d IIR 100 CM2 100 CM2 REMARKS L-14'4/1 .. 2 LL.. 4 // ._____________p___,4c/ 2 M,.: I______ _,. _1 A J1PC. 4 56, V\\ e. .IJI Area C-IU PBF-402 1 Revision 0 01101/93 HlP 1.9 Notes: I) All rcadings in mrem/hr

2) *Designates hot spots

3) GDesignates routinely updated posting

4) 'Potential Hazards" identified are indicated on map

/ 7 ,111, / . ; I I I POINT BEACH' 'CLEAR PLANT RADIOLOGk .L SURVEYS LOCATION: t/ -/ (. -,u 7-4J4) ,V ' At'f DATE 4 C~V INSTRUMENT TYPE /O;A-1N PURPOSE: 0 Daily Survey 0 Pre-RWP TIME IYC6j SERIAL NO. V~7/ 0 RWP # (Pf /-33' tOther 4 ACo MONITOR 7rA,41,7 X/- COUNTED BY, 2 REVIEWED BY: - NO. MREM/ py DPM/ aDPM/ a -/ 7,9Jr'=zf.t/,i'7 At'r!,/' HR 100 CM2 100 CM2 REMARKS _Vm I VI Isj e-aA/z / K l_4eJ 4 _____( ,2 Kin /A'U-o f / 5f. // or ,,.2. 5C ,/',sie.. C\\J/ r.-x _K 5 r ss

4 ies 48

&y t.. ro etCr e-s t gS I/ sp A' K ill' i A2 /= /e~e /&~ 5z's~ "'? /2. 7e" rcz=/Sy t I L I Jns#237 voD /= e So >otoSu~pfa^ /°r/0r =T l I Ie Miscellaneous Area VI-k'ryA4'/r

7. If)

PBF-402 1 Revision I 01/01/93 HP 1.9 Notes:

1) All readings in mrem/lhr

2) *Designates hot spots

3) (Designates routinely updated posting

4) "Potential Hazards' identified are indicated on map

POINT BEWA 'JCLEAR PLANT RADIOLOuiCAL SURVEYS LOCATION: %\\-\\/7 I " U I)A'I'I INSTRUM3NT TYPn P0o -z2 lAe,( f Y PURPOSE: al Daily Survey a Pre.RWP _, __I SURIAL NO. _1(& Go' / 7 i7 t '/17Z MRW ?q 3 EJO ther MONITOR' r(. Ocscl l.5 COUNTED llY D7. [Dstef RE:VIE:WED BY: afiZ1 NO. MIZl.M/ IIY DPMI/ aDPM. lilt too CMhi 100 cm RE-MARKS itA.. O/ \\ I TAi-1"e d

\\

8 = J .dg / Pl h,4 _c _ r L etll !e 4 2 AZ f a co-A*Hn V1 ,,t -~M (4.5. fg° / \\Or `1 4)/ MIlP-4021 Revision I 01/01/9)) III, 1.9 ,4-, Y Y7. I o3 stray )\\t.,> )At mot Notes:

1) All readings in rnremlhr

2) *Designates hot spots

3) fDesignates routinely updated posting

4) 'Potential lamnrdls" idensitfet are intlk:tel on n:lnl Miscellanieouls Area u

.\\

POINT BEACH "'LEAR PLANT RADQOL!ML SURVEYS LOCATION: Keyway, Unit DATE - ? (2' INSTRUMENT TYPE /75O5 /'e,/, y PURPOSE: WDaily Survey O Pre-RWP TIME C'43_: SERIAL NO. 2 " / -no./

7. 7-'

a RWP O Other MONITOR COUNTED BY C (- /1 REVIEWED BY:_ NO. MREM/ ly DPM/ oeDPMI HR 100 CM2 100 CM2 REMARKS t t .., S 36..ed .} '9t>.. j %4Z/ \\ \\ /

..)3 ),.

.~ 3!3. .9

6.. '

I\\\\ f/I? 75 4 ____. 9S Area C-10 PBF4021 Revision 0 01/01/93 TIP 1.9 Notes:

1) All readings in mremhr

2) Designates hot spots

3) Designates routinely updated posting

4) 'Potential Hazards' identificd are indicated on map

POINT BEACH '"LEAR PLANT RADIOLQOQ SURVEYS LOCATION: Keyway, Unit / DATE ii. '?- 'o INSTRUMENT TYPE /Z" ( As o //7"A'P' PURPOSE: O Daily Survey 0 Pre-RWP TIME Of, SERIAL NO. io 7? 17 9c<5' 5'7OZ76tiRkwP# i-MONITOR _.-/ /9, COUNTED BY Ii. L IC REVIEWED BY: NO. MREM/ 63y DPM/ aDPM/ Osl[ IIR

OO0CM, 100 CM,.

REMARKS ./ 5'-e /-I't ________1 FYe SQ rj '*1i / A'A %4 15=C-;I 0 1q>1 N /.. i yv /t' I =__ 6I{ /I Rj/% CA bSD Area C-iU PBFI4021 Revision 0 01/01/93 lip 1.9 Notes:

1) All readings in mrem/hr

2) *Dcsignates hot spots

3) fDesignates routinely updated posting

4) 'Potential Hazards' identified are indicated on map

Al E.41; TYPE u'tl Point B3eachI Nuclear Plaunt AIRBORNE R4DIOACTIVITY SURVEY RNPNo. t-f/ 33-San111t Lo IcIC ItOitl: tL l I Lt

LPL, C _- Y Z

A * -A Y I,; 4 RC31C M lCOntaiilnincill samplin Sy\\scm used? ED Yes E No '° [4, SAMPL.ING DATA: l SAN sAMPLE SAMPLE START rSAMPLE STOP \\ X 'NU1BER DATE 1 IME DATE I TIME c Sanplle Stall iloW Sample Stop l-lowl Averagc Sanpie FIo, IG L; P Total Samplc Time (mIin) Flow Corrcction Reimariks 1, - - =k GROSS iETA-GANMA COUNTING DATA: SAM PLE DAT1 E 'TIME Countcr GROSS i1GD NET ULT. ACTI'IT' B), Numbcr cpmn Cepin cpn PY FACTOR (tCi/cc)ti ! INITIALS t~~-il;-t ; - tII P^Lv i3L0 0.2 .-,*'.s

zl.cGi E"l S

¢ 1 SIf)1 anclp i~tiis i( greater than ozr cqunl to SIE-ID pCi'cc. ntuxir! 1RI' siiperv isitn. perfiorr cross alpha counting muid take nr Sencl s.aritlei to Chemistry fhr isolopicn ahnlsis. -' l f sannIc taknl Ihi an :nrca witih k;now alpha co ntaminatiin (c :.c. trculind cata ity scr nt fuel pol transier cfnal. rcanlor h1Cisd) and S ple

Ietiv\\ity i

rc31te t han1 I 1E. I) n I(i'cC. PTr rm~~1 !rOSS ralpha eoutuning anid take or scnd salmpl tn lchmistry fior isotopiic annly~sis. lr-nmpIc ;uetivit% rattiO ol net cpm bctaammaina tnncl cprn azpha is less than 180. ntilA RI' supervision mid pcrforni long-lived alpha counting. IJ Isotopic Analysis Date E NOBLGS a DACDOS Retumn to RP by . hr. for LLA counting. Time Scctrum Index No. ACTIVITY BY [ ACTIVITY BY ISOTOPE l (PCi!cc) INITIALS ISOTOPE (4Cilcc) INITIALS I_ I I Iccord RE-21 I Iand RE-2 12 rcadinsvs for all an-powcr containnint air sampics. ] Unit 1 OUnit 2 RE-2 II: _lCi Wca(rd RE-215 rcadin-- and SAE flow for all SAE air samples. J Unit I ED L 'it 2 RE-2 15: pCi'cc RE-212: Ci'cc SAE Flow: scfjn )0TE: All relcase path air samples musr t be counted for Iont-lived : 1pha. See hacd sidc of form. t-LeaX -A Let.'u'i~:ihIlit' - I [t eIC ea2 pa:1l1s olyjl ) If t!1h tnta c1 inret11;aic f:r vanti

'ajes (c cluding,raturalth o i'e urring i topudJ cscced's W)"

{1'1 C. OT. oxr 1 ti'tal 1nr nohib:,asl. Cxceed: 6.S(6l-l(i pti'e. nn:iIt f ( r lah supervisor and or:lie I udiaiinn I r;otCCIilon 'i tlr. Save t Ihr ait In::M;xlc lilter until the inmcs'Iieiaion is coniplctd.iIhe sa:mp'L Ji(IiilIJ h in'llesiv:ited tno dctcrmittc it silnyflefanvc as a1 A i. o.11I 1 ( .I

-11,;

I I - 1.7 li t ( 5 1&f; 1( I

I.ONc(; I WMFI) AL.PHIA Ct1 IN'TING DATA: Ifihie ratio of (C 2.'C1) is preater than the v akii t i n in Table ], nrld if Cr is grcatcr than 7.5E-1;3. pelrfiorml Ct ,crelliM." '"lRccord LLD for the counter being used at each cou-S'am11ple V'ol0lm1C (cc): (from Plnc I ) C uInter Grc'ss Ilod Nei NMoll. Acti\\ i I i olIs Activil\\ BY (.O'c I.1i IIE Na )g~ fcplll) J (rm) F.,ctnr f ii0e F.J~ JIrom_(I Ra it ioVC1 I NIT. z _-I_ IiI1-i..,I_ C4, Rev.ked Hl y: _ Date: 5Itr/ RP Supervision COUNTING iNlORMATION FOR LONG LIVED ALPHA Count Time C, At T4 Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C: At T, Start second count at least 2 hours after C,. C-At T, Start timc dependent upon rcsults of C2. C4 At Tr Stan count 24 hours afier C,. CLI At T.,; Start count at Ilast 75 hours afier Tt. CLL C. - (C, e I-e ;v VALUES OF (C:.,.4 ETC.)/Ct FOR CLL EQUAL TO ZERO TABLE I AT) ATAT I l __ _93_6 5.5 .(Y6975 1 9.25 0.S456 13 0.4_ 68 2 1.8772 5.75 0.6862 F 9-'.5 (.5367 13.25 (1.4198 2.25 (1.8630 [ 6 (0.6750 j 9.75 (1.5:80 13.5 01.4 I3( 2.5 (1.8490( 6.25 (0.6641 [ 15 01.5194 13.75 (1.4(063 2.7 5 0.8352 6.5 (0.6533 1 1.25 U.5110 14 (1.3997 3 0.8216 6.75 0.0427 i 0.5 I (0.5027 16 0.350( 3.25 (0.8083 7 0.6322 1(1.75 0.4945 1I .3U76 3.5 (1.7951 7.25 0.6220 1 11 0.4865 20 (1.269E l 3._ 0.7822 7.5 .61 I' 9 11.25 1.4 X6 22 0.236 4 0.7695 7.75 0.6039 1 1.5 0,4708 23 0.222 l 425 0.757011 U.591 I 11.75 0 4632 24 0.208 4.5 (.7447 8.25 0.5E21 12 (0.4557 26

3. 182

[ 4.75 (17320 8.5 (1.5731 12.25 0.4483 2N (.160 i S1.72U7 8.75 l .5t(338 12.5 0.44101 31 0.1401 5 25 (M M(19( 9 0.5546 1 2.75 (1.4338 NOTES: 1

l. I fthc ratio of activity (C:

. ctc.)'C, is equal to or less than) that indicated in Table 1. or if the act ivity of any count is less thIa I.LD. airborne alpha activity will be considered as not present (the LLD must be c 7.5E-13 pCi'cc).

2.

If C, 1 is grealer than 7.SE-;.3 ptCicc, notify RP supervision for review. II-. Iftlic C IC, ratio is mreatcr tian t1:1 in T:blc I. refer to i PIP 3.53. Co}un:in¢2 of Air Samples far Low L.ve, l. Lorn-LiVJ Rladiouartivc Alpha Pa'riculaJe Contamin iatison.

/

I l oJtlz 3 .e e X.

I 'u? bc.jic N.iclrar Maiint S'II1:11 ILova;lioll: RWN'P No. LCI - I 3 A IRBORNE RADIOACTIVITY SURVEY iA I 4 A L Ae.* A; 4. c-" t) Iv _; -, L9 -I i.tz

t '

77' RcI1101lc C011tli~ltlCltl S3zl1Pli,,-- sys-1cml used? O %'es ONo 2-1 -A- ,2N1PL.N'G, DA TA^: I I Satj111c Strip h 1o Avert:&L' Simple Flow II b LP"-,\\ z z t z z z J, Total Samnpic Time ctminj Flomz Correction Rcnarks GROSS TETA-GA.M\\A COLIVT-NG DATA: Cone SAMP11LE DITE lTME Counter GROSS BlKG)D NET ML'LT. ACTIVITY I Numbcr cplm cplm cpni y FACTOR (pCi'cc) 1' INITIALS Oti-{J* 1. ir( 4(S.'i { 2 v i13~ j i Z-3t0 /-h* jr* Li -

i. z23 m

It SiDpk

Icivily iS~acr tthan or c~qual tn 5-Io ;i'cic.

Rt 1ti; 'crvis piprfIrm gross alphhn cowtlinc ;,md tke or srsend aniple to C'l lwntstr% fu1r !sfn pican afl y sis. 01 I 1srtntc ialukei fni an.I 1rca witih kno%% n alpha con:amination (c t.. rcrucling cavity. spent flucl pool transrer cinal. reactor hIead) and sample activity i.s grealtr thaii I E. I( pCi 'cc. pcrhrrnil Vross alphz collir.l

innd ta cr scnd samplk to CIemiisiry fbr isotopic analysis.

GROSS ALI IPIA COlNTING DATA: NET DATE TIM E Countcr GROSS BKGD NET cpm pin Ily Il Number cPln Cplll cpmn NET1; INITIALS -l -1CA 1,0 6nc le v.G-o I 1? I DI

t SmpLC z'cliviti rttio of1nct cpm bcizr-gamtna to tlCt cp:n alpha is less tIan 10. notit\\ RI' supervision ;nd perorun Iong-lived ralpha counting.

I Isotopic Analysis Date 4-- 4-- (9' - MNOBLGS ,DACDOS Return to RP bv hr. for LLA counting. Titte I 7 Setcirum Indrim \\n O..I/i \\/f F1 I ACTIVITY BY j ACTIV!ITY BY SOTOPE (pCi!cc) IN1ITIALS ISOTOPE (;pCi'cc) INITIALS cs-17 3.6 f ,-E-11 1 C.&- lY 1 3 ") L T A L ~ A. i i I. ccord RE-2E II and RC-212 rcadings for all a:-powcr con:ain:ncnt air samplcs. 3 Unit I a j, 2it RE-2l1 : _ICi Lcord R r-- 15 rcadimnl an11d SAE Jlo. for all SAE air samplcs. ] Unit 1 fl': it'2 RE-215: pICi/cc RE-2 12: _ _ _ p C i 'c c SAE Flow: sc.'m .)YrE: All rcictsc, pat!i air saipkles rmtust b coauncd for lon1 -l-ve_ ::i;-ia. Sec hbact. siic of farml. .- I ': relcake j'a:IiS tall 1' t1!1u. ulo l 'iui:it a :'r rutwicixc:. tecludding r.Ji r:I:A o.ciirring ki w:vpes) c ueeds ..I-IJ' IVI LL. Ii 111 f'ol tar 1ohki grxses e e 's \\I SLU. ( 'i ;x. nwi!% I!,; : 1;1t supcr ismI ;:II,, or ulic 16dnwion 1'ro'cnion 'C' ir %;S;!': :he irt F::a-.a IIt I:cr un:lil

e. i;:\\ sliLio:n I

' hi sas L-JIUIJ

jheb il% e mRced :, jccmid c itc I'n;fi canvc s ;n M I :u1a I h ei:

t L it (

o d t r n i i t . iaci x c : s I ..,, i _ i

,S. 1 It.

, i ; I';. I , -sr (.' _ M,.; t:S:: I I ? 51,' '1

I

V.ON(; I I ' \\ 1j-l.I) 1 Cot1 3:TING DATA: Saimple Xoltille (cc): (from PasIe I ) If tili ratio of (C2!C,) is e rea:cr tI:ln thc va'aue it: in Table 1I and if C is rcater thain 7.JE-13. pet firtn ri, reL.l iIcun '4 )l ccord LLD for tlhe counter bcing used at acth count. ChILiwer Gross MIlud l N l ltl. Alii it) J i oti: A;t iviill 1BY LOtNI DATEl 1*I1 No. (c°nC'M) (crpll) (q'm) fl(tcir .uciCC) R1w 4 1 rrt'm C,! rlit'-. !- INMT -- -r C' -1 S / 1.z 5--1 I. G 5 ( 1.f PP-c0- 8 I S'{XWl.lt ^ 58(*D{ E , L, t . -0; x, C 7 1

5 O:-cC~~f3,j

+/-. IL j____ q.s*5 _h O. C.; Pats~qjL{ c - .I 3()' I i ,1 7S- _D ate: / RP Supervision COUNTING INFORMATION FOR LONG LIVED ALPH4A Count Time C, At T4 Stan first count 4 hours after sample stop time. (Essentially all radon decayed.) C: Ai Tr, Stan second count at least 2 hours after C1. C; At rT Stan time dependent upon results of C,. C, At Tr,, Start count 24 hours after C1. CI. At T. 5 Start count at least 75 hours aficr T.,. CLL = C, (C, e VALLIES OF (C-,, ETC.)/Cl FOR CLL EQUAL TO ZERO { TABLE I AsT AT J AT l AT i_ _1_93_6_ I __- _1 5.5 i 0.m975 9.25 (1.5456 13 0.4268 2 j-iX772 5*.5 U U682 9.5 0s.5367 13.25 0.419N 2.2' 0IX6;t 6 (l675(1 Y9.75 (1.5:N( 13.5 0(.4130 2.5 t490 6.25 (1.6641 10 01.5194 13.75 0(.4(163 275 38 352 6.5 03.6533 1i1.25 0.5110 l94 3 t.K216b 6.75 U.0427 j 0.5 0.507 36(1.350u j.25 REMS()7 (7.6322 1(1.75 0.4945 1 0.3076 i

1.7951: 7. 5 U.622u

.A I65 2 0 0.2(98 3.7i 0.7822 7.5 (0.6119 I 1 1.25 (1.476 22 .236 4 7('695 7.75 0 Wo9 11.5 0.47US 23 0.222 425 (375701 8 0.5921 175 04632 24 .208 4.5 (3.7447 8.25 0.582 12 0.4557 2, 1 0.182 !.75 (I 3 26_ s 1 .5;31t 12.25 0.44F3 81 (J 7207 .75 5t3 8 12.5 U.4410t 3(0 l 341 S-, '. (I 7(190 9 I (1.5546 12.75 (I34338 ! I! I I_ NOTES: I. If thle ratio ofaetivice (C2 l

c: .)'Cl is equal lo or less than that indicated in Table I. or if tHe cICix il of znv count is Icss tilan L.LD. airborne alpha activity wtill be considered as not present (the LLD must be s 7.SE-I It pCi.'cc).; 2.

If C, is ireoair than 7.5E-13 prCi cc. notify Rl supervision for review. I Date ~ J C j PJsuptrvision Mi Tn. IC:A CI Noilc (initials) I I I I i I I 1 I [ar I Ij1 l C I C l .(,z / I7 l CI \\~iid(nta If:lic C4,'C, raxio is greater lhan that in Table I. t fr to HI?;P ^.52. Co:on:in cf Air S:in ;fles far Low Ltuvel. Lonl-Lived I 4i;oClti Aiprlp har.ieu'ate Containimn:,tin^. l11 l { il }X %I I. llt

I~ 6 l

I a; ses -1 1

Point Beach Nuclear Plant RESTRICTED DAC IN AIR CALCULATIONS SAMPLE DATE: 4/412004 14:15 SAMPLE LOCATION: UNIT 1 KEYWAY REMARKS: INSULATION REMOVAL SAMPLE ID: 30-52 /S /S' -9LI TAKEN BY: RM ANALYSIS BY: LAK ISOTOPIC ANALYSIS RESULTS ISOTOPE C0-60 CS-137 RESTRICTED DAC (uci/cc) 1.OOE-08 6.OOE-08 CONC (uCi/cc) 3.88E-11 3.65E-12 FRAC. OF CONC. 0.91 0.09 OF DAC 0.388 0.006 TOTALS 4.25E-1 1 1.00 0.394 Based on a 40 hour work week, the maximum stay time for the listed concentrations is: 1.OE+04 hours. I /. Date: Reviewed by: MECDose/Noble Gas Program (SWR-2001-103) 04 /04/04 9 :01:41 PM

SMPLE TYPE:

v AP F Gas

) Other Point Beach Nuclear Plant AIRBORNE RADIOACTIVITY SURVEY R\\\\'P No. OL(- Sample Location: LA I D I P,-t, 0 -j 4 0_ E rs fl

l 't r tkfl 8

/ ( Remote containment sampling system used ? Sample Start Flow 3o P Total Sample Time (min) ( Sample Stop Flow I Flowv Correction t'D 7 Average Sample Flow 4, Remarks GROSS BETA-GAMMA COUNTING DATA: SAMPLE DATE TIME Counter GROSS BliGD NET aULT. ACTIVITY BY Number -epm Cp71I cpm,By FACTOR (pjCi/cc)I1 l INITIALS /.2. S. Ifsampleactivity is greater than or equal to SE-IO pCicc. noti RP sup.r% ision. perform gross alpha couningid anid c tk or scnd.sap to Chemistry for isotopic analhsis. I1 samplc taken from an area vith known alpha contamination (c.e.. refueling cavity. spent fuel pool transfer canal. reactor head) and sampli activity is greater than I E-10 pCi/cc. perform gross alpha counting and take or scnd sample to Chemistry for isotopic analysis. GROSS ALPHA COUNTING DATA: NET DATE TIME Counter GROSS BKGD NET cpm Py/ BY Number cpm cpm cpm a NET INITIALS I a lct aI JRapm ah '~Ifsample activity ratio of net cpm bcta-gamma to net cpm alpha is less than ISO. notify RP supervision and perform long-lived alpha counting. O Isotopic Analysis Date I NOBLGS E DACDOS Return to RP by _ hr. for LLA counting. Time Spectrum Index No. _ ACTIVITY BY ACTIVITY BY ISOTOPE (pCi/cc) INITIALS ISOTOPE (pCi/cc) INITIALS I .I I I I I____ i 4 4 i Record RE-21 I and RE-212 readings for all at-power containment air :aimples. 0 Unit I F Unit 2 RE-21 1: ptCi Record RE-215 readine and SAE flow for all SAE air samples. [] Unit I 0 Unit 2 RE-215: PCilcc RE-2 12: ptCi/Cc SAE Flow: scfm NOTE: All release path air samples must be counted for long-lived alpha. See back side of form. ,ase Accountahility - (For rclease paths only) If thc total concentration for parniculates (excluding naturally oncurring isotopes) cxceds

E-09 pCi/cc, or the total for nohle gascs exceeds 6.S6E-06 pCi/c. notify the Chemistr' lab supervisor and/or the Radiation Protection supcrvisor. SaVe the air particulate filter until the investltation is completed. The sample should be investigated to determine Its si.nificance as an airborne release.

PIt F.4022 Revision 16 1 1:13 /01

LONG LIVED ALPHA COUNTING DATA: Sample Volume (cc): (from Page I) If the ratio of (C2/C0) is greater than the value given in Table 1. and if C2 is =reater than 7.5E-13. perform-CLL screening. '4'Record LLD for the counter being used at each count. I l Counter Gross l BkLgd l Net lMult. Activity ll Hours l Activity 1 BY COUNT DATE TIME No. l (cpm) l (cpm) cpm) Factor (Ci/cc) LLD""' From Cj Ratio/C, JNIT. C, C'2 C3 C., Reviewed By: Date: ___/r/o / RP Supervision COUNTING INFORM1ATION FOR LONG LIVED ALPHA Count Time C, At T4 Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C2 At T6 Start second count at least 2 hours after C1. C3 At T1 Start time dependent upon results of C2. C, At T.s Start count 24 hours after C1. Cu. At T>7s Start count at least 75 hours after To. CLL = C. - (C, I -Ce VALUES OF (C-.3 j ETC.)/C, FOR CLL EQUAL TO ZERO TABLE I AT J AT j AT J AT I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6862 9.5 0.5367 13.25 0.4198 2.25 0.8630 6 0.6750 9.75 0.5280 13.5 0.4130 2.5 0.8490 6.25 0.6641 10 0.5194 13.75 0.4063 2.75 0.8352 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 10.5 0.5027 16 0.3506 3.25 0.8083 7 0.6322 10.75 0.4945 I 0.3076 3.5 0.7951 7.25 0.6220 11 0.4S65 20 0.2698 3.75 0.7822 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 11.5 0.4708 23 0.222 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.208 4.5 0.7447 8.25 0.5525 12 0.4557 26 0.1I2 4.7.5 0.7326 8.5 0.5731 12.25 0.4463 28 0.160 5 0.7207 8.75 0.5638 12.5 0.4410 30 0.140 5i.25. 0.7090 9 0.5546 12.75 0A338 I_ NOTFS: I. If the ratio of activity (C2. I. etc.)/C, is equal to or less than that indicated in Table I. or if the activity of any count is less than LLD, airborne alpha activity will be considered as not present (the LLD must be S 7.5E-J 3 pCi/cc).

2.

If C L is greater than 7.5E-13 pCi/cc, notify RP supervision for review. Date I I l RP Supervision Date I Time C, l C-I M l I I CLL Notified (initials) I I __I I o.°o55 I I 1,

3.

If the C.,/C, ratio is serealer than that in Table 1. refer to HPIP 3.53. Counting of Air Samples for Low Level. Long-Lived Radioactive Alpha Particulate Contamination.

Pke:nt BJejh

i: ;ear PNam IODINE ACTIYITY CONCENTRATIONS LOCATON:

Lt ( L v R\\VP Nc'. L'I(- 33 3 Remnote zontnnen,: s:imXnint svs:em use` ' Ykes .AMlPLING DATA:

' No E3 NA ITh SAMPLE l

SAMPLE START l S-0IPLESTOP SAMPLE SAMPLER NUBRl T T:\\1-

n.;E TMxE VO CLUMSE. i,;

l NUMIBER lINITEA 3c-s't L.I-l Oc SS l y -iqb'l I 1 &t.l$- 2 ' l 6> Sample st:lrl flw 3,, L_ p Tot:al zimplc time Irmin) 6C Sample stop flow Flokw ecore;:ion factor L.'I 7 Averaye sample,lew Remarks_ ANALYSIS DA\\TA: .XN] Isotopic An.z;is:s !.\\MECDOS df.'; DAC cta1) S.]. N A 2iA* l Concenirazti n By Conzertzra:iun Dv Dx l Time I Is (I cp pciA;, In:;:z!s Dxe ! Tine Isotope opctA." Ini:izk 14-+-o 4-z ~ I.1 4-3 CI-3S I __ I ll T otil To ll.~ 'tavnl l ti l* / l I o d i ne__ _i__ _ V_ _o n _ I ToŽtal lIdine Con.enlranlcn - Total Additiorn.l CLun un:.razion = -7 Lj. 1,.i. pCiicc By i1ni:ia!;) i ] *nit ! i jLr.::I RE'2i ;: PCi RE-'i': _c.iu_ Ir:n s'huli be use J *e a31 r_ icicdin.e ::r. ; _ FELEASE.ACCOUNTA3LITY-lT"- .ele i n:\\ If :.'5e ;c n.ra: n.n'f tota! tkr

t!.';Z-;-

.2SF.V9 "C:. <;. q t*:

r.e4 i'. R.AM! '.2.

l.v @^ r.*e i:.l:..i .. ne; i r i-in':; D).-: : ";-:F.-, _' i._

.-.'j It HP ! : - : -.,. C" ::, ;

S MPLE TYPE: M AP F Gas 5 Other Point Bea.ch Nuclear Plant AIRBORNE RADIOACTIVITN SURVEY R\\N'P No. Sample Location: U-1 I-k--4. - Remote containment sampling system used'? E] Yes [ No GNA SAMPLING DATA: I I ISAMPLE SAMPLE I SAMPLE START SAMPLE STOP VOLUME SAMPLER BY NUMBER l DATE I TIME DATE TIME (CC) l NUMBER INITIALS 30-6 1 z 4S 3 4'-s-s 1 f.ZzG7 1 Sample Start Flow Total Sample Time (min) m)O Sample Stop Flow Flow Correction o.97 Average Sample Flow Remarks (561 1'4 'zr GROSS BETA-GAMMA COUNTING DATA: l SAMPLE ATE TIME Counter GROSS BKGD NET MULT. ACTIVITY BY Number cpm Cpn c opm py FACTOR (IJCi/cc)' 11 INITIALS 0030 _ooo _ __Z_ 2__ 9.4_ Co / I 0I Ifsamplc activity is grcaicr than or equal to 5E-10 pCi/cc. notify RP supervision. perform gross alpha counting and takc or send sample to Chemistry for isotopic analysis. 4! li sampic taken from an area %with known alpha contamination (e.g.. refueling cavity. spent fucl pool transfcr canal. reactor hcad) and samplc activity is greater than IE-l10 pCi/cc. perform gross alpha counting and take or send sample to Chemiistry for isotopic analysis. u" IrfsampIc activity ratio of net cpm beta-garnma to net cpm alpha is less than I80. notify RP supcrvision and perform long-lived alpha counting. E/iotopic Analysis Date 5 NOBLGS C DACDOS Return to RP by ) hr. for LLA countinr. Time Spectrum Index No. ACTIVITY 1 BY ACTIVITY BY ISOTOPE (ptCi/cc) l_INITIALS ISOTOPE (pCikcc) l_INITIALS .I I-I. Record RE-211 and RE-212 readings for all at-power containment air sa.imples. D Unit I 5 Unit 2 RE-21 I: ptCi Record RE-215 readina and SAE flow for all SAE air samples. 5 Unit I [ Unit 2 RE-15: pCi/cc RE-2 12: __pCi/cc SAE Flow: scfm NOTE: All release path air samples must be counted for long-lived alpha. See back side of form.

Release Accountahility - iFor release paths only) If thc total concentration for paniculates (excluding naturally occurring isotopes) exceeds

'E-09 pCi/cc. or thc total for noble gacs ex.cecds 6.S6E-06 pCi/cc. noify the Clicmistry lab supervisor and'or the Radiation Protection .rvisor. Save the ait particulate filicr until the investication is completed. The sampile should be investigated to determinc its significance as an airborne release. PBF-4022 Revision 16 I1/13.'03

LONG LIV'ED ALPHA COUNTING DATA: If the ratio of (C2/C,) is greater than the value given in Table 1. and if C2 is greater than 7.5E-13. perform Cu. screening. " 4'RPnrA I I n fnr the couinter heinp msed at each count. Sample Volurme (cc): (from Page 1) 1 l Countcr Gross l Bkgd Net Mull. 1 Activity 1 Hours l Activity l BY COUNT DATE I TIME .No. Icpm) W pm) (cpm) Factor tyCiI/cc l LLD 4' From C, Ratio/C _INIT. C, _.I... C, C2 C'. Revicwed By: Date: 5^ 31 RP Supervision COUNTING INFORMATION FOR LONG LIVED ALPHA Count Time C, At T4 Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C2 At T6 Start second count at least 2 hours after Cp. C. At Tx Start time dependent upon results of C2. C4 At T2g Start count 24 hours after C,. CLL At T>7 i Start count at least 75 hours after To. Cu. = C, - (C, e I - e.~ VALUES OF (C-. 3.4, ETC.)/C, FOR Cu EQUAL TO ZERO -TABLE I AT A D T AT A AT I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6S62 9.5 0.5367 13.25 0.4198 2.25 0.8630 6 0.6750 9.75 0.5280 13.5 0.4 130 2.5 0.S490 6.25 0.6641 10 0.5194 13.75 0.4063 2.75 0.8352 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 10.5 0.5027 160.3506 3.25 O.SOS3 7 0.6322 10.75 0.4945 I 0.3076 3.5 0.7951 7.25 0.6220 11 0.4865 20 0.2698 3.75 0.7822 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 11.5 0.4708 23 0.222 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.208 4.5 0.7447 8.25 0.5825 12 0.4557 26 0.182 4.75 0.7326 S..5 0.5731 12.25 0.4483 28 0.160 5 0.7207 8.75 0.5638 12.5 0.4410 30 0.140 5.25 0.7090 9 0.5546 12.75 0.4338 NOTES:

1.

If the ratio of activity (C, 3. etc.)/C, is equal to or less than that indicated in Table 1. or if the activity of an) count is less than LLD. airborne alpha activity will be considered as not present (the LLD must be < 7.5E-13 pCiccc).

2.

If CLL is greater than 7.5E-13 pCilcc. notify RP supervision for review.

3.

If the CIC, ratio is ercater than that in Table 1. refer to HPIP 3.53. Counting of Air Samples for Low Level. Long-Lived Radioactive Alpha Parziculate Contamination. PBF-4(22

PonitB:Xh!^:! P~xit IODI.NE ACTIV'ITY'CONCENTRATI'O0NS LOCATION: U-I L(. _ RW? No. O4'.- (3 3 Rmnote zXonummerC1 s:mphlng sysytm t:seS I eJ? E Y's --1 No [EJ-, 'S.2I SAMPLING DATA: SAMPL.E SANIPLE START l SAMIPLE STOP SAMIPLE SAMPLER NLM13E D PATE l TIME I f5ATE l TIME NOLMIE.t NUNIBER INIIL 30~~ s 1 /44od /- 14'-oVI 23S 1-22-Cl y5~2 f I Sample tpart flow 3_0 -. 0 To:ml siamcle 1ni e 'mini 4) sample stop flow F/o% r ou;re:ion fictor O.1- .A% erae simple flew Remarks ANALYSIS DA.\\TA: 'NJ I1s~topic An.alylss M IECDOS i -1 DAC ) S.J.im: 4 J CLoncenir:aio: n Br f Coner:ration Bv iDate Ti .sMCA Issuzape pC:I.Tm lCnC: i~ik T 'm.- I sot p C_ _I_ I3S 1In___ .B l_ _ _ _ _ _ _ 0 _ _ t _ f l : : f _ -'Jf 1 3 r.S _ I _ I - I^X 1 i _ 1 I 1 _3_ I =______lodKine irŽ~/. j a t8 tlI odine Tom!.ll !dine Concertraticon - Total Additional CnL-n:.a:i.)n = /-i b1. 4 pCii;. By ulnil:3!s1 i I LUnit ! i 'I Unit' RE. 'i: .+/-Ci RE.'I': pC:iz:_ This i.M.r:n ShLuld be u;3J for al! raJieic'd.e ar.ais r Sah!. R.FLEASE ACCONTA3%ILITY - I' z L._- piZ ~+/-t.S Oen I If: rcn en;'.:ion to'ta! ftr rioj.ei; eC; 2 'E-N9 _C:,::. RA.'2.:w

s-

.z:M'.eJ i R ^.'. S..:: :;::e ch.j:,x i *.3er

!e :n.eI:%

a:i r :S5

r. i

'E:F.-;, "

j..
iP

i -., 7. :1:. zr- I I).::e: - .-// I/ Record RE-2 Il and RE-2 12 readings for all at-power containment air samples. El Unit I E Unit 2 RE-2 l : pCi RE-2 12: pCi/cc Record RE-. 15 reading and SAE flow for all SAE air samples. O Unit I E Unit 2 RE-215: Ci/cc SAE Flow: scfm NOTE: All release path air samples must be counted for long-lived alpha. See back side of form. Release Accountability. (For release paths only) If the total concentration for particulates (excluding naturally occurring isotopes) cxcceds 6.8SE-09 pCi'cc. or the total for noble gases exceeds 6.86E-06 pCi/cc. notify the Chemistry lab supervisor and/or the Radiation lProtcction 'ervisor. Save the air particulate liltcr until the investigation is completed. The sample should be invcstigated to determine its sienificancc as an 'orne release. PBF-4U22 Revisioni Io)1 1/1 /113 H P 1.I - 1.7 or (53.2/1'(..' Pa-c I of2S aleckrcsccs I lll's 3.32. 3.53. 5.1

LONG LIV'ED ALPHA COUNTING DATA: Sample Volume (cc):

2. I C '

If the ratio of (C21C0) is greater than the value given in Table I and if C2 is greater than 7.SE-13. perform CI screening. (')Record LLD for the counter being used 2t each count. (from Page 1) I Hours Activily BY I.LDt4 I Froni C1 I Ratin r INIT. 72____ 7c<t r2)[ j 0 )'70 (; (. ..,2 270 L O. 6 i-2S `o7 f -t. il /0 I G.,/ 36-/3 II1A lo7So I 7 V w wv _ I ,/- ;z F /.5 IRIk Date: I//(/. I COUNTING INFORMATION FOR LONG LIVED ALPHA Count Time C, At T4 C2 At T6 C3 At T, CL At T>,s CLL At T>7s Stan first count 4 hours after sample stop time. (Essentially all radon decayed.) Start second count at least 2 hours after C1. Start time dependent upon results of C2. Start count 24 hours after C,. Start count at least 75 hours after Tn. CLL C2 -(C1 e"' ) I -e e41 VALUES OF (C2. 3 4. ETC.)/C, FOR CLL EQUAL TO ZERO TABLE I AT AT AT AT I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6862 9.5 0.5367 13.25 0.4198 2.25 0.8630) 6 0.6750 9.75 0.5280 13.5 0.4130 2.5 0.8490 6.25 0.6641 10 0.5194 13.75 0.4063 2.75 0.8352 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 10.5 0.5027 16 0.3506 3.25 0.8083 7 0.6322 10.75 0.4945 18 0.3076 3.5 0.7951 7.25 0.6220 '1 0.4865 20 0.2698 3.75 0.7822 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 i 1.5 0.4708 23 0.222 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.208 4.5 0.7447 8.25 0.5825 1 2 0.4557 26 0.182 4.75 0.7326 8.5 0.5731 12.25 0.4483 28 0.160 5 0.7207 8.75 0.5638 12.5 0.4410 30 0.140 5.25 0.7090 9 0.5546 12.75 0.4338 NOTES: I. f the ratio of activity (C2.3. etc.)1C1 is equal to or less than that indicated in Table I or if the activity of any count is less than LLD. airborne alpha activity will be considered as not present (the LLD must be <7.5E-13 pCi/cc).

2.

If CLL is greater than 7.5E-]13 pCi/cc, notify RP supervision for review. ICI I RP Supervision Date I Time C,~ C, A 1 Notified (initials) IY1 6 e3 A /.z82 -/7 - 0.0655 If the C4 fc ratio is treater than that in Table 1 refer to HPIP 3.53. Counting of Air Samples for Low Level Long-Lived Radioactive Alpha Particulate Contamination. I'13-14(122 Revision 16 1I/IS/US 11'.I -1.7 tr 0.21'6.3 Pa Ce 7 2 of 2 Rfefrkelnc III'1s t 3 3 5

Point Beach Nuclear Plant RESTRICTED DAC IN AIR CALCULATIONS SAMPLE DATE: 4/5/2004 02:25 SAMPLE LOCATION: UNIT 1 KEYWAY REMARKS: INSULATION REMOVAL SAMPLE ID: 30-57 I\\b 9, TAKEN BY: RM ANALYSIS BY: LAK ISOTOPIC ANALYSIS RESULTS RESTRICTED FRAC. DAC CONC OF OF ISOTOPE (uCi/cc) (uCi/cc) CONC. DAC CO-60 1.OOE-08 2.83E-1 1 0.57 0.283 CS-137 6.OOE-08 2.12E-11 0.43 0.035 TOTALS 4.95E-1 1 1.00 0.318 Based on a 40 hour work week, the maximum stay time for the listed concentrations is: 1.3E+04 hours. Reviewed by: D Date: t By L ' MECDose/Noble Gas Program (SWR-2001-103) 04/n5/n4 4:29-40 AMl

Po:nt Bej'h N.:eAir p11:mt IODINE.\\CTIVITY CONCENTRATIONS bf / 1-'Al C,; ,.1 l A5 4J1 'A L R\\VPNo. ('/- 3 3 LOCAT'ON: ( ( Ren.ote containmeni: sampling s!em tsePi. OJi Yes I y1, N 3>.NA -- I SAMPLING DATA: SAMPLE SAMPLE START l SAMPLE STOP SAMPLE SAMPLER NMIBER i TRIE \\OLL-IE., c:Z NUMBER INITIALS 30 SSE ! q5-cq bz2% I 1-.5.C D O2

i40L.

k Sample start how loc) c Towal sample time i min) .). t, Saimple stop flow Flo-1 orrec::on Lwtor .Aceragc sample flovw Remarks ANALYSIS DATA: 'NJ Isotopic Antlviyis I NIECDOS i f"i DACdat.;) S.I. / tŽ rIo t oCpncntrio Bv Isotlpe C oi l Date l Time I rx I l

.: Ci';:

1!' .L -Q t Yg -13 I _ I I-pjDr~ 1-1.13 j__ I I Cl-S. l pC 34 Iodine__ A d.4 itional J Al; ' ( Toia.l !odine Concentration - Total Addz:ihnaI Cunctnl:.:i,3n = J-i-A r 4 pCii~c By ilnifia!sl z-, j I Un*t ! i I Ulni; 2 RE.' II: pCi RE-'! ': FC:ic_ ThIs lrm.:n s.uld be uscj fb al! raiej;'di~e ar.Ws s r-:n.

-RLE.ASF ACCOLUNTABILITY - '.lc;;;as n'a.

,.I;\\ A If :'; ovjy f t:!ta! Ec- ..:.i: el:nced in RAM! 2.

x:e:

I.', iiP !: ',,, t -

SAMPLE TYPE: dAP El Gas [ Other Point Bcach NU'lear Plant AIRBORNE RADl OACTIVITY SURVEY RWPNo. _____/___ Sample Localtion: L A I ( -w v'Q. I A. c Remote containment sampling system used? El Yes ElNo I&NA i(I-f Il SAMPLING DATA: SAMPLE SAMPLE SAMPLE START SAMPLE STOP VOLUME SAMPLER BY NUMBER DATE TIME DATE TIME (cc) NUMBER INITIALS Sample Start Flow I (C) Total Sample Time (min) 3Cy Sample Stop Flow Flow Correction Average Sample Flow Remarks GROSS BETA-GAIMMA COUNTING DATA: SAMPLE DATE TIME Counter GROSS BKGD NET MULT. ACTIVITY ' B Y' N TMNumber cpm cpmi cpm py FACTOR (pCiIcc)"'-' INITIALS St5-t /z~ I ';/ '(-I2 I Y/.7 1,r 33-5t a ltis-t1W ,' lfrsampnic3ctivily is grcaterthan or cqual to 5E-10pCi/cc. notify RP supcrviion. perforc gross alpha counting and take or send sample to Chemistry for isotopic analysis.

42)

If sarrpl tak'n frrn an area with known alpha contamination se.g.. reefuling ct vity, spenn tul pool transrmr canal. raacnor head) and sarpIc activity is greaier than IE-I0 pCi/ce. pcrformross alphacounting Lnd take or cnd sanplo Chemistry forisotopicanalysis. ~n nL( at~ fl 1 aT,%rrS, VttlfTl~vr U1KUJ33 ALrrA k LJUNt I iI LJA 1 A: NET DATE TIME Counter GROSS BKGD NET cpm OY/ BY i Number cpm cpm cpm a NET 3 INITIALS _cpm I IIIT t31 irsampic activity ratio of net cpm beta-gamma to net cpm alpha is less than 180. notify RP supervision and perform long-lived alpha counting. El Isotopic Analysis Date l NOBLGS O DACDOS Return to RP by _ hr. for LLA counting. Time Spectrum Index No. El 1r----- Y ACTIVITY BY ISOTOPE (CTiVT) BYNITIALS ISOTOPE (Pci/cc) INITIALS (pI c I I Record RE-2 1I and RE-212 readings for all al-power containment air zuimples. C Unit I C Unit 2 RE-` Il: pCi Record RE-215 readintg and SAE flow for all SAE air samples. C Unit I R Unit 2 RE-215: pCi/cc RE-2 12: pCi/cc SAE Flow: scfm NOTE: All release path air samples must be counted for long-lived alpha. See back side of form.

ase Accountability - tFor release paths only) If the total concentratiun for particulazes (excluding naturalIk ox:urrinr isotopcs) exceeds

_.eE-09 pCi/cc. or the total for noble gpascs exceeds 6.S6E-06 pCi/ce. notify the Chemistry lab supervisor anrior the Radiation Protection supernisor. Save the air particulate filter until the investiation is completed. The sample should he inmestigated to determine its significance as an airhornc release. I'IBF-4022 Revision 16 1I:t./;0

!I. LONG LIVED ALPHA COUNTING DATA: Sample \\'olume (cc): 3. So *. (from Pace I) If the ratio of (C./C) is greater than the value piven in Table 1. and if C2 is greater than 7.5E-13. perform Cm screening. '4'Record LLD for the counter being used at each count O Counter Gross Bkgd Nl Mcl l s ul. l Activity l Hours Activity BY CONT DATE TJ IE No. (cpm) j (cpm) (cpm) Factor (UCicc) I LLD' 4' 1FromC Ratio/C, INIT. C' C4 CLL Rcvicwved By: -DaL /- Date: C `/ MP Supervision COUNTING INFORMATION FOR LONG LIVED ALPHA Count Time C, At T4 Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C2 At T6 Start second count at least 2 hours after C,. C. At Tl Start time dependent upon results of C2. C4 At T2 a Start count 24 hours after C,. Cam At T, 75 Start count at least 75 hours after To. Cum= C,-(Cie

)

I e.1 VALUES OF (C,. 3. ETC.)/C, FOR CLL EQUAL TO ZERO TA LE ______d TABLE 1Il AT IAT AT I AT 1 I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6862 9.5 0.5367 13.25 0.4198 L 2.25 0.8630 6 0.6750 9.75 0.52S0 13.5 0.4130 2.5 0.8490 6.25 0.6641 10 0.5194 13.75 0.4063 2.75 0.83S52 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 10.5 0.5027 16 0.3506 3.25 0.8083 7 0.6322 10.75 0.4945 18 0.3076 3.5 0.7951 7.25 0.6220 11 0.4865 20 0.2698 3.75 0.7S22 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 11.5 0.4708 23 0.222 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.20S 4.5 0.7447 8.25 0.5825 12 0.4557 26 0.182 4.75 0.7326 8.5 0.5731 12.25 0.4483 28 0.160 5 0.7207 8.75 0.5638 12.5 0.4410 30 0.140 C -IC a sna n r .1.zj U.. I ulu 1j 0.'.5546 12.75 0.4338 r l UI NOTES: I1. If the ratio of activit) (C., etc.)1CI is equal to or less than that indicated in Table 1. or if the activity of any count is less than LLD. airborne alpha activity will be considered as not present (the LLD must be S 7.5E-1 3 pCi/cc).

2.

If CL.L is greater than 7.SE-13 plCi/cc. notif% RP supervision for review.

3.

1 the C/IC, ratio is greater than that in Table 1. refer to HPIP 3.53. Counting of Air Samrples for Low Level. Lung-Livcd Radioactive Alpha Particulate Co ntamination. NIPlF-40

.SAMPLE TYPE. D AP 5 Gas 5 Other Point Beach Nuclear Plant R\\\\PNo. C-f1 /3*3 AIRBORNE RADIOACTIVITY SURVEY' Sample Location: L, ( C+/-4 I l / c f I

cA 7Y C {L.

/.

, /

Remote containment sampling system used? 5 Yes O No LNA b; C-> SAMPLING [ATA: SAMPLE SAMPL.E SAMPLE START SAMPLE STOP VOLUME SAMPLER BY NUMBER DATE TIME DATE TIME (cc) NUMBER INITIALS Sample Start Flow i'-. Total Sample Time (min) (c / Sample Stop Flow Flow Correction ' 7 Average Sample Flow Remarks GROSS BETA-GAMMA COUNTING DATA: SAMPLEI DATE TIME Counter GROSS BKGD NET MULT. ACTIVITY BY Number cpm cpm cpm py FACTOR (pCi/cc)tII ' INITIALS 2--f 1 i2S J2 (I....S2.2. / P Iii If sample activity is zreater than or equal to 5E-IpCi!cc. notifr RP supervision. perform gross alpha counting and takc or send sample to Chcmistrv for isotopic analysis. If sample taken from an area with knowvn alpha contamination (e.g. refueling cavitv. spent fuel pool transfer canal. reactor head) and sampic activ ity is greatcr than I E-10 pCilcc perform Sross alpha countine and take or send sampil to Chemistry for isotopic analysis. 1J) If sample activitv ratio of net cpm beta-gamma to net cpm alpha is less than 180. notjfi RP supervision and perform long-lived alpha counting. E Isotopic Analysis Date S1 NOBLGS 5 DACDOS Return to RP by _ hr. for LLA counting. Time Spectrum Index No. ACTIVITY BY ACTIVITY l BY ISOTOPE (pCi/cc) 'INITIALS ISOTOPE (PtCilcc) l INITIALS I I I I I Record RE-' I I and RE-' 12 readings for all at-power containment air samples. [] Unit I E Unit 2 RE-21 1: Ci Record RE-' 15 reading and SAE flow for all SAE air samples. 5 Unit I E Unit 2 RE-215: pCi/cc RE-'12: SAE Flow: _ _ _ p C i. Ccc scfin NOTE: All release path air samples must be counted for lonu-Iived alpha. See back side of form. ReleaC; Accoluntahility - (For releasc paths only) If the total concentration tir particulates (excluding naturally occurring isotopcsl exceeds 6 .-09 pCi "cc. or the total for noble gases exceeds 6.86E-06 pCi/cc. notifl the Chcmistnr lab supervisor and!or the Radiation Protection s .-isor. Save the air pnrticulate tilter until the investigation is completed. The sampie should be investigated to determine its significance as an airorne release. Rc% siicm i 0 1 i/IYo S

11.I 1.7 or C3 2,01(.3 Paie I of2

I1 LONG LIVED ALPHA COUNTING DATA: If the ratio of (CfC1) is greater than tihe value *iven in Table I. and ifC5 is greater than I.5E-I3. perform CLL screening. "4'Rccord LLD for the counter being used at each count. Sample V'olume (cc): (from Page I) 1 1Counter1 Gross Bkgd Net llult. Activiti I lours l Activitv BY C)t'01INT DATE f NrlM E No. J(cpmr) (epnl (Ipm) J Facar (LICi'c) '.LD"' rrom C, Ratio'CJ INIT. C, C.) c t.', = = =___ _=___ I\\'ie-cd 13: ,41U.- /'. Date: 5> S X KP Supervision COUNTING INFORMATION FOR LONG LIVED ALPHA Count Time C, At TJ Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C, At T6 Start second count at least 2 hours after C,. C-At T. Start time dependent upon results of C2. C, At T.s Start count 24 hours after C,. CLL At T., 5 Start count at least 75 hours afterT,,. C,, = C. - (C, e '?)i -e ; VALUES OF (C2,,.,, ETC.)/C, FOR CLL EQUAL TO ZERO TABLE I AT l AT T I AT I AT I I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6862 9.5 0.5367 13.25 0.4198 2.25 0.86301 6 0.6750 9.75 0.5280 13.5 0.4130 2.5 0.8490 6.25 0.6641 1 0.5194 13.75 0.4063 2.75 0.8352 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 10.5 0.5027 16 0.3506 3.25 0.8083 7 0.6322 10.75 0.4945 1 8 0.3076 3.5 0.7951 7.25 0.6220 11 0.4865 20 0.2698 3.75 0.7822 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 11.5 0.4708 23 0.222 1 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.208 4.5 0.7447 8.25 0.5825 12 0.4557 26 0.182 4.75 0.7326 8.5 0.5731 12.25 0.4483 28 0.160 5 0.7207 8.75 0.5638 12.5 0.4410 30 0.140 5.25 0.7090 9 0.5546 12.75 0.4338 .J1 NOTES: I. If the ratio of activity (C2.3 etc.y)C is equal to or less than that indicated in Table 1. or if the activity of any count is less than LLD. airborne alpha activity will be considered as not present (the LLD must be S 7.5E-13 pCi/cc).

2.

If CLL is greater than 7.5E-13 plCilcc, notify RP supervision for review.

3.

If th CC, I ratio is greatcr than that in Table, refer to HPIP 3.53. Counting of Air Samples for Low Level, Lontg-Lived Radioactive Alpha Particulate Contamination. .I1F.4(022 Rtvisiofn I6 11/13/03 ItP 1.I-.1 7 ar C; 2116 ; pn-I 11... I n I

!4AMPLE TYPE: 59AP n Gas n Other Point Beach Nuclar Plant AIRBORNE RADIOACTIVITY SURVEY RWPNo. _____/3_3 Sample Location: £1 ( Cotq-i ijAVt'

F

-.- ::t Remote containment sampling system used? El Yes Elo; SAMPLING DATA: I I I SAMPLE SAMPLE SAMPLE START SAMPLE STOP VOLUME SAMPLER BY NUMBER DATE I TIME DATE I TIME (cc) NUMBER INITIALS 3,-) ( !Cj -_o 50-1 Lt J oot OH 1 - 1 r.l Sample Start Flow Total Sample Time (min) Sample Stop Flow Flowv Correction -________7 Average Sample Flow Remarks GROSS B ETA-GA MMA COUNTING DATA: SAMPLE DATE TIME Counter GROSS BKGD NET MULT. ACTIVITY BY Number cpm cpm cpM Py FACTOR (pCi~cc)" 2 > INITIAS °1 Irsampl acti% ity is greater than or equal to 5E-1pCi/cc. notify RP supcrvision. perform gross alpha counting and takc or send sample to Chemistry for isotopic analysis.

12) 1 fsample taken from an area with known alpha contamination (e.g.. refueling cavity. spent fuel pool transfcr canal. reactor head) and sample activitV is greater than I E-IO pCi/cc. perform gross alpha counting and take or send sample to Chemistry for isotopic analysis.

I I I I I I I 1'J If sample activity ratio of net cpm beta-gamma to net cpm alpha is less than 180. notify RP supervision and perform long-lived alpha counting. El Isotopic AnalN sis Date E NOBLGS Time E DACDOS qnecitnm Index No Return to RP by . hr. for LLA counting. n _I_- ACTIVITY BY ACTIVITY BY ISOTOPE (pCi/cc) INITIALS ISOTOPE (PCi/cc) INITIALS I II I I Record RE-2 I R Unit I Record RE-21 El Unit I I and RE-2 12 readings for all at-power containment air samples. El Unit 2 RE-211: __Ci S readin-and SAE flow for all SAE air samples. [l Unit 2 RE-215: pCi/cc RE-2 12: p C i'c c SAE Flow: scfm NOTE: All release path air samples must be counted for long-lived alpha. See back side of form. Release Accoutohiliv - (Ior release paths only) Ifthe total concentration fbr particulates fexcluding naturally occurring isotopes) exceeds 6.Y`r'i:-19 0'i`Cc. or the total for noble gases exceeds 6.86E.06 pCiicc. notiFy the Chemistry lab supervisor and'or the Radiation l'rotection j' isor. Save the nir particulate tiller until the invcstigation is completed. The sample should be investigatcd to determine its sianificanrc as an at, .lC release. 'l I-Jt,'2 ICIViSij ll j. I [ 3!I3 (I3; It; - I'. C.2 3 Pac I of V.. , I

LONG -IVED AI.PIHA COUNTING DATA: Sample \\'olumle (cc): (from Page 1) If the ratio of(CSrC1) is greater than the value *ivenI in Table 1. and if C: is greater than 7.51E-I. perform CLL screening. ('"Record LLD for the counter bein2 used at ench count. 1 Counter Gross l Bkd 1 Net M Nilt. Alctiit I lours l Activiw l Y COU'NT J A)TE j IT\\NIE No. (cpmi cpmI J(pm) jFc:r (uCi'CLI J l.lD'4 IrromC Rati&Cl INIT. C'. 1 1 i-1 I I I Reviewed 13i: -777cjZrb Date: A"/0 RP Supervision COUNTING INFORMATION FOR LONG LIVED ALPHA Count Time C1 At T4 Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C, At T6 Start second count at least 2 hours after C1. C-At T, Start time dependent upon results of C2. C, At T s Start count 24 hours after C,. CLL At T,. 5 Start count at least 75 hours after To. CLL = C - (CI e') I e VALUES OF (C. 3, ETC.)/C, FOR CLL EQUAL TO ZERO TABLE I I AT AT AT [ AT I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6862 9.5 0.5367 13.25 0.4198 2.25 0.863( 6 0.6750 9.75 0.5280 13.5 0.4130 2.5 0.8490 6.25 0.6641 10 0.5194 13.75 0.4063 2.75 0.8352 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 10.5 0.5027 36 0.3506 3.25 0.8083 7 0.6322 10.75 0.4945 38 0.3076 3.5 0.7951 7.25 0.6220 i 0.4865 20 0.2698 3.75 0.7822 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 11.5 0.4708 23 0.222 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.208 4.5 0.7447 8.25 0.5825 12 0.4557 26 0.182 4.75 0.7326 8.5 0.5731 12.25 0.4483 28 0.160 5 0.7207 8.75 0.5638 12.5 0.4410 30 0.140 5.25 0.7090 9 0.5546 12.75 0.4338 I 31 1 __________________________ II 3 ____________________________ NOTES: I. If the ratio of activity (C2. 3. etc.)/C is equal to or less than that indicated in Table I, or if the activity of any count is less than LLD. airborne alpha activity will be considered as not present (the LLD must be S 7.5E-13 pCi~cc).

2.

If CLL is greater than 7.5E-13 pCifcc, notify RP supervision for review. IfIrtlCC C4CI ratio is greater than that in Table I. refer to HPIP 3.53. Counting of Air Samples for Low Level, Long-Lived Radioactive Alpha Particulate Contamination. NW-340122 Re ision I (6 I I / 3 /03 I33' 1 I

- oC 2 11f, ;

P-..a' ,,f' .1. I r

P. :n:t B.jh N.:clcar Pl!nt IODINE.\\CTIVITY CONCENTRATIONS LOCAT;ON: ,l I cT-rt1 /4':w RP NoX; (-Li-t 3 RF-rnoie totinamen. sianpiing syktm useP LG Yes SA.MPLING DATA: n NO, O.NYA SAMPLE SAMPLE START l SAM\\IPLE STOP SAMPLE SAMPLER N.MIBER V OATE l T\\IET NUMBER INITIALS q--i IL'o I - o-I 2 GC 17 I o - l 3c, -70 l (-)I t O l.{Sbyl / -Y3§S~l R Sample start tSLv \\,v To1tal sample time (minl __1 Saimple stop llhw [:lo% corrt;:.in tctor C ) .Aerave sample flow Remarks .\\NALYSIS DA.TA:

X Is'tL'pic Anah-sv MECDOS it'r DAC data)

S.l. I T I tC~ncentra:i&,un B% j-1 oncer. ;:iun D3 ! i a;:e Tfime lsot ~pe

CiA;;i lni;;3!s Date Tine l'<~p I

Fa It.:ials ~Vc~' .o _l__ K A ~ ~ I. t 13 T I I 1 3 r-S2 l ll 1 o i.e3 l l__ l I l1~dlo i To!al Iodine Concentration - Total Adjitionail Cun.n:raz.in = pKiicc Bi i.Init :f!,s .z i I Lnit ! RE--' 1: pCi RE-' i 2: pC.,icc TN fo nrmn,hould be ubcZ;; aP t rJhclioc~irn ar.;!S'\\ rs;:i! -R.FL EASE ACCOUNTA. ILITY - f.o:.. eiase ratts o n!\\ If :he -,n;e.tr'; 'f z.t ! I,;r _:idi'i; es 'rS 2; -!%-. _Ci;,:. f'0":\\ I; 5L'z:i'ir-eC. i'. RA-M! 5.'. b -vt "i> -. x.e ..:. :'en1,:l.r 7 ~, .n "-:::-' P:-: F :, \\ ' '::::,:;w:-: !-?:

-.). ;,- _" ',

--- ).::e: y / Y

_ MPLE TYPE: MAP E Gas [ Other Point Beach Nuclear Plant RNVP No. 6SI-i AIRBORNE RADIOACTIVITY SURVEY Sample Location: V-I -. 4-+ I Remote containment sampling system used? Fl Yes El No IGi~A SAMPLE NUMBER \\'OLUME (cc) = C/2_0 1j.70Af Sample Start Flow Sample Stop Flow Average Sample Flow 3C I e.- Total Sample Time (min) Flow Correction o.17 Remarks SskA 11dA, GROSS BETA-GAMMA COUNTING DATA: I SAMPLE DATE TIME Counter GROSS BKGD NET MULT. ACTIVITY BY _Number . cpm cprn cpm Py FACTOR (pCifcc) INITIALS 4-0 1 C>ozt-IP--Z 3Zt S I . / 1 3,?. -7 3 ey"P, 5? "1' If sample activitv is greater than or equal to oSE-10,Ci/cc. notify RP sup.rvision. perform gross alpha counting and take or send sample to Chemistry for isotopic analysis. 2' If sampie taken from an area with known alpha contamination (e.r.. refueling cavity. spent fuel pool transfer canal. reactor head) and sampie activity is greater than I E-10 ItCi/cc. perform gross alpha counting and take or send sample to Chemistry for isotopic analysis. '3i If sample activity ratio of net cpm heta-gamma to net cpm alpha is Ies thlan ISO. notify RP supcrvision and perform long-livcd alpha counting. O Isotopic Analysis Date n NOBLGS E DACDOS Return to RP by _ hr. for LLA counting. Time Spectrum Index No. Ol ACTIVITY BY ACTIVITY BY ISOTOPE (pCi/ke) INITIALS ISOTOPE (pCi/cc) INITIALS I I Record RE-2 11 and RE-212 readings for all at-power containment air sanples. El Unit I E1 Unit 2 RE-21 1: pCi Record RE-215 reading and SAE low for all SAE air samples. 0 Unit I ED Unit 2 RE-215: pCi/cc RE-' 12: SAE Flow: pCi/cc scfm NOTE: All release path air samples must be counted for long-lived alpha. See back side of form. ase Accouniahilitv - i For release paths only) If the total concentration for particulates (excluding naturally occurring isotopes) exceeds ,E-09 pCi/cc. or the total for nohle gases exceeds 6.SbE-06 pCi/cc. noiifl the Chemistry lab supnrvisor and/or the Radiation Protection supervisor. Save the air particulate filter until the investigation is completed. The sample should be inmestifated to dcterminc its significance as an airbornc release. Pit P.4022 Rcvision 16 11113,103,

LONG LIVED ALPH.A COUNTING DATA: If the ratio of (C./C,) is greater than the value given in Table 1. and if C2 is greater than 7.5E-13. perform.CL screening. '4'Record LLD for the counter being used at each count. Sample Volume (cc): (from Pare 1) Countcr Gross l Bled N'et Mult. Activity l Hours l Activity l BY COUNT DATE TIME No. kCpm) (cp Factor J Xilccl LLD4' From C,l Ratio/C, INIT. C. C, C.: Rcvicwed By: ~ Date: / ?-6V RP Supervision COUNTING INFORMATION FOR LONG LIVED ALPHA Count Time C, At T4 Start first count 4 hours after sample stop time. (Essentially all radon decayed.) C2 At T6 Start second count at least 2 hours after C,. C., At T, Start time dependent upon results of C2. C4 At T28 Start count 24 hours after C,. Cu. At T,75 Start count at least 75 hours after To. Cu. = C. - (C, e I - e VALUES OF (C.. ETC.)/C, FOR CLL EQUAL TO ZERO TABLE I AT AT l AT AT I 0.9366 5.5 0.6975 9.25 0.5456 13 0.4268 2 0.8772 5.75 0.6862 9.5 0.5367 13.25 0.4198 2.25 0.8630 6 0.6750 9.75 0.52S0 13.5 0.4130 2.5 0.8490 6.25 0.6641 10 0.5194 13.75 0.4063 2.75 0.8352 6.5 0.6533 10.25 0.5110 14 0.3997 3 0.8216 6.75 0.6427 J0.5 0.5027 16 0.3506 3.25 0.8083 7 0.6322 10.75 0.4945 18 0.3076 3.5 0.7951 7.25 0.6220 II 0.4865 20 0.2698 3.75 0.7822 7.5 0.6119 11.25 0.4786 22 0.236 4 0.7695 7.75 0.6019 11.5 0.4708 23 0.222 4.25 0.7570 8 0.5921 11.75 0.4632 24 0.208 4.5 0.7447 8.25 0.5825 32 0.4557 26 0.182 4.75 0.7326 8.5 0.5731 12.25 0.4483 28 0.160 5 0.7207 8.75 0.563S 12.5 0.4410 30 0.140 50.25 0.7090 9 0.5546 12.75 0.4338 NOTES: I. If the ratio of activity (C2.,. etc.)fC, is equal to or less than that indicated in Table 1. or if the activity of any count is less than LLD. airborne alpha activity will be considered as not present (the LLD must be S 7.5E-13 pCi/cc).

2.

If CuL is greater than 7.5E-I3 pCi/cc. notify RP supervision for review. Date Time I C I I lRP Supervision I Dae I Time I C, l C, I

i.

I Alt Cu. I Notified (initials) I I i ij 0.065O j i -i

3.

If the C.,C, ratio is *reater than that in Table I. refer in HPIP 3.5:. Counting of Air Samples for Low Level. Long-Lived Radioactive Alpha Particulate Contaminaiion. I'll- ',:

Poi:nz B:.I.jih Nu.I1cr Plant 10DINE ACTIVITY CONCENTRATIONS LOCAT:ON: U - / C Itle RN%-P N,. af"- / 3-3 Remote ;; rtitn:ment s:ampling Szsyem LSeij ' G eIs 1I No D, 5A i ,srf'.- 71*Th 4 ,) 2 SAMPLING DATA: Sampkle S::rt tln w 3 v L-'vi-Total sample time (min) _7_ Samrnpie Stiop flow Fklw &trel:iL.n fatxor 'c', 7 A4seralet: urnmcle f1Cow Vf5r z,4 -- I ___ 4,- 2f#(LJ-4} - i ANALYSIS DATA: "Xi Isowplic Anah-sis I .MECDOS if fI. DAC Llatta S I. -. To.uJI kcdine Concienlralion - Total Ad4itioamtl Cuncuntration = PzCii;;c By ilnitia!s) i I* l !r t1 j 7 Unit I RE--'i: ,Ci RE-'; 2: pC:icc , !:s*.-~n:.. l e USC _ ;;r

11' TJJICikld;-.eC :l lS:S rLs.

'R.ILEASE ACCOUNT.ABII ITY -

e.

.. Sihs e I :1ic ; +/-::.. ::;nr *' t;.tj! :',. r: : eiaJ! e. eeeJf 5E.C') C.,::. 'e.' ss S;ir:e.n

i. RA.

2. b.ve

e

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ML050880089

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