View source for NRC 2002-0062, Emergency Plan Implementing Procedures EPIP 7.3.7, Revision 5, Stimating Radioiodine Air Concentrations - EPIP 12.1, Revision 14

{{Adams
| number = ML022070312
| issue date = 07/12/2002
| title = Emergency Plan Implementing Procedures EPIP 7.3.7, Revision 5, Stimating Radioiodine Air Concentrations - EPIP 12.1, Revision 14
| author name = Webb T
| author affiliation = Nuclear Management Co, LLC
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000266, 05000301
| license number = DPR-024, DPR-027
| contact person = 
| case reference number = NRC 2002-0062
| document type = Emergency Preparedness-Emergency Plan Implementing Procedures
| page count = 159
}}

=Text=
{{#Wiki_filter:EPIP 7.3.7 ESTIMATING RADIOIODINE AIR CONCENTRATIONS DOCUMENT TYPE:          Technical CLASSIFICATION:        NNSR REVISION:    5 EFFECTIVE DATE:         July 12, 2002 REVIEWER:      Qualified Reviewer APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title):          Group Head OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                     Date         Time List pages used for Partial Performance               Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                             EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                                                             July 12, 2002 TABLE OF CONTENTS SECTION      TITLE                                                                                                                                 PAGE 1.0          PU R P O S E ...................................................................................................................... 3 2.0          PRERE QU ISITES .....................................................................................................                   3 3.0          PRECAUTIONS AND LIMITATIONS ...................................................................                                         3 4.0          IN ITIA L C ON D ITIO N S ............... .............................................................................                 3 5.0          PR O CED U RE ........................................................................................................                  4 5.1    Purging C harcoal Filter ..............................................................................................                 4 5.2    Determ ining Contact Dose Rate .................................................................................                        4 5.3    Determining Radioiodine Air Concentrations ...........................................................                                  5 5.4    D eterm ining DA C-H ours ............................................................................................                  5 6.0          REFER EN C E S .........................................................................................................                5 7 .0         B A S E S ........................................................................................................................... 5 TABLE I CARTRIDGE - CHARCOAL - FLOW RATE - 100 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CON V ERSIO N FACTO R S ..............................................................................................                     6 TABLE 2 CARTRIDGE - CHARCOAL - FLOW RATE - 30 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CON VERSION FACTORS ............................................................................................                           7 TABLE 3 CARTRIDGE - SILVER ZEOLITE - FLOW RATE - 100 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CON VERSIO N FACTORS ............................................................................................                          8 TABLE 4 CARTRIDGE - SILVER ZEOLITE - FLOW RATE - 30 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CON V ERSION FACTO RS ............................................................................................                         9 WORKSHEET 1 IODINE AIR CONCENTRATIONS AND DAC-HOURS/HOUR E ST IM A T ION S ..................................................................................................                10 Page 2 of 10                                                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                             EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                             July 12, 2002 1.0   PURPOSE This procedure provides a method to estimate radioiodine air concentrations when charcoal air sample cartridge dose rates exceed the multichannel analyzer (MCA) counting capability. It uses a set of tables to estimate radioiodine concentrations from contact dose rates.
2.0   PREREQUISITES 2.1      Responsibilities Radiation Protection Supervision (Offsite Radiation Protection Coordinator and/or Radiation Protection Leader) is responsible for:
2.1.1        Estimation of radioiodine air concentrations.
2.1.2        Implementation of radiological monitoring controls.
2.1.3        Ensuring Dose/PAR Coordinator or Rad/Chem Coordinator is informed of results.
2.2      Equipment Emergency Preparedness Radiation Protection Equipment maintained in OSRPF and/or OSC.
3.0   PRECAUTIONS AND LIMITATIONS 3.1      Personnel shall wear prescribed protective clothing, dosimetry devices, and other protection equipment when performing sample analyses.
3.2      Improper handling of radioactive material can result in personnel contamination, radioactive material uptake, unplanned personnel exposure, and cross-contamination of samples.
3.3     An air particulate filter will have been placed in front of the charcoal filter to collect particulate matter and prevent charcoal filter contamination by particulates.
3.4     The total DAC-hours/hour determined by this procedure is for iodine nuclides only.
4.0    INITIAL CONDITIONS 4.1      The contact dose rate reading (after purging, if charcoal filter) on the air sample cartridge is greater than 1 mR/hr or the spectroscopy amplifier dead time is greater than 20%.
4.2      The iodine air sampling cartridge contains activity which exceeds the counting capability of the MCA.
Page 3 of 10                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                        EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                        July 12, 2002 5.0   PROCEDURE 5.1  Purging Charcoal Filter NOTE:      IF a silver zeolite cartridge was used for the sample, THEN no purging is necessary.
IF a charcoal cartridge was used, THEN purge the cartridge with non-radioactive air to remove radioactive noble gases that may have accumulated in the filter. Purging may be accomplished utilizing the following:
NOTE:      Purging should be accomplished inside a chemistry laboratory hood or in an open area away from personnel.
5.1.1      IF service air is utilized to perform the purge, THEN verify that the plant service air is not contaminated.
5.1.2      IF an air sampler is utilized to perform the purge, THEN place the filter in another sampler and operate it in an area outside the known radioactive airborne area. Use a clean particulate filter to prevent contamination from particulates.
5.1.3      Purge until the contact reading on filter stabilizes over 5 minutes.
5.2  Determining Contact Dose Rate NOTE:      The contact dose rate is defined as the dose rate observed when the inlet side of the cartridge is placed in contact with the beta shield of the survey meter in the closed window position. The contact dose rate may be measured through a plastic bag.
5.2.1      Measure the iodine air sampling cartridge contact dose rate with a Survey Meter (i.e., Eberline RO-2, Bicron RSO-5, or equivalent).
5.2.2      Record the contact dose rate on Worksheet 1 and on the plastic bag the cartridge is in.
Page 4 of 10                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                         EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                         July 12, 2002 5.3  Determining Radioiodine Air Concentrations NOTE:       The user may need to interpolate to get the desired numbers from the tables.
5.3.1       Determine the appropriate table to be used by selecting the table matching:
: a. The type of iodine air sampling cartridge used, and
: b. The flow rate used during the air sampling.
5.3.2       Record the conversion factors from the appropriate table on Worksheet 1.
5.3.3       Calculate the radioiodine air concentrations by multiplying the conversion factors by the contact dose rate.
5.4  Determining DAC-Hours 5.4.1        Calculate the DAC-hours/hour for each nuclide listed by dividing the radioiodine air concentration by the corresponding DAC conversion factor.
5.4.2        Sum the DAC-hours/hour for all listed radioiodine nuclides.
5.4.3        Sign/Print the "Complete by" and "Date" sections of Worksheet 1.
5.4.4       Forward the results to the Dose/PAR Coordinator.

==6.0   REFERENCES==

6.1   Correspondence, NEM-89-5 10, Contact Dose Rate to Air Concentration Conversion Factors for 1-130, 1-132, 1-133, 1-134 and 1-135, 8/7/89 6.2  Calculation 1999-0113, Air Cartridge Contact Dose Rate to Air Concentration Conversion Factors for Radioiodines 7.0  BASES B-1  10 CFR 20, Standards for Protection Against Radiation Page 5 of 10                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                  EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                     NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                  July 12, 2002 TABLE 1 CARTRIDGE - CHARCOAL - FLOW RATE - 100 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CONVERSION FACTORS Time                                    Conversion Factor Post-Accident (Hours)                           (gCi/cc per mR/h contact total) 1-131         1-132             1-133             1-134          1-135 0          1.52E-07     2.19E-07          3.12E-07          3.43E-07       2.91E-07 0.5          1.83E-07     2.26E-07          3.68E-07          2.77E-07       3.32E-07 1         2.14-E-07     2.28E-07          4.25E-07          2.19E-07       3.69E-07 1.5         2.46E-07      2.26E-07          4.8 1E-07         1.70E-07       4.04E-07 2         2.78E-07      2.20E-07          5.36E-07          1.30E-07       4.34E-07 4         4.02E-07      1.75E-07          7.30E-07          3.88E-08       5.12E-07 6         5.18E-07      1.24E-07          8.87E-07          1.04E-08       5.39E-07 8         6.31E-07      8.35E-08          1.02E-06          2.62E-09       5.36E-07 10         7.42E-07      5.42E-08          1.13E-06          6.38E10        5.15E-07 12         8.53E-07      3.43E-08          1.22E-06          1.52E-10       4.83E-07 18          1.18E-06     7.93E-09          1.41E-06          1.86E-12       3.63E-07 24          1.49E-06     1.68E-09          1.49E-06          2.1OE- 14      2.50E-07 30          1.78E-06     3.37E-10          1.49E-06          2.23E- 16      1.63E-07 36         2.05E-06      6.48E- 11         1.44E-06          2.28E- 18      1.02E-07 48         2.49E-06      2.21E-12          1.22E-06          2.19E-22       3.68E-08 72          3.11E-06     2.18E-15          7.48E-07          1.72E-30       4.05E-09 96          3.49E-06     1.92E-18          4.11E-07          1.20E-38       4.OOE- 10 168          3.88E-06     1.04E-27          5.37E-08          3.28E-63       3.03E- 13 Page 6 of 10                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                  EPEP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                     NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                  July 12, 2002 TABLE 2 CARTRIDGE - CHARCOAL - FLOW RATE - 30 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CONVERSION FACTORS Time                                   Conversion Factor Post-Accident (Hours)                            (gCi/cc per mR/h contact total) 1-131         1-132             1-133            1-134          1-135 0          1.48E-07      2.13E-07          3.03E-07         3.34E-07       2.83E-07 0.5         1.78E-07      2.19E-07          3.58E-07         2.70E-07       3.23E-07 1         2.08E-07      2.21E-07          4.13E-07         2.13E-07       3.59E-07 1.5         2.39E-07      2.19E-07          4.68E-07         1.65E-07       3.93E-07 2          2.70E-07      2.14E-07          5.21E-07         1.26E-07       4.22E-07 4          3.91E-07       1.70E-07         7.1OE-07         3.78E-08       4.98E-07 6          5.04E-07       1.21E-07         8.63E-07         1.01E-08       5.25E-07 8         6.14E-07      8.13E-08          9.90E-07         2.55E-09       5.22E-07 10         7.22E-07      5.27E-08          1.1OE-06         6.21E-10       5.01E-07 12         8.29E-07      3.34E-08          1.19E-06         1.48E-10       4.70E-07 18          1.14E-06     7.72E-09          1.37E-06         1.81E-12       3.53E-07 24          1.45E-06      1.64E-09         1.45E-06         2.04E- 14      2.44E-07 30          1.73E-06     3.28E-10          1.45E-06         2.17E- 16      1.59E-07 36          1.99E-06     6.30E-11          1.40E-06         2.22E- 18      9.92E-08 48         2.42E-06      2.15E- 12         1.19E-06         2.13E-22       3.58E-08 72         3.03E-06      2.12E- 15         7.28E-07         1.67E-30       3.94E-09 96         3.39E-06       1.87E-18         4.OOE-07         1.17E-38       3.89E-10 168         3.77E-06       1.02E-27         5.23E-08         3.19E-63       2.94E- 13 Page 7 of 10                         REFERENCE USE

POINT BEACH NUCLEAR PLANT                                  EPIP 7.3.7 NNSR EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 5 July 12, 2002 ESTIMATING RADIOIODINE AIR CONCENTRATIONS TABLE 3 CARTRIDGE - SILVER ZEOLITE - FLOW RATE - 100 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CONVERSION FACTORS Time                                    Conversion Factor Post-Accident                        (XCi/cc per mR/h contact total)
(Hours) 1-131        1-132             1-133            1-134         1-135 0          1.64E-07     2.36E-07         3.36E-07          3.70E-07      3.14E-07 0.5          1.97E-07     2.43E-07         3.97E'07          2.99E-07      3.57E-07 1          2.3 1E-07    2.45E-07         4.58E-07          2.36E-07      3.98E-07 1.5         2.65E-07     2.43E-07          5.19E-07         1.83E-07      4.35E-07 2          3.00E-07     2.37E-07          5.78E-07         1.40E-07      4.67E-07 4          4.33E-07     1.89E-07          7.87E-07         4.19E-08      5.52E-07 6          5.59E-07     1.34E-07          9.56E-07         1.12E-08      5.81E-07 8          6.80E-07     9.OOE-08          1.1OE-06         2.82E-09      5.78E-07 10          8.OOE-07     5.84E-08          1.22E-06         6.88E-10      5.55E-07 12          9.19E-07     3.70E-08          1.32E-06          1.64E-10     5.21E-07 18          1.27E-06     8.55E-09          1.52E-06         2.01E-12      3.92E-07 24          1.61E-06      1.81E-09         1.61E-06         2.26E-14      2.70E-07 30          1.92E-06     3.63E- 10         1.61E-06         2.41E-16       1.76E-07 36          2.21E-06     6.99E- 11         1.55E-06         2.46E- 18      1.1OE-07 48          2.68E-06     2.39E-12          1.32E-06         2.37E-22       3.97E-08 72          3.35E-06     2.35E-15          8.07E-07          1.85E-30      4.36E-09 96          3.76E-06     2.07E-18          4.43E-07          1.30E-38      4.31E-10 168         4.18E-06      1.13E-27         5.79E-08         3.53E-63       3.26E-13 Page 8 of 10                         REFERENCE USE

POINT BEACH NUCLEAR PLANT                                  EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                     NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                  July 12, 2002 TABLE 4 CARTRIDGE - SILVER ZEOLITE - FLOW RATE - 30 LPM AIR CARTRIDGE CONTACT DOSE RATE TO AIR CONCENTRATION CONVERSION FACTORS Time                                   Conversion Factor Post-Accident                        (gCi/cc per mR/h contact total)
(Hours) 1-131         1-132             1-133             1-134          1-135 0         1.49E-07     2.14E-07           3.06E-07          3.37E-07      2.86E-07 0.5         1.79E-07     2.21E-07           3.61E-07          2.72E-07      3.25E-07 1         2.1OE-07     2.23E-07           4.17E-07          2.15E-07      3.62E-07 1.5        2.41E-07     2.21E-07           4.72E-07          1.67E-07      3.96E-07 2         2.73E-07     2.15E-07           5.25E-07          1.27E-07      4.25E-07 4         3.94E-07      1.72E-07          7.16E-07          3.81E-08      5.02E-07 6         5.08E-07      1.22E-08          8.70E-07          1.02E-08       5.29E-07 8         6.19E-07      8.19E-08          9.98E-07          2.57E-09       5.26E-07 10         7.28E-07      5.31E-08          1.11E-06          6.26E- 10      5.05E-07 12         8.36E-07      3.36E-08          1.20E-06          1.49E-10      4.74E-07 18          1.15E-06     7.78E-09          1.38E-06          1.83E-12       3.56E-07 24          1.46E-06     1.65E-09          1.46E-06          2.06E- 14      2.46E-07 30          1.75E-06     3.30E-10          1.46E-06          2.19E- 16      1.60E-07 36         2.01E-06      6.35E-11           1.41E-06         2.24E- 18      1.00E-07 48         2.44E-06      2.17E-12           1.20E-06         2.15E-22       3.61E-08 72         3.05E-06      2.14E- 15         7.34E-07          1.68E-30       3.97E-09 96         3.42E-06      1.89E-18          4.03E-07          1.18E-38       3.92E- 10 168        3.80E-06      1.02E-27          5.27E-08          3.21E-63       2.97E-13 Page 9 of 10                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 7.3.7 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 5 ESTIMATING RADIOIODINE AIR CONCENTRATIONS                            July 12, 2002 WORKSHEET 1 IODINE AIR CONCENTRATIONS AND DAC-HOURS/HOUR ESTIMATIONS Time of shutdown Time air sampling initiated Time contact dose rate determined Time elapsed between shutdown and start of air sampling                              hours Sample Volume                                                                        cc Iodine air sampling media used:       Charcoal        Silver Zeolite (Circle one)
Was charcoal cartridge purged?        Yes        No (Circle one)
Contact dose rate (after purging, if charcoal filter)                                mremrhr Air Concentration Conversion Factor         Contact from Tables 1-4        Dose Rate         DAC*
Nuclide     (gCi/cc per mR/h)         (mR/h)          (jiCi/cc)       DAC-hours/hour 1-131                          X                        2E-8 1-132                          X                        3E-6 1-133                          X                        1E-7 1-134                          X                        2E-5 1-135                          X                        7E-7 Total                         DAC-hours/hour
* 10 CFR 20, Appendix B, Table B-1 Completed By:                                          Date:               Time:
FORWARD THE RESULTS TO THE DOSE/PAR COORDINATOR Page 10 of 10                        REFERENCE USE

EPIP 8.4.1 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH ACTIVITY REACTOR COOLANT DOCUMENT TYPE:          Technical CLASSIFICATION:         Safety Related REVISION:     15 EFFECTIVE DATE:         July 12, 2002 REVIEWER:       Qualified Reviewer APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title):           Group Head OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                     Date         Time List pages used for Partial Performance               Controlling Work Document Numbers

PONT BEACH NUCLEAR PLANT                                                                                      EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                        SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                                                        July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT TABLE OF CONTENTS SECTION    TITLE                                                                                                                                PAGE 1.0        P U R P O S E ...................................................................................................................... 4 2.0        PRERE Q U ISITES .....................................................................................................                 4 3.0        PRECAUTIONS AND LIMITATION .....................................................................                                       4 4.0        IN ITIA L C O N D IT IO N S ................................................................................................           5 5.0        PR O C E DU RE ............................................................................................................             6 5.1  Prelim inary E valuation ...............................................................................................                6 5.2  Preparation Of Sampling Equipment And Laboratory Setup ....................................                                             9 5.3  Approvals For Implementing Sampling And Analyses ............................................                                          13 5.4  Reactor Coolant Sampling .......................................................................................                       14 5.5  Collecting Gaseous Sample From Pressurized Sample Vessel .................................                                             33 5.6  Analyzing Gaseous Sample ......................................................................................                        35 5.7  Collecting Liquid Sample From Sample Vessel .....................................................                                      37 5.8  A nalyzing Liquid Sam ple ..........................................................................................                   38 5.9  Submittal Of Sampling/Analyses Documents ..........................................................                                    41 5.10 Sampling/Analysis Report And Continuation Of Procedure - Chemistry Supervision                                                         41 5.11 L abeling Sam ples .....................................................................................................               41 5.12 S am ple Storage ..............................................................................................................        41 5.13 System Normal Valve Lineup ...................................................................................                         42 5.14 Re-Installation Of Shielded Sample Vessel ..............................................................                               44 5.15 Preparation/Transfer Of Sample(S) To Off-Site Laboratory ...................................                                           47 5.16 Post-Analysis Documentation/Submittal ................................................................                                 48 6.0        R EFE R E N CE S ..............................................................................................................        49 7 .0       B A S E S .......................................................................................................................... 49 Pag-e 2 of 55                                                       CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                             EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                                July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT TABLE OF CONTENTS SECTION   TITLE                                                                                                        PAGE ATTACHMENT A   PRIMARY COOLANT HIGH-LEVEL SAMPLING FLOW DIAGRAM ...... 50 ATTACHMENT B   SETUP FOR TRANSFER OF SAMPLE FROM SAMPLE VESSEL ......                                                   51 ATTACHMENT C   PBNP REACTOR COOLANT POST-ACCIDENT SAMPLING AND A N A LY SIS REPORT ................................................................................... 52 Page 3 of 55                                                      CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                  EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                     SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                     July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT Reason for performance: E] Drill      [-] Training   El Fuel Failure Unit Being Sampled: [] Unit 1       LI Unit 2 1.0    PURPOSE This procedure provides instructions for collecting, handling, and analyzing a (potentially high radioactivity) reactor coolant sample with due to fuel failure.
This procedure may also be used for training and drills or exercises. Chemistry supervision may exclude any section or step where performance may adversely affect operation of unit.
2.0    PREREQUISITES 2.1     Responsibilities 2.1.1       The Shift Manager (SM) Operations Support Center Coordinator if TSC is activated) is responsible for the management of the reactor coolant sample collection and analysis.
2.1.2       Radiation Protection (RP) Supervision (Rad/Chem Coordinator if TSC is activated) is responsible for the radiological monitoring controls.
2.1.3      Chemistry Supervision (Chemistry Leader is OSC is activated) is responsible for sample collection and analysis.
2.2     Equipment 2.2.1      Emergency Preparedness Radiation Protection Equipment maintained in OSC.
2.2.2       Refer to Step 5.2 for Chemistry equipment.
3.0    PRECAUTIONS AND LIMITATIONS 3.1     During performance of radiological sampling activities, personnel may be subjected to radiological hazards including high radiation, contamination, and airborne radioactivity.
3.2     Personnel shall wear prescribed protective clothing, dosimetry devices, and other protective equipment, as required by the applicable Radiation Work Permit (RWP) or Re-entry Permit, when performing radiological sampling.
3.3     Improper handling of radioactive material can result in personnel contamination, radioactive material uptake, and unplanned personnel exposure.
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POINT BEACH NUCLEAR PLANT                                                 EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                    SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                    July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT 3.4     SM approval is required for connecting DI-148 (DI Header To High Radiation Sample System) to the DI (deionized) water manifold, and Unit Control Operator (Unit CO) shall be informed prior to initiating DI flush because flush will dilute reactor coolant and affect reactivity. Unit CO shall also be notified upon completion of flush.
3.5     Reactor Coolant system samples shall be taken within three (3) hours from the time a decision is made to dispatch a sample team.
NOTE:        SC-956C and SC-990 (Step 3.6) may be required for containment isolation should SC-955 or SC-959 (Step 3.7) fail to shut.
3.6     SM approval is required for opening the following valves when they are being used for containment isolation (i.e., only one other valve operable upstream):
3.6.1       SC-946, HX-14C RC Hot Leg Sample HX DI Flush 3.6.2       SC-956C, HX-14C RC Hot Leg Sample HX Inlet 3.6.3      SC-990, HX-14C RC Hot Leg Sample HX Inlet RHR 3.7     Unit CO shall be notified immediately should the following containment boundary valves fail to SHUT within 15 seconds of moving valve switch to CLOSE position:
3.7.1      SC-955, RC Hot Leg Sample Isolation 3.7.2      SC-959, RHR Loop Sample Isolation 3.8      Sample vessel shall be re-installed with shielding upon completing training, drill, or exercise.
3.9     Flush and blow dry laboratory stripping apparatus upon completing training, drill, or exercise.
4.0   INITIAL CONDITIONS Indications of fuel failure.
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POINT BEACH NUCLEAR PLANT                                              EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                 SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                 July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.0   PROCEDURE 5.1  Preliminary Evaluation NOTE:     This section shall be completed prior to entering the Auxiliary Building OR Sample Room to obtain Reactor Coolant samples under emergency conditions.
NOTE:     Equipment collection and laboratory setup (Section 5.2) may be performed concurrently with this section.
5.1.1      Indications of Possible Fuel Damage NOTE:       Fuel damage may be the cause when any of the conditions in Steps 5.11.a - 5.11.h exist.
Circle step number(s) and initial to indicate existing condition(s), and enter N/A for conditions that do NOT exist:
: a. Letdown Valve Gallery Monitor (RE- 116) reading is unusually high OR offscale high. (Containment isolation may invalidate readings.)
: b. Post Accident Sample Line Monitor, l(2)RE-109 reading is unusually high OR offscale high. (Containment isolation may invalidate readings.)
: c. Containment Air Particulate Monitor, l(2)RE-211 and Containment Noble Gas Monitor, 1(2)RE-212 readings are unusually high OR offscale high. (RE-211/212 readings may be invalid if containment is isolated.)
: d. Containment Low-Range Monitor, 1(2)RE-102, and Seal Table Monitor, 1(2)RE- 107 readings are unusually high OR offscale high.
: e. Auxiliary Building Vent Stack Monitor, RE-214 is indicating a significant increase due to Auxiliary Building airborne activity from the Letdown and Charging Pump areas.
: f. Charging Pump Room Low Range Monitor, 1(2)RE- 104 is indicating increased radioactivity in the Auxiliary Building.
Page 6 of 55                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: g. Sample Room Low Range Monitor, l(2)RE-106 is indicating increased radioactivity in the Sample Room and Background Monitor, 1(2)RE-219B is indicating increased radioactivity outside Sample Room.
: h. Chem Lab Low Range Monitor, RE-103 is indicating increased radioactivity in laboratory (prior to sample analysis).
5.1.2  Verification of Component Cooling and Instrument Air NOTE:       This section (5.1.2) is NOT required for training.
NOTE:       Sample cannot be obtained without component cooling to Sample Room heat exchangers and instrument air for operating air operated sample valves.
Contact SM and confirm following (circle as appropriate):
: a. Component Cooling In-Service in affected unit (Yes       No)
: b. Instrument Air In-Service in affected unit      (Yes No) 5.1.3  Pre-Job Briefing and Evaluation of Potential Radiological Hazards for Sampling and Analysis Functions Attend pre-job briefing which includes Chemistry supervision, Radiation Protection (RP) supervision (or designee), and affected Chemistry technicians to evaluate the following, based on Radiation Work Permit(s) OR reentry permit(s), radiological survey/monitor data, Calculation 98-0058 (Post-LOCA Reactor Coolant Sample System Dose Rate), AND Attachments A-B.
Page 7 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                       EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                          July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:     RP determines radiological hazards in access and sampling/analysis areas, dosimetry/respiratory requirements, stay times, and dose estimates, based on radiation dose rate (area and contact), estimated time required for each task, and shielding/distance(s) indicated by chemistry.
: a. Chemistry supervision:
I. Provide input as requested by RP and Chemistry Technician(s) regarding sampling and analysis functions.
: 2. Determine which valve/instrument/component position verification(s) OiR other function(s) in procedure may be omitted as a means for minimizing radiation exposure, based on knowledge of pre-event lineups, laboratory readiness, historical data, value gained/lost by performing/NOT performing, etc., i.e.:
(a)   Omit section(s) NOT to be performed (e.g., If radiation dose from pre-sample flush may negate any reduction in over-all dose, then section should be omitted).
(b)   Omit steps NOT to be performed (e.g.,
sampling equipment Steps 5.2.1.b and 5.2.1 .c may already be in location for use, AND Steps 5.4.2.i through 5.4.2.k should already be in desired position.
(c)   Choose flow path to be used, i.e., if SC-955/966C OR SC-959/990 used, omit steps/sub-steps for flow path NOT used.
: 3. Ensure N/A entered and initialed for any section/steps/data lines omitted AND affected selection boxes are checked.
: 4. Provide other suggestions for reducing exposure time and completing procedure in timely manner, as applicable.
Page 8 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: 5. Assign sampling/analysis functions among chemistry personnel, as necessary to maintain exposure ALARA.
: b. Chemistry Technician(s): Provide input as requested by Chemistry supervision OR RP, AND ask questions, as necessary to ensure all concerns are adequately addressed.
5.2  Preparation Of Sampling Equipment And Laboratory Setup 5.2.1      Sampling Equipment List
: a. Obtain the following equipment and supplies:
: 1. Two-way radio and spare battery
: 2. Waste container for collecting possible drips from High Rad Sampling Station (HRSS) sample vessel fittings
: 3. Polyethylene bags for trash, and large bag(s) to cover sample vessel during transport
: 4. Paper towels to control/contain potential leaks or spray during connection/disconnection of sample vessel NOTE:       Items in Step 5.2.1.b AND 5.2.1.c are normally maintained for immediate use at locations specified in each step. Chemistry supervision may enter N/A for these steps when items are known to be positioned as indicated.
: b. Ensure the following equipment is positioned adjacent to Unit 1 Sample Room (normal location) AND ready for use:
: 1. Sample cart designated for transport of sample vessel
: 2. Wrenches, 5/8" and 11/16", open-end (or adjustable) for connecting and disconnecting sample vessel
: 3. Remote valve turning tool
: 4. Syringe for evacuating liquid from sample vessel fittings
: 5. Shielded waste bottle Page 9 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: c. Ensure the following are positioned for use in the Primary Sample Hood:
: 1. Equipment detailed in Attachment B, excluding sample vessel
: 2. Remote handling tools located in cabinet below the hood NOTE:  Preparation of Laboratory Equipment can be completed in any logical sequence as deemed applicable by the performers.
5.2.2  Laboratory (Analysis) Equipment
: a. Gas Chromatograph (G.C.)
: b. Ion Chromatograph (I.C.)
: c. Multichannel Analyzer (MCA)
: d. pH/mv meters (120v AC or battery powered) and pH probe
: e. Magnetic stirrers; (120v AC, battery, or water/air powered),
one 50 ml polyethylene beaker, and a 50 ml beaker
: f. Piston burette; manual or auto
: g. Automatic pipets; continuously adjustable through 5 ml, or equivalent
: h. One, 1.0 liter sidearm flask with correctly sized solid stopper and rubber septum over sidearm
: i. Gas Collection Vessel, glass.
: j. Gas syringe, pressure-lock, or equivalent
: k. Beaker, 50 ml
: 1. Mini-lab analyzer, as required by Chemistry supervision
: m. Lead brick barricade (wall) of sufficient size to temporarily shield sample in analytical hood Page 10 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.2.3   Reagents, Standards, and Bottled Gases
: a. NaOH, 0.1N for boron (May be obtained from normal boron analysis reagents.)
: b. Mannitol for boron analysis
: c. Boron standard, appropriate for expected boron concentration
: d. Calibration gases for G.C.
: e. Carrier and valve gas (if applicable)
NOTE:   Preliminary Equipment checks can be completed in any logical sequence as deemed applicable by the performers.
5.2.4   Preliminary Equipment Check and Preparation NOTE:        Chemistry supervision selects instruments to use.
(Step 5.2.4.a)
: a. Ensure current calibration on following instruments and startup instruments (if necessary), in accordance with applicable CAMP procedures, and as directed by Chemistry supervision:
: 1. G.C.
: 2. I.C.
: 3. MCA
: b. Ensure daily QA check performed and results are within limits specified in applicable CAMP procedure for instrument selected (Step 5.2.4.b) and analysis parameters listed below:
: 1. G.C. for hydrogen analysis and hydrogen result
: 2. I.C. for chloride analysis and chloride result
: 3. MCA for noble gas and iodine analyses and results Page I11 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                             July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:      In the event of loss of AC power to laboratory, a battery-powered pH meter and a battery, air, OR water-powered magnetic stirrer may be used.
: c. Standardize pH meter and ensure mid-point check within +/- 0.1 su.
: d. Check and prime piston burette with 0.1 N NaOH solution.
: e. Perform QA check on boron standard and ensure result within +/- 1 ppm for 10 - 19 ppm standard OR +/- 1% or +/- 1 ppm (whichever is greater) for 20 - 2000 ppm standard.
: f. Organize equipment behind lead brick barricade to allow view of operations with aid of mirror.
: g. Set up Gas Collection Vessel, ensuring the following:
: 1. New septum installed AND Valve 2 OPEN
: 2. Vacuum line attached to vessel at Valve 1
: 3. Valve 1 OPEN AND valve 3 SHUT
: 4. Outlet line to liquid sample vessel capped AND vacuum established
: 5. Valve 1 SHUT AND vacuum stable
: 6. IF vacuum decreases, THEN ensure the following:
(a)   Valves SHUT (b)   Rubber septum replaced (c)   Fittings are tight (d)   Vacuum re-applied AND Steps 5.2.4.g.3 - 5.2.4.g.5 repeated until vacuum stable
: h. Rinse sample vessel drain tube, receiving beaker, and tips of transfer pipets with DI water to remove any chloride contamination.
Pagre 12 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS
: i. Perform two-way radio check with Control Room AND Operation Support Center (OSC), as applicable.
: j. IF DI water flush desired by Chemistry supervision, THEN obtain SM permission for connecting DI water to DI water manifold.
5.3  Approvals For Implementing Sampling And Analyses NOTE:          Steps 5.3.1 and 5.3.2 are NOT required for training.
Obtain verbal approval to implement sampling and analyses from:
5.3.1      Shift Manager (SM) (Operations Support Center Coordinator if TSC is activated) 5.3.2      Duty and Call Radiation Protection Supervisor (Rad/Chem Coordinator if TSC is activated)
Page 13 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                             EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.4  Reactor Coolant Sampling NOTE:          The terms, demineralized and deionized (DI) water are both used in CHAMP component names for the same water. The term DI is used in this procedure except when demineralized is used in the CHAMP name.
NOTE:          For drills and training, DI water flush and sample dilutions are NOT to be performed unless otherwise directed by Chemistry supervision.
CAUTION Sampling (fuel failure only) shall NOT begin until preliminary evaluation is completed and all approvals for implementation have been received.
CAUTION Performance of a DI water flush will dilute the reactor coolant, and affect reactivity.
5.4.1      Preparation for Collecting Pressurized Sample
: a. Contact Unit CO AND, perform following:
I. Inform Unit CO of following, as applicable:
(a)   PASS sampling (including installation of shielded sample vessel, as applicable) to begin.
(b)   RE-109, Post Accident Sample Line Monitor to be removed from service while sampling (c)   SC-955, RC Hot Leg Sample Isolation valve will be SHUT.
: 2. Have Unit CO SHUT SC- 966C, RC Hot Leg Sample (isolation valve), as applicable.
Page 14 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS IN4ITIALS
: b. Proceed with sample cart (loaded with sampling equipment) to HRSS outside appropriate Sample Room, 26' elevation, Primary Auxiliary Building (PAB).
: c. Ensure SC-955 SHUT.
: d. IF shielded sample vessel installed, THEN enter N/A for Steps 5.4.1.e AND GO TO Step 5.4. L.f
: e. IF shielded sample vessel NOT installed, THEN perform following:.,
: 1.      Place a waste container under sample vessel fittings to collect potential drips.
CAUTION System pressure shall be relieved by opening valves in Step 5.4.1.e.2 before loosening sample vessel fittings.
: 2.      OPEN following valves to relieve possible pressure in system.
ID                          Name                   Initials SC-939      Z-5E High Rad Sample Vessel Inlet SC-940      Z-5E High Rad Sample Vessel Bypass SC-941      Z-5E High Rad Sample Vessel Outlet
: 3.      Ensure the following valves are SHUT:
ID                          Name                   Initials SC-939      Z-5E High Rad Sample Vessel Inlet SC-940      Z-5E High Rad Sample Vessel Bypass SC-941      Z-5E High Rad Sample Vessel Outlet Page 15 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                             July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS CAUTION Paper towel shall be used to contain potential spray when performing Step 5.4.1.e.4.
: 4. Disconnect (carefully) sample vessel fittings using care to contain potential spray and prevent possible contamination.
: 5. Allow any liquid in line to drain into waste container.
: 6. Install shielded sample vessel on HRSS sample vessel fittings.
: f. Perform following:
: 1. Ensure the sample vessel fittings are tight.
: 2. Ensure the following valves are SHUT:
ID                        Name                      Initials SC-939       Z-5E High Rad Sample Vessel Inlet SC-940       Z-5E High Rad Sample Vessel Bypass SC-941       Z-5E High Rad Sample Vessel Outlet 8A       Sample Vessel Valve 8B       Sample Vessel Valve 9A       Sample Vessel Valve 9B       Sample Vessel Valve Page 16 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:   N/A Section 5.4.2 if NOT performing a presample flush.
5.4.2   Pre-Sampling Flush
: a. Connect DI water line quick-connect from valve DI-148 to the DI water manifold, AND ensure the quick-connect is unlocked.
: b. Ensure the following valves are SHUT:
ID                             Name                       Initials DI-148    DI Header To High Radiation Sample System SC-946    HX-14C RC Hot Leg Sample HX DI Flush SC-947    Z-5E High Rad Sample Vessel DI Flush Inlet SC-948    Z-5E HighRad Sample Vessel DI Flush Outlet NOTE:       Next step is performed only to determine if pump will energize. Pump is NOT to be left on after performance.
: c. IF P-166, Demineralized Water Flush Pump to be used, THEN perform following:
: 1. Ensure the motor starter switch for P-166, is unlocked.
: 2. Check that P-166 is energized by momentarily switching pump ON, then OFF.
: d. IF P-166 did NOT energize, THEN have Unit CO ensure Breaker No. 4 on Panel 1Y-l 14/2Y- 113 (U1/2 Rod Drive Room) CLOSED, then repeat Step 5.4.2.c.
: e. IF P-166 still did NOT energize, THEN discontinue effort to start pump. (DI water header pressure to be increased at later step.)
: f. IF N/A entered by Chemistry supervision for all Steps 5.4.2.i through 5.4.2.k, THEN GO TO note/caution preceding Step 5.4.2.1.
Page 17 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: g. IF Chemistry supervision did NOT omit all Sample Room valve position verifications, THEN review Steps 5.4.2.i through 5.4.2.k for familiarization with valves needing verification.
: h. Obtain SM approval to open SC-946/SC-956C, as applicable AND enter Sample Room.
NOTE:       Sign-offs (below) may be initialed after all positions verified.
: i. Ensure valves are positioned as indicated in position column, as follows:
ID                             Name                              Position    Initials SC-961C HX-14C RC Hot Leg Sample HX Outlet                            SHUT SC-964C RC Hot Leg Sample Throttle                                    SHUT SC-965C Z-5C RC Hot Leg Sample Vessel Bypass                          SHUT SC-971 RC Hot Leg Grab Sample                                        SHUT SC-968 Z-5C Sample Pressure Vessel Common Outlet                     SHUT SC-938A RE-109 Failed Fuel Monitor Inlet                              SHUT SC-938B RE-109 Failed Fuel Monitor Outlet                             SHUT SC-938C RE-109 Failed Fuel Monitor Flow Throttle                      SHUT SC-938 HX-14C RC Hot Leg HX Out To High Rad Sample                   OPEN System SC-969A FI-903 Flow Indicator Purge Line To T-4 VCT Isolation         OPEN SC-956C HX-14C RC Hot Leg Sample HX Inlet                             OPEN
: j. Ensure component cooling flow to Sample Room Heat Exchangers by viewing FI-603, Sample System HX Shell Side Outlet Flow Indicator on Sample Panel.
CAUTION SC-990 shall NOT be used for drill OR, training.
: k. Ensure SC-990, HX-14C RC Hot Leg Sample HX Inlet RHR Sample OPEN, then exit to low radiation area.
Page 18 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                        EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                           July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS CAUTION Unit CO shall be informed prior to initiating DI flush because this evolution can affect reactivity.
NOTE:      Steps 5.4.2.1 - 5.4.2.x required only if DI water flush is performed, as directed by Chemistry supervision.
: 1. Ensure the following valves OPEN:
ID        Initials SC-939 SC-940 SC-941 DI- 144 NOTE:      SM approval required to open SC-946 following containment isolation if SC-966C fails to shut.
: m. OPEN following valves:
ID        Initials DI-140 DI-145 DI-148 SC-946 Page 19 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                      EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                         July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:      To minimize radiation dose during an emergency event, Chemistry supervision may have omitted Step 5.4.2.n
: n. IF N/A NOT entered by Chemistry supervision for Steps 5.4.2.n. I - 5.4.2.n.2, THEN check DI water system lineup for applicable unit, as follows:
: 1. Unit 1: Ensure DI flow by momentarily OPENING, checking flow, then SHUTTING DI water valve in Primary Sample Hood.
: 2. Unit 2: Ensure OPEN DI water valve (DI-57) located on east wall of Sample Room.
: o. IF P-166 to be used, THEN perform following:
: 1. Ensure valve DI-142 SHUT.
: 2. Ensure valve DI-143 OPEN.
: 3. Turn pump switch ON AND record time:
Time:
: 4. Exit to low radiation area.
: p. IF P-166 would NOT energize at Step 5.4.2.o, THEN perform following:
: 1. Ensure OPEN DI-142, P-166 Flush Pump Bypass.
: 2. Ensure SHUT DI-143.
: 3. Record system pressure as indicated on PI-4145:
_          psi
: 4. Exit to low radiation area.
Page 20 of 55                      CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: 5. IF system pressure (Step 5.4.2.p.3) is less than 80 psi, THEN contact Unit CO, AND request that DI water header pressure be maximized and the time pressure maximized be provided.
: 6. Record time pressure maximized:
Time:
: q. Time flush, as follows:
: 1. IF flushed using P-166, THEN wait approximately 2 minutes.
: 2. IF flushed by maximized DI water header pressure, THEN wait approximately 15 minutes after header pressure maximized.
: r. Return to HRSS AND measure radiation levels in Sample Room OR general area, as applicable.
: s. Record data below AND exit to low radiation area:
: 1. Time:
: 2. Radiation Level:            mR/Hr; Location:
: 3. PI-4145 pressure indication:            psi
: t. Notify Chemistry supervision of radiation dose rate, AND wait for instructions on system flush.
: u. IF Chemistry OR RP supervision directs discontinuation of flush, THEN N/A Step 5.4.2.v AND GO TO Step 5.4.2.w.
Page 21 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 SAFETY RELATED EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 15 July 12, 2002 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS
: v. IF Chemistry OR RP supervision directs continuation of flush, THEN repeat Steps 5.4.2.q - 5.4.2.t, AND record data in Table A (below) until Chemistry Oil RP supervision directs discontinuation of flush, as applicable:
Table A Flush #      PI-4145         Time       mR/hr psig                   After Flush 2
3 4
: w. Secure flush according to following:
: 1. IF flushed by P- 166, THEN turn P- 166 OFF AND record time flush STOPPED, AND total flush time:
Time:                 Total Flush Time:         minutes
: 2. IF flushed by maximized DI water header pressure, THEN SHUT DI-142, AND record time flush STOPPED, AND total flush time:
Time:                 Total Flush Time:          minutes
: 3. SHUT following valves:
ID         Initials SC-946 SC-939 SC-940 SC-941
: x. Notify Unit CO DI water flush completed.
Page 22 of 55-                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 SAFETY RELATED EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 15 July 12, 2002 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.4.3   Pressurized Sample Collection
: a. Contact Control Room AND perform following:
: 1. Obtain SM permission to OPEN one of following AND check block to indicate valve to be opened:
[] SC-955, RC Hot Leg Sample Isolation OR
                              - SC-959, RHR Loop Sample Isolation NOTE: Cycling of Containment Isolation valves may be necessary to reset isolation signal to allow sampling.
: 2. Have Unit CO reset containment isolation signal on valve selected to enable sampling, OR N/A if NOT applicable.
NOTE:       Valve positions are indicated on switch panels by green AND red lights, as follows:
                                  -    Green light (only) lit = SHUT
                                  -    Red light (only) lit = OPEN
                                  -    Both lights lit = Intermediate Position
: b. OPEN isolation valve selected (Step 5.4.3.a.1), using local control switch on switch panel outside Sample Room, AND check block for valveOPENED:
                       - SC-955 OR LIISC-959 Page 23 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                             July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: c. IF valve selected (Step 5.4.3.a.1) will NOT open because containment isolation signal NOT reset, THEN perform following:
: 1. Have Unit CO ensure the containment isolation signal for SC-955 OR SC-959 (as applicable) has been reset.
: 2. Ensure SC-955 OR SC-959, as applicable SHUT by placing applicable control switch on panel outside of Sample Room in CLOSE position, AND check block to indicate valve shut.
D&#xfd; SC-955 OR D-- SC-959
: 3. Ensure SC-955 OR SC-959, as applicable OPEN by placing applicable control switch in OPEN position, AND check block to indicate valve opened.
F-- SC-955 OR D-1 SC-959
: d. Ensure valve positions as indicated in position column, as follows:
ID                               Name                           Position    Initials SC-961C   HX-14C RC Hot Leg Sample HX Outlet                      SHUT SC-964C   RC Hot Leg Sample Throttle                              SHUT SC-965C   Z-5C Hot Leg Sample Vessel Bypass                       SHUT SC-971    RC Hot Leg Grab Sample                                  SHUT SC-968    Z-5C Sample Pressure Vessel Common Outlet               SHUT SC-938A   RE-109 Failed Fuel Monitor Inlet                        SHUT SC-938B   RE-109 Failed Fuel Monitor Outlet                       SHUT SC-938C   RE-109 Failed Fuel Monitor Flow Throttle                SHUT SC-938    HX-14C RC Hot Leg Hx out to High Rad Sample              OPEN System SC-969A   FI-903 Flow Indicator Purge Line to T-4 VCT              OPEN Isolation SC-956C   HX-14C RC Hot Leg Sample Hx Inlet                        OPEN Pag~e 24 of 55                       CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                             July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: e. Ensure following valves OPEN:
ID                         Name                      Initials 9B       Sample  Vessel  Valve 9A       Sample  Vessel  Valve 8A       Sample  Vessel  Valve 8B       Sample  Vessel  Valve CAUTION For drill OR training exercises only. SC-941 shall be cracked OPEN slightly AND flow maintained at 0.5 - 1.0 gpm by THROTTLING SC-941 to minimize N-16 gamma.
NOTE:       FI-903 (located inside Sample Room) can be used as aid for setting flow rate if dose rates permit.
NOTE:       Observe pressure indication PI-995 when throttling SC-941 or opening SC-966C.
: f. Ensure OPEN SC-939 AND throttle SC-941.
: g. IF sample being taken off Hot Leg (i.e., only SC-955 being used)
THEN have Unit CO OPEN SC-966C.
: h. Ensure sample flow by confirming one OR both of following indications, as desired (n/a if needed):
: 1. Increase in radiation level at Sample Vessel
: 2. Pressure increase/decrease indication on PI-995 when SHUTTING/OPENING Valve SC-941
: i. Exit to low radiation area.
Page 25 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 SAFETY RELATED EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 15 July 12, 2002 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:        Next step should be performed immediately before returning to HRSS to obtain sample.
: j. Contact Unit CO AND obtain/record following pressure indications, as applicable:
(RCS):     -   psig OR RHR:    _    psig    VCT __ .psig
: k. WHEN sample has recirculated for 15 minutes, THEN return to HRSS to collect sample.
: 1. IF reading on PI-995 NOT between RCS AND VCT pressure, THEN exit to low radiation area, notify Chemistry supervision, AND wait for instructions.
NOTE:       Use the remote valve operating tool only as needed to reduce dose.
: m. SHUT following valves IN EXACT ORDER listed.
ID                        Name                     Initials 9B       Sample Vessel Valve 9A       Sample Vessel Valve 8B       Sample Vessel Valve 8A       Sample Vessel Valve
: n. Record sample time, AND check that PI-995 indicates less than 100 psig AND is NOT increasing:
Sample time:
: o. IF PI-995 equal to or greater than 100 psig, OR is increasing, THEN notify Chemistry supervision, AND wait for instructions.
Page 26 of 55                       CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:      Sample vessel is NOT to be disconnected until sample flow is secured and DI flush (if being performed) is completed.
NOTE:      Valve positions are indicated on switch panels by green and red lights, as follows:
                             -       Green light (only) lit = SHUT
                             -       Red light (only) lit = OPEN
                             -       Both lights lit = Intermediate Position
: p. SHUT isolation valve opened at Step 5.4.3.b OR 5.4.3.c.3, as applicable, using local control switch on switch panel outside Sample Room, AND check block for valve SHUT.
                      - SC-955 OR F-- SC-959
: q. IF valve SC-955 OR SC-959 (as applicable) did NOT SHUT (green light on panel lit) within 15 seconds, THEN notify Unit CO.
: r. IF sample being taken off Hot Leg (i.e., only SC-955 being used)
THEN have Unit CO SHUT SC-966C.
: s. IF DI flush NOT to be performed, THEN perform following:
: 1. Ensure the following valves SHUT:
ID        Initials SC-939 SC-940 SC-941
: 2. Enter N/A for Steps 5.4.4.a - 5.4.4.p, AND GO TO Step 5.4.4.q.
Page 27 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                        EPIP 8.4.1 SAFETY RELATED EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 15 July 12, 2002 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:  Post-sampling flush to be performed only as directed by Chemistry supervision, OR N/A entered for sign-offs when NOT performed.
5.4.4  Post-Sampling Flush
: a. Ensure following valves OPEN:
ID        Initials SC-940 SC-941 DI-144 CAUTION Unit CO shall be informed prior to initiating DI flush because this evolution can affect reactivity.
NOTE:        SM approval required to open SC-946 following containment isolation if SC-966C fails to shut.
: b. Ensure following valves OPEN:
ID        Initials DI- 140 DI-145 DI-148 SC-947 SC-948
: c. IF P-166 to beused, THEN perform following:
I                       1. Ensure valve DI-142 SHUT.
: 2. Ensure valve DI-143 OPEN.
Page 28 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                       EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                          July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: 3. Turn pump switch ON AND record time:
Time:
: 4. Exit to low radiation area.
: d. IF P-166 NOT to be used, THEN perform following:
: 1. Ensure OPEN DI-142, P-166 Flush Pump Bypass.
: 2. Ensure SHUT DI-143.
: 3. Record system pressure as indicated on PI-4145:
psi
: 4. Exit to low radiation area.
: 5. IF system pressure (Step 5.4.4.d.3) is less than 80 psi, THEN contact Unit CO, AND request that DI water header pressure be maximized and the time pressure maximized be provided.
: 6. Record time pressure maximized:
Time:
: e. Time flush, as follows:
: 1. IF flushed by P-166, THEN wait approximately 2 minutes.
: 2. IF flushed by maximized DI water header pressure, THEN wait approximately 15 minutes after header pressure maximized.
: f. Return to HRSS AND measure radiation levels AND DI water pressure at Sample Vessel.
Page 29 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                             July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS
: g. Record data below AND exit to low radiation area:
: 1. Time:
: 2. Radiation Level:            mR/Hr
: 3. PI-4145 pressure indication:      -    psi
: h. Notify Chemistry supervision of radiation dose rate, AND wait for instructions on system flush.
: i. IF Chemistry OR RP supervision directs discontinuation of flush, THEN N/A Step 5.4.4.j AND GO TO Step 5.4.4.k.
: j. IF Chemistry OR RP supervision directs continuation of flush, THEN repeat Steps 5.4.4.e - 5.4.4.h AND record data in Table B (below) until Chemistry OR3 RP supervision directs discontinuation of flush:
Table B Flush #      PI-4145         Time        mR/hr psig                    After Flush 2
3 4
: k. WHEN directed by Chemistry ORl RP supervision, THEN STOP flush according to following:
: 1. OPEN valve SC-946.
: 2. SHUT following valves:
ID         Initials SC-947 SC-948
: 3. OPEN valve SC-939, using remote valve tool.
Page 30 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                        EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                           July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS
: 1. Exit to low radiation area AND wait 5 minutes.
: 1. IF flushed by P-166, THEN turn P- 166 OFF, AND record time flush STOPPED:
Time:
: 2. IF flushed by maximized DI water header pressure, THEN SHUT DI-142 AND record time flush STOPPED AND total flush time:
Time:              Total Flush Time:
: m. SHUT following valves, using remote valve tool:
ID        Initials SC-940 SC-941
: n. SHUT following valves:
ID        Initials DI-148 DI-140 DI-143 DI-145 SC-947 SC-948
: o. Notify Unit CO DI water flush completed.
: p. Disconnect quick-connect between Valve DI-148 AND the DI water manifold, using a paper towel to prevent spraying.
Page 31 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS NOTE:      The bottom fitting (Step 5.4.4.q) to be loosened is the fitting closest to the tee.
NOTE:      Disconnect the bottom fitting first and then the top fitting.
: q. Disconnect sample vessel by loosening the top AND bottom fittings using appropriate wrench (5/8", 11/16", or adjustable) AND a paper towel to prevent spraying.
: r. Ensure sample cart attached to sample vessel.
: s. Remove shielded sample vessel (carefully) from support while ensuring vessel fittings are directly above catch basin.
NOTE:      Any water remaining in fittings will dilute sample.
CAUTION Approximately 4-5 mls of liquid will drip out when the syringe needle is inserted into the bottom of the vessel.
: t. Remove liquid from top AND bottom vessel fittings with syringe (with long needle) AND EJECT liquid into shielded waste bottle.
: u. Replace Swagelok plugs on Sample Vessel (finger tight).
: v. Place large polyethylene bag over vessel for transport, AND back sample cart away from sample area.
: w. Replace Swagelok plugs on wall fittings (for Sample Vessel), using appropriate tool.
: x. IF directed by Chemistry supervision, THEN GO TO Section 5.13, restore system to normal valve lineup, AND RETURN TO Step 5.4.4.
Page 32 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                             EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS
: y. Transport vessel, remote valve tool, AND wrenches to Chemistry laboratory on sample cart.
: z. Record any unusual conditions observed OR conditions that interfered with sampling, including step number(s)
AND affected component ID in comments block, below, AND notify Chemistry supervision of unusual condition(s):
COMMENTS (Sampling) aa. Document completion of sampling on PBNP Reactor Coolant Post-Accident Sampling and Analysis Report, Attachment C, Section 3.0.
5.5  Collecting Gaseous Sample From Pressurized Sample Vessel NOTE:      A diagram of setup for collecting sample is provided on Attachment B.
5.5.1      Place shielded sample vessel in sample holder in Primary Sample Hood.
5.5.2      Obtain contact, radiation reading on sample vessel AND record reading for future reference in determining RCi content:
Dose Rate:                   /Hr NOTE:      Sample vessel fittings should be cleaned, but only when radiation levels permit. Thread compounds are NOT to be used anytime.
5.5.3      Ensure sample vessel AND shielded gas collection vessel are adequately shielded.
Pagre 33 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS NOTE:   If vacuum is still established in collection vessel, it will be lost when connecting the sample vessel in the following step.
Vacuum will be reestablished by the procedure.
5.5.4   Connect sample vessel to the shielded gas collection vessel by means of the fittings provided.
5.5.5   Connect drain tube to opposite end of sample vessel, AND ensure Valve 11 on drain tube is OPEN.
5.5.6   Ensure vacuum line is attached to gas collection vessel at valve 1 location.
5.5.7   Ensure Gas Collection Vessel valves (Attachment B), as follows:
: a. Valves 1 AND 2 OPEN.
: b. Valve 3 SHUT.
5.5.8   Evacuate Gas Collection Vessel and connecting lines.
5.5.9   SHUT valve 1 AND check stable vacuum.
5.5.10  IF vacuum unstable, THEN perform following:
: a. REPAIR leak(s).
: b. OPEN valve 1, AND repeat Steps 5.5.8 AND 5.5.9 until stable.
5.5.11  Secure vacuum AND disconnect vacuum line.
NOTE:   Other methods of pressure adjustment (Step 5.5.12) may be used, as directed by Chemistry supervision.
5.5.12  Adjust vacuum to 12-14" Hg, using valve 1.
NOTE:   Use the remote valve tool only as needed to reduce dose.
5.5.13  OPEN valves 9A AND 9B.
Page 34 of 55                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: e. Document hydrogen analysis on Attachment C, Section 3.0.
5.6.2  Radioactive Noble Gas
: a. Draw 0.5 cc sample into gas tight syringe (lor 2 cc for drill/training).
: b. LOCK syringe, then withdraw from sample vessel.
NOTE:         Dilution should be performed if contact reading on syringe is >5 mR/hour OR >10% detector spectroscopy amplifier dead time.
: c. IF syringe contact radiation reading is >5 mR/hr OR >10% detector dead time, THEN dilute as follows:
I.      Inject sample into side-arm flask prepared at Step 5.2.2.h, AND, allow 15 minutes for thermal mixing.
: 2.      Draw 1 cc of sample of dilution into syringe.
: 3.      IF contact reading is still >5 mR/hr OR >10% detector dead time, THEN perform following:
(a)   Repeat Step.5.6.2.c until reading is <5 mR/hr OR *10% detector dead time.
(b)   Record number of dilutions performed below, AND label each side-arm flask as second, third, dilution, etc.:
Dilutions performed for this analysis:
: d. IF syringe contact reading (original sample or dilution) is
                      *!<5 mR/hr OR *<10% detector dead time, THEN prepare sample (normally) for analysis, in accordance with procedure for instrument to be used.
Page 36 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS 5.5.14    OPEN valve 8B one-quarter turn.
NOTE:     Vacuum drop should be no more than 5 inches Hg/min.
5.5.15    OPEN (crack slightly) valve 8A AND control rate of degassing by throttling valve 8A.
5.5.16    Allow system to degas for 2-4 minutes.
5.5.17    Ensure that the following sample vessel valves are OPEN.
ID          Initials 9A 9B 8A 8B 5.5.18    CLOSE valve 2.
5.6  Analvzina Gaseous Sample NOTE:     Steps 5.6.1 and 5.6.2 can be done concurrently OR in opposite order.
5.6.1     Hydrogen
: a. Draw an appropriate size sample (typically Icc) using a gas tight syringe AND inject sample through injection port of instrument designated by Chemistry supervision, AND perform analysis, in accordance with CAMP procedure for designated instrument.
: b. Record percent (%) Hydrogen from instrument output in space provided on Attachment C, Table 1, Line A.
: c. Record analysis data for Lines B, C, AND D in Attachment C, Table 1.
: d. Calculate cc/Kg hydrogen in accordance with equation provided in of Attachment C, Section 1.0, AND record result in space provided on Table 1.
Page 35 of 55                       CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: e. Perform MCA analysis in accordance with CAMP procedure for instrument designated by Chemistry supervision, AND obtain MCA printout.
: f. Record analysis data for Lines A - F in Attachment C, Table 2.
: g. Determine Common Multiplier (CM) in accordance with equation provided in Attachment C, Section 1.2 AND record CM in, Table 2, Line G.
: h. Correct MCA results using values in Table 2, Lines E - F AND record corrected .tCi/cc for each Noble Gas isotope detected in spaces provided on Table 2.
: i. Document noble gas analysis on Attachment C, Section 3.0.
5.7  Collecting Liquid Sample From Sample Vessel 5.7.1      Ensure valve 2 SHUT.
5.7.2      OPEN (carefully), valve 3.
5.7.3      Allow liquid sample to drain into 50 ml beaker.
5.7.4      IF necessary to recover total liquid sample, THEN direct a slow stream of air through vent line on valve 3.
5.7.5       WHEN all sample collected, THEN SHUT following:
ID         Initials 8A 8B 9A 9B 3
Page 37 of 55                       CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.8 Analyzing Liquid Sample 5.8.1     pH and Boron Analysis
: a. pH Measurement
: 1. Transfer approximately 2-5 mls of sample (using an automatic pipettor) into an appropriate beaker for boron analysis.
: 2. Measure pH AND record pH in space provided in, Attachment C, Table 3 .
: b. Boron Analysis Perform boron analysis in accordance with applicable plant procedure; e.g. CAMP 205, AND record appropriate analysis parameters/results in Attachment C, Table 3.
5.8.2    Chloride Analysis
: a. IF PBNP I.C. OR laboratory is NOT available, THEN perform following:
: 1. Obtain a suitable aliquot of sample (as directed by Chemistry supervision) for analysis by WE Laboratory Services (LS) using WE Laboratory Services I.C.
: 2. Store sample, as directed by Chemistry supervision in laboratory vent hood until other analyses are completed.
: 3. Contact TSC Manager to arrange for transport of necessary WE Laboratory Services personnel AND equipment to PBNP to perform Chloride analysis.
: b. IF PBNP I.C. analyzer OR laboratory is available, THEN obtain a suitable aliquot of sample (as directed by Chemistry supervision) AND analyze for Chloride.
Pag~e 38 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: c. Record ppm chloride in space provided in Attachment C, Table 4,
: d. Document chloride analyses on Attachment C, Section 3.0.
5.8.3   Iodine Analysis and Gamma Scan NOTE:       More than 0.3 cc may be used for drill/training.
: a. Transfer 0.3 cc (or less, based on activity) of sample from the beaker to a 1000 ml polyethylene bottle containing 1000 ml of DI water, using 2 cc syringe or adjustable automatic pipet.
: b. IF the contact radiation reading on 1000 ml polyethylene bottle is >5 mR/hr OR >10% detector dead time, THEN prepare additional dilution, as follows:
: 1. Transfer 0.3 cc of diluted sample to another 1000 m]
polyethylene bottle containing 1000 ml DI water.
: 2. IF contact reading still >5 mR/hr OR >10% detector dead time, THEN perform following:
(a)   Repeat Steps 5.8.3.b.IAND 5.8.3.b.2 until reading is *5 mR/hr OR *10% detector dead time.
(b)   Record number of dilutions performed below, AND label each container as second, third, dilution, etc.:
Dilutions performed for this analysis:
Page 39 of 55                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS
: c. IF reading (original sample OR dilution) is *5 mR/hr ORi *10% detector dead time, THEN perform following:
: 1. Count sample in accordance with CAMP procedure for instrument designated by Chemistry supervision.
: 2. Obtain MCA printout.
: d. Record analysis/calculation data on in Attachment C, Table 5, Lines A - F.
: e. Determine Common Multiplier (CM) in accordance with equation provided in Attachment C, Section 2.3, AND record CM in Table 5, Line G.
: f. Correct MCA results using values in Table 5, Lines E - G AND record corrected pCi/cc for each isotope listed in Table 5, Section B AND C.
: g. Document analysis of iodine AND other isotopes for EPIP 10.2, as applicable on Attachment C, Section 3.0.
5.9  Submittal Of Sampling/Analyses Documents Remove (temporarily) Sections 1.0 - 5.10 AND submit to Chemistry supervision.
Page 40 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                               EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                  SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                  July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.10  Sampling/Analysis Report And Continuation Of Procedure - Chemistry Supervision 5.10.1      Review/sign/date completed procedure and Sampling and Analysis Report (Attachment C), as applicable.
5.10.2      Forward completed sections of procedure (Sections 1.0- 5.10)
AND Attachments A-C to the Rad/Chem Coordinator.
5.10.3      Direct completion of Sections 5.11- 5.16 of procedure, as appropriate.
NOTE:    Sections 5.11- 5.16 may be performed in any order, as directed by Chemistry supervision.
5.11  Labeling Samples Ensure chloride, noble gas, iodine AND gamma scan samples, including sample to be sent to Off-Site analysis laboratory are labeled with following information (as minimum):
5.11.1       Sample number 5.11.2       Name of sample 5.11.3       Date and time of sampling 5.11.4       Sample volume 5.11.5       Dilution 5.11.6       Technician initials 5.11.7       Contact radiation dose rate 5.12 Sample Storage WHEN analysis completed AND samples have been properly labeled, THEN store all samples (liquid and gas) NOT to be transported to Off-Site Laboratory in the designated high level shielded storage area located in the Auxiliary Building area outside of Gas Decay Tank Room.
Page 41 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.13 System Normal Valve Lineup NOTE:    This section is to be performed during training OR drill exercise, OR when directed by Chemistry supervision.
NOTE:    Sign-offs (below) (5.13.1/5.13.2) may be initialed after all positions verified.
5.13.1    Ensure valves are positioned as indicated in position column, as follows:
ID                            Name                            Position   Initials SC-961C    HX-14C RC Hot Leg Sample HX Outlet                      SHUT SC-964C    RC Hot Leg Sample Throttle                              SHUT SC-965C    Z-5C RC Hot Leg Sample Vessel Bypass                    SHUT SC-971     RC Hot Leg Grab Sample                                  SHUT SC-938B    RE-109 Failed Fuel Monitor Outlet                       SHUT SC-939     Z-5E High Rad Sample Vessel Inlet                       SHUT SC-940     Z-5E High Rad Sample Vessel Bypass                      SHUT SC-941     Z-5E High Rad Sample Vessel Outlet                      SHUT NOTE:     Step 5.13.2 can be omitted for training if no flushing evolutions performed. N/A in initials column.
5.13.2    Ensure DI water flush valves positioned as indicated in position column, as follows:
ID         Position       Initials DI-148          SHUT SC-946          SHUT SC-947          SHUT SC-948          SHUT DI- 140         SHUT DI-141          SHUT DI-142          SHUT DI-143          SHUT DI-145          SHUT 5.13.3    IF DI water header pressure has been maximized OR is still maximized, THEN have Unit CO return DI water header pressure to normal.
Page 42 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                        EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                           July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.13.4   IF DI flush was performed, THEN RED-LOCK P-166 switch AND DI water jumper to following, as applicable:
: a. Unit 1: 1RE-219 SG Blowdown Liquid Monitor Demineralized Water Inlet" pipe
: b. Unit 2: HX-14C RC Hot Leg Sample HX Demineralized Water Flush" pipe NOTE:   Sign-offs (below) may be initialed after all positions verified.
5.13.5  IF RE-109 is to be put in service, THEN ensure valves are positioned as indicated in position column, as follows:
NOTE:   Valves SC-955 AND SC-956C require SM approval to open following containment isolation AND SC-966C fails to shut.
ID                              Name                            Position   Initials SC-938A   RE-109 Failed Fuel Monitor Inlet                           OPEN SC-956C   HX-14C RC Hot Leg Sample HX Inlet                          OPEN SC-968    Z-5C Sample Pressure Vessel Common Outlet                  OPEN SC-969A   FI-903 Flow Indicator Purge Line To T-4 VCT Isolation      OPEN 5.13.6   OPEN valve for SC-955, RC Hot Leg Sample Isolation OR SC-959, RHR Loop Sample Isolation, as applicable, using valve switch on switch panel outside Sample Room.
5.13.7   Have Unit CO OPEN SC-966C, RC Hot Leg Sample.
5.13.8   Establish 0.2 to 0.4 gpm flow through RE-109, Post Accident Sample Line Monitor by throttling SC-938C.
5.13.9   Notify Unit CO RE-109 back In-Service.
Page 43 of 55                      CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                               EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                  SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                  July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS 5.13.10     Record any unusual conditions observed OR conditions that interfered with restoring system to normal valve lineup, including step number(s) AND affected component ID in comments block, below, AND notify Chemistry supervision of unusual condition(s):
COMMENTS (Normal Valve Lineup) 5.13.11     Sign AND date in Section 5.16 for restoring system to normal valve lineup.
NOTE:    Section 5.16 to be performed during drill OR training, OR as directed by Chemistry supervision during post-accident conditions.
5.14 Re-Installation Of Shielded Sample Vessel NOTE:       The RP survey and release (Steps 5.14.1 and 5.14.2) may be omitted for drill OR training.
5.14.1      Have RP perform radiological survey of sample vessel AND associated tools.
5.14.2      WHEN sample vessel AND tools have been released by RP, THEN perform following:
: a. Notify Unit CO that RE- 109 will be temporarily removed from service for installation of sample vessel.
: b. Transport sample vessel AND tools to affected unit HRSS.
Page 44 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS INITIALS NOTE:      Valve positions are indicated on switch panels by green AND red lights, as follows:
                     -    Green light (only) lit = SHUT
                     -    Red light (only) lit = OPEN
                     -    Both lights lit = Intermediate Position 5.14.3     SHUT SC-955 AND ensure SC-959 SHUT.
5.14.4     IF SC-955 (OR SC-959) did NOT SHUT (green light on panel lit) within 15 seconds, THEN notify Unit CO.
5.14.5     Place a waste container under sample vessel fittings to collect possible liquid when sample vessel fittings are removed.
CAUTION System pressure shall be relieved by opening valves in Step 5.14.6 before removing sample vessel fittings.
5.14.6     OPEN following valves to relieve possible pressure in system.
ID                         Name                       Initials SC-939       Rad Sample Vessel Inlet SC-940       Z-5E High Rad Sample Vessel Bypass SC-941       Z-5E.High Rad Sample Vessel Outlet 5.14.7     SHUT following:
ID          Initials SC-939 SC-940 SC-941 Page 45 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS CAUTION Paper towel shall be used to contain potential spray when performing Step 5.14.8.
5.14.8     Remove (carefully) Swaglok plugs from HRSS sample vessel inlet AND outlet lines, using care to contain potential spray AND prevent contamination.
5.14.9     Allow any liquid in line to drain into waste container.
5.14.10    Remove plugs from sample vessel, AND install sample vessel on HRSS fittings.
5.14.11   Ensure sample vessel fittings are tight.
5.14.12   Ensure following valves are SHUT:
ID                        Name                        Initials SC-939     Z-5E High Rad Sample Vessel Inlet SC-940     Z-5E High Rad Sample Vessel Bypass SC-941     Z-5E High Rad Sample Vessel Outlet 8A      Sample Vessel Valve 8B      Sample Vessel Valve 9A      Sample Vessel Valve 9B      Sample Vessel Valve 5.14.13   OPEN SC-955.
5.14.14   IF SC-955 did NOT OPEN (red light on panel lit) within 15 seconds, THEN notify Unit CO.
5.14.15   Notify Unit CO that RE-109 back In-Service.
5.14.16   Dispose of any liquid collected in waste container, as directed by Chemistry supervision.
Page 46 of 55                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                              EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                 SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                 July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.14.17    Return sample cart AND tools to original storage location AND configuration, as directed by Chemistry supervision.
5.14.18    Record any unusual conditions observed OR conditions that interfered with re-installation of sample vessel, including step number(s) AND affected component ID in comments block, below, AND notify Chemistry supervision of unusual condition(s):
COMMENTS (Sample Vessel Installation) 5.14.19     Sign AND date in Section 5.16 for sample vessel installation.
5.15 Preparation/Transfer Of Sample(S) To Off-Site Laboratory NOTE:        The Kewaunee Nuclear Plant, Chemistry laboratory is the Off-Site Laboratory that will perform analyses of the PBNP Post-Accident sample(s). Refer to Post-accident counting agreement with Wisconsin Public Service, Kewaunee Nuclear Plant.
NOTE:       Kewaunee Nuclear Plant does NOT utilize the gas serum vial and 1 cc test tube geometries. Therefore, "normal" sample has to be diluted AND placed in one liter poly bottle for transport to Kewaunee Nuclear Plant.
5.15.1     IF 1-liter sample used for Iodine analysis ANDD Gamma scan is to be transferred to Kewaunee Nuclear Plant, THEN enter N/A for Step 5.15.2 AND GO TO Step 5.15.3.
5.15.2     IF separate dilution to be prepared for Kewaunee Nuclear Plant, THEN prepare dilution, as directed by Chemistry supervision, AND label in accordance with Section 5.11.
5.15.3     Contact Radioactive Material Shipping personnel to ensure completion of any required shipping papers.
Page 47 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                             EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT INITIALS 5.15.4     Complete documents, AND submit documents, sample, AND copies of all analysis data obtained for sample being shipped to Kewaunee to Radioactive Material Shipping personnel for transport to Kewaunee Nuclear Plant.
5.15.5      Sign AND date in Section 5.16 for preparation of sample for off-site analysis.
5.16 Post-Analysis Documentation/Submittal 5.16.1      Sign/date for task performed/completed below AND submit to Chemistry supervision:
Post-Sampling Normal Valve Lineup:
Performer:
Printed Name                       Signature            Date Sampling Vessel Installation:
Performer:
Printed Name                       Signature            Date Preparation of Sample(s) For Off-Site Analysis:
Performer:
Signature            Date Printed Name Approval:
Supervisor:
Signature            Date Printed Name 5.16.2     Forward Sections 5.11 - 5.16 to Rad/Chem Coordinator for re-attachment to Sections 1.0- 5.10 (submitted to Chemistry supervision at Step 5.9).
Page 48 of 55                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                               July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT

==6.0  REFERENCES==

6.1  Calculation 98-0058, Post-LOCA Reactor Coolant Sampling System Dose Rates, 08/10/98 6.2  Calculation 98-0018, Evaluation of WEPCO PBNP Post Accident Sampling System 6.3  Calculation 98-0175, Post-LOCA Post-Accident Sampling System 6.4  CAMP 205, Boron-Titration-Mannitol\ph Method 6.5  NPM 94-0030, Compilation of WEPCO Commitments Associated with NUREG 0737, clarification of TMI Action Plan Requirements, 0 1/12/94.
7.0  BASES B-1   10 CFR 50.47, Code of Federal Regulations, Emergency Plans B-2  NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Rev. 1, November 1980 B-3  NUREG-0737, Clarification of TMI Action Plan Requirements, November 1980 Page 49 of 55                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                         EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES            SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF            July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT ATTACHMENT A PRIMARY COOLANT HIGH-LEVEL SAMPLING FLOW DIAGRAM Page 50 of 55                CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                                    EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                       SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                                       July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT ATTACHMENT B SETUP FOR TRANSFER OF SAMPLE FROM SAMPLE VESSEL Vacuum Line Side View Vessel Sample k<    Vessel 4"
End View 12 x 20" Lead Wall Lead Pig tor Samoles "WilH                                Stirrer    [      .
Gas View            Hollow for pH and Boron Collection                                 Brick Vessel                                                Poly S~Sample Vessel 9B 9A             8B  8A                                       j4_Lead B             20 Bricks Staggered for Stability Page 51 of 55                                            CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                           EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                              SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                              July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT ATTACHMENT C PBNP REACTOR COOLANT POST-ACCIDENT SAMPLING AND ANALYSIS REPORT Page 1 of 4 1.0    ANALYSIS OF GASEOUS SAMPLE 1.1      Hydrogen Analysis A-D):
Hydrogen @ STP (using following
() 280        (C)    273with Table 1, Values equation cc/Kg H2 @*STP -(A)100 x 28        (B) x   (C x 27 1013   (D) x 1000 1.01E 3  (A) x(C)
(B)(D)
Table 1: Hydrogen A     Percent (% ) hydrogen from instrument output B     Volume of sample bomb (ml)
C     Atmospheric pressure (mbar)
                       -)    Ihnkrntnrv temn ('C  4- 273'1
:c/Ag nyarogen in coomint I
1.2       Radioactive Noble Gases MCA Results (corrected, using following equation with Table 2, Values E-F):
Common Multiplier (CM) =              280       (E) x (E)
(G)
If gas dilution NOT                 (F) -1 required then the quantity          (E)
Table 2: Radioactive Noble Gases A. Analysis/Calculation Data                                              oble Gases A Decay time (min)                                   Isotope          RCi/cc              Isotope        &#xfd;tCi/cc B Count Time (sec)                                   Xe-133                     t'.        K-7      ____Xe-138 C Detector                                           Kr-85m Kr-88                          I;}   Ar-41 D Geometry Xe-133m                           .. N Kr-85 E Vol Sample Vessel (ml)                                                            I* Xe-131m F Vol sidearm flask (ml)                             Xe-135 G Vol of sample removed with gas syringe (ml)
H *CM Page 52 of 55                              CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                             July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT ATTACHMENT C PBNP REACTOR COOLANT POST-ACCIDENT SAMPLING AND ANALYSIS REPORT Page 2 of 4 2.0   ANALYSIS OF LIOUID SAMPLE 2.1  pH and Boron pH and Boron (with Boron calculated, using following equation with Table 3, Values A-C):
           *ppmBoron = (B) x (C) x 10810 (A)
Table 3: pH and Boron A      Sample volume (ml)
B      Normality NaOH C     {Volume NaOH used (ml)
D     Sample pH E       ppm Boron 2.2  Chloride Table 4: Chloride Chloride concentration                     ppm[
Page 53 of 55                    CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                      EPIP 8.4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                         SAFETY RELATED Revision 15 POST-ACCIDENT SAMPLING AND ANALYSIS OF                                         July 12, 2002 POTENTIALLY HIGH ACTIVITY REACTOR COOLANT ATTACHMENT C PBNP REACTOR COOLANT                POST-ACCIDENT        SAMPLING AND ANALYSIS REPORT Page 3 of 4 2.3     Iodine Analysis MCA Results (corrected, using following equation and Table 5, Values E-F):
1000
              *CM =             xF Vs Vs = Volume of sample (first dilution)
F = Any additional dilution factors (2 or more dilutions)
NOTE:        Isotopes in Table 5, Column C, are NOT required. However, if time permits, analysis results for as many as possible should be provided to aid in completing EPIP 10.2, "Core Damage Estimation."
NOTE:        Multiply the corrected MCA iodine results by the listed multiplication factor to obtain the final iodine corrected result.
Table 5: Iodine and Other Isotopes for EPIP 10.2 A. Analysis/Calculation Data                     B. Iodine                  C. Other (for EPIP 10.2)
A Decay time (min)                           Isotope  Mult. Fact. Final          Isotope        1 iCi/cc Corrected
_.tCi/cc B  Count Time (sec)                           1-130     x 4.5 =                     Rb-88 C  Detector                                   1-131     x 4.5 =                    Cs-134 D Geometry                                    1-132     x 4.5 =                    Cs-137 E  Vs: Vol of Sample (1st dil),               1-133     x 4.5 =                    Te-132 ml F lAdditional dilutions (>l)                 1-134     x 4.5 =                    Ba-140 G
* Common Multiplier                         1-135     x 4.5 =                    La-140 Total                                La-142 Pagre 54 of 55                            CONTINUOUS USE

EPIP 8.4.1 POINT BEACH NUCLEAR PLANT                                    SAFETY RELATED EMERGENCY PLAN IMPLEMENTING PROCEDURES                       Revision 15 July 12, 2002 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH ACTIVITY REACTOR COOLANT ATTACHMENT C PBNP REACTOR COOLANT POST-ACCIDENT SAMPLING AND ANALYSIS REPORT Page 4 of 4 3.0   PERFORMANCE (SAMPLING and ANALYSES)
SAMPLING:
Performer:                                                                Date Printed Name                  Signature Verifier:                                              Signature          Date Printed Name ANALYSES (including calculations, as applicable)
Hydrogen:                                                                 Date Performer Printed Name        Performer Signature Noble Gas:                                                                Date Performer Printed Name        Performer Signature pH/Boron:                                                                 Date Performer Printed Name        Performer Signature Chloride:                                                                 Date Performer Printed Name        Performer Signature Iodine/Other:                                                            Date Performer Printed Name        Performer Signature 4.0   ROUTING AND APPROVAL Chemistry Leader                                         Signature        Date Printed Name Rad/Chem Coordinator:                                    Signature        Date Printed Name TSC Manager:                                             Signature        Date Printed Name Page 55 of 55                CONTINUOUS USE

EPIP 8.4.2 POST-ACCIDENT SAMPLING OF CONTAINMENT ATMOSPHERE DOCUMENT TYPE:          Technical CLASSIFICATION:        Safety Related REVISION:     10 EFFECTIVE DATE: July 12, 2002 REVIEWER:      Qualified Reviewer APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                    Date         Time List pages used for Partial Performance              Controlling-Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                         EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                            SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                                                             July 12, 2002 ATMOSPHERE TABLE OF CONTENTS SECTION    TITLE                                                                                                                               PAGE 1.0        P U R P OSE ...................................................................................................................... 3 2.0        PR ERE Q U ISITES .....................................................................................................               3 3.0        PRECAUTIONS AND LIMITATIONS ...................................................................                                       3 4.0        INITIAL CONDITIONS ............................................................................................                       4 5.0        PR O C ED U RE ........................................................................................................               4 5.1  Prelim inary Evaluation .............................................................................................                 4 5.2  Equipm ent ...................................................................................................................... 5 5.3  Laboratory Setup And Preparation Of Sampling Equipment ....................................                                           6 5.4  Approvals For Implementing Sampling And Analyses ............................................                                         8 5.5  Containment Atmosphere Sampling Using Post-Accident Sampling System (RE-21 1/RE-212 Bypass Loop) ..................................................................                                8 5.6  Containment Atmosphere Sample Analysis ...............................................................                                 13 5 .7 C alculation s ................................................................................................................... 17 5.8  Procedure Submittal and Sample Storage ................................................................                                19 5.9  Performer Documentation ..........................................................................................                     19 5.10 A nalysis Report ..............................................................................................................       20 6.0        R E FE R EN CE S ...............................................................................................................      20 7 .0       B A SES ........................................................................................................................... 20 ATTACHMENT A        PASS VALVE LINEUP FOR CONTAINMENT ATMOSPHERE GRAB SAMPLING .......................................................................................                        21 ATTACHMENT B        CONTAINMENT ATMOSPHERE POST ACCIDENT SAMPLING ANALYSIS REPORT ...................................................................................                          22 Page 2 of 23                                                       CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                             EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                 SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                                  July 12, 2002 ATMOSPHERE Reason for performance:   13 Drill     E3 Training     LI Fuel Failure Unit Being Sampled:       E3 Unit 1    13 Unit 2 1.0    PURPOSE This procedure provides instructions for collecting, handling, and analyzing a containment atmosphere sample with potentially high radioactivity due to fuel failure and/or loss of reactor coolant system (RCS) integrity.
This procedure may be used for training and drills or exercises. Chemistry Supervision may exclude any section or step where performance may adversely affect operation of unit.
2.0    PREREQUISITES 2.1     Responsibilities 2.1.1       The Shift Manager (SM) (Operations Support Center Coordinator if TSC is activated) is responsible for the management of the containment atmosphere sample collection and analysis.
2.1.2       Radiation Protection Supervisor (Rad/Chem Coordinator if TSC is activated) is responsible for radiological monitoring controls.
2.1.3       Chemistry Supervision (Chemistry Leader if OSC is activated) is responsible for sample collection and analysis.
2.2     Equipment 2.2.1       Emergency Preparedness Radiation Protection Equipment maintained in OSC.
2.2.2       Refer to Step 5.2 for Chemistry equipment.
3.0    PRECAUTIONS AND LIMITATIONS 3.1     During performance of radiological sampling activities, personnel may be subjected to radiological hazards including high radiation, contamination, and airborne radioactivity.
3.2     Personnel shall wear prescribed protective clothing, dosimetry devices, and other protective equipment, as required by the applicable Radiation Work Permit (RWP) or Re-entry Permit, when performing radiological sampling.
3.3     Improper handling of radioactive material can result in personnel contamination, radioactive material uptake, and unplanned personnel exposure.
3.4     SM approval is required for the manipulation of valves.
Page 3 of 23                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                          EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                              July 12, 2002 ATMOSPHERE 3.5   Containment atmosphere samples shall be taken and analyzed within three (3) hours from the time the decision is made to dispatch a sample team.
4.0   INITIAL CONDITIONS 4.1   Possible fuel failure 4.2   Loss of RCS integrity 5.0   PROCEDURE INITIALS 5.1   Preliminary Evaluation NOTE:       This section shall be completed prior to entering facade to collect a Containment atmosphere sample under emergency conditions.
5.1.1       Indications of Possible Fuel Damage NOTE:       Fuel failure or loss of RCS integrity may be the cause if any of the conditions in Steps 5.1.1.a 5.1.1.e exist.
Circle step number(s) and initial to indicate existing condition(s), and enter N/A for conditions that do NOT exist:
: a. Letdown Valve Gallery Monitor, RE- 116, unusually high or offscale high
: b. Containment Air Particulate Monitor, 1(2) RE-2 11 and Containment Noble Gas Monitor, 1(2) RE-212, unusually high or offscale high. (Readings may be invalid if containment isolation has occurred.)
: c. Containment Low-Range Monitor, 1(2) RE-102, and Seal Table Monitor, 1(2) RE- 107, unusually high or offscale high
: d. Post Accident Sample Line Monitor, 1(2) RE-109, unusually high or offscale high. (Readings may be invalid if containment isolation has occurred.)
: e. Auxiliary Building Vent Stack Monitor, RE-214, indicating significant increase due to auxiliary building airborne activity from letdown and charging pump areas Page 4 of 23                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                      EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                          July 12, 2002 ATMOSPHERE INITIALS NOTE:     Equipment collection and laboratory setup (Sections 5.2 and 5.3) may be performed before or while performing Step 5.1.2.
5.1.2     Evaluation of Radiological Hazards in Access Areas Required for Sampling
: a. WHEN Radiation Protection (RP) has completed airborne, radioactive contamination, and radiation surveys of facade and all areas through which chemistry personnel must pass, THEN obtain following:
: 1. Radiation Work Permit (RWP) or Reentry Permit, as applicable
: 2. Radiation levels indicated by following monitors:
(a)   RE-211B, Background Monitor (b)   RE-103, Chem Lab Low Range Monitor
: 3. Radiation levels in personnel accesses to facade
: b. Estimate (using RWP, data from Step 5.1.2.a. I through Step 5.1.2.a.3, and Calculation 97-0011, as applicable) potential personnel (whole body and extremity) dose based on dose rates (area/sample) vs. known or estimated times for performing following:
: 1. Proceeding to facade
: 2. Obtaining sample (including evacuation/wait time)
: 3. Transporting sample to laboratory
: 4. Performing analysis 5.2  Equipment 5.2.1     Sampling Equipment List
: a. Flashlight with new or spare batteries
: b. Lead syringe case (lead brick hollowed out to contain syringes and provide shielding with hinged and latchable, lead cover)
Page 5 of 23                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                        EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                            July 12, 2002 ATMOSPHERE INITIALS
: c. Radiation dose rate survey instrument
: d. Two, 2 cc gas-tight (pressure-lock) syringes and spare needle
: e. Two-way radio with spare battery 5.2.2      Analysis Equipment and Reagents List
: a. Gas Chromatograph (GC) with adequate supply of carrier gas (Argon), and integrator, as designated by the Chemistry Leader
: b. Gas sample vessel, glass (sacrificial, for equilibrating sample) and lead shielding for sample vessel (in case sample hood inoperable)
: c. Marker or labels for marking/labeling sample dilutions
: d. Multichannel Analyzer (MCA), as designated by the Chemistry Leader
: e. Poly bottle, 1-liter, one (or more if additional dilutions anticipated) with cap, and gas serum vial, one (or more if additional dilutions anticipated) with septum NOTE:      Silver zeolite is stocked in the storeroom.
: f. Silver zeolite (AgZ) reagent (for iodine analysis)
: g. Syringe 1 cc, gas-tight (pressure-lock), one or more (if additional dilution probable)
: h. Test tube (for iodine analysis) with cap or stopper 5.3  Laboratory Setup And Preparation Of Sampling Equipment 5.3.1      Consult with the Chemistry Leader to determine following:
: a. Which GC (and associated integrator) to be used for Containment atmosphere Hydrogen analysis
: b. Which MCA to be used for Iodine and Noble Gas Analyses Page 6 of 23                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                             July 12, 2002 ATMOSPHERE INITIALS 5.3.2       Ensure GC and integrator selected for use by the Chemistry Leader are operating and calibration current (according to applicable procedures for GC and integrator).
5.3.3       Ensure MCA selected for use by the Chemistry Leader is operating and calibration current (according to applicable procedures for MCA).
Ensure spare syringe needle and needles on the two 5.3.4 2 cc gas-tight syringes are not plugged.
5.3.5       Load 1 cc of AgZ into one of the two 2 cc gas-tight syringes.
CAUTION Close syringe case carefully to avoid breaking sample syringes.
5.3.6       Place the two syringes and spare needle in lead syringe case and close.
Ensure cap is correctly seated on 1-liter bottle, tightened, and 5.3.7 sealed.
5.3.8       Place following near work area for easy accessibility:
: a. 1-liter poly bottle (Step 5.3.7)
: b. gas serum vial
: c. 1 cc gas-tight syringe (one or more)
: d. test tube with cap or stopper 5.3.9       Place lead brick barricade toward rear of hood to shield sacrificial gas sample vessel (with sample) in the event hood ventilation is lost.
5.3.10      Obtain a two-way radio AND perform a radio check with Control Room (CR) and Operation Support Center (OSC).
Page 7 of 23                            CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                             July 12, 2002 ATMOSPHERE INITIALS INITIALS 5.4    Approvals For Implementing Sampling And Analyses Obtain verbal approval to implement sampling and analysis from:
5.4.1      Shift Manager (SM) (Operations Support Center Coordinator if TSC is activated) 5.4.2      Radiation Protection Supervisor (Rad/Chem Coordinator if TSC is activated)
CAUTION Sampling shall not begin until preliminary evaluation has been completed and all approvals for implementation have been received.
NOTE:      Section 5.5 to be accomplished under direction of the Chemistry Supervision.
NOTE:      For consistency with PBNP Technical Procedures regarding valve positions, the word SHUT is used.
5.5    Containment Atmosphere Sampling Using Post-Accident Sampling System (RE-21 1/RE-212 Bypass Loop) 5.5.1      Sampling System Operational Verification, Valve Lineup, and Purge
: a. Have Control Room perform following:
: 1. Ensure instrument air available for operating containment isolation/sample valves and valves inside containment.
: 2. Ensure following pumps secured:
(a)   P-707-A (b)   P-707-B Page 8 of 23                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                   EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                      SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                       July 12, 2002 ATMOSPHERE INITIALS
: 3. Ensure following AOV valves SHUT:
(a)    RM-3200A (b)    RM-3200B (c)    RM-3200C NOTE:      SM approval is required prior to resetting Containment isolation signal.
: 4. Reset Safety Injection (SI) signal and Containment Isolation (CI) signal (if necessary).
: 5. Switch Mode Selector Switch on ASIP panel to SEPTUM position.
NOTE:       SM approval is required prior to opening any Containment isolation valve.
: 6. OPEN AOV containment isolation valve RM-3200A.
: b. Proceed to door 182 in Potable Water Room to sample Unit I Containment atmosphere OR to door 183 in Non-nuclear Room to sample Unit 2 Containment atmosphere.
NOTE:      Station a person at the facade door to open the door upon exit as there are no door knobs from the faqade side. Alternately, block open the door to prevent closure if conditions permit.
Determine correct course during pre-job brief.
: c. Enter facade outside 1(2) RE-211/1(2) RE-212 cubicle.
: d. OPEN nitrogen supply valves on two nitrogen bottles, AND ensure respective nitrogen header valves OPEN.
: e. OPEN valve RM-3200LL.
: f. Ensure pressure at nitrogen regulator is 80 to 90 psig.
Page 9 of 23                            CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                   EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                      SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                       July 12, 2002 ATMOSPHERE INITIALS
: g. Proceed to grab sample panel, AND activate eductor by ensuring the following valve positions:
: 1. RM-3200JJ, Sample Septum Inlet Series Isolation, OPEN
: 2. RM-3200M, Sample Septum, SAMPLE
: 3. RM-3200Y, Nitrogen Supply To PASS, OPEN
: h. Record pressure indicated on PI-3410 (should indicate negative pressure).
Indicated pressure:              psig or in. Hg (circle one as applicable)
: i. Exit Facade.
NOTE:      SM approval is required prior to opening any Containment isolation valve.
: j. Have Control Room OPEN following AOV Containment Isolation valves to initiate purge.
: 1. RM-3200B
: 2. RM-3200C
: k. WHEN sampling system has purged for >_10 minutes, THEN return to Facade with two, 2 cc gas-tight syringes (one containing 1 cc of AgZ) in lead syringe case.
: 1. Record pressure indicated on PI-3410 (pressure should be greater than pressure recorded at Step 5.5.1 .h).
Indicated pressure:              psig or in. Hg (circle one as applicable)
Page 10 of 23                            CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                      EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                          July 12, 2002 ATMOSPHERE INITIALS 5.5.2 Sample Collection CAUTION Syringes shall not be purged while obtaining samples.
Purging syringe that contains AgZ will result in AgZ retaining iodine from each withdrawal.
: a. Obtain first sample, as follows:
NOTE:       Syringe should be inserted until syringe cylinder touches septum guide.
: 1. Collect 1 cc sample, SHUT syringe lock valve, AND record time.
Sample Time:       _      (first sample)
: 2. Remove syringe from septum and place in syringe case.
: b. Repeat Step 5.5.2.a.1 and 5.5.2.a.2 for second sample, AND record sample time.
Sample Time:              (second sample)
CAUTION Close lead syringe case carefully to avoid breaking sample syringes.
: c. Close lead syringe case and latch.
: d. Exit Facade.
Page I11 of 23                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                   EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                      SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                       July 12, 2002 ATMOSPHERE INITIALS 5.5.3   Sample Line Purge
: a. Notify Control Room that sampling completed, AND have Control Room perform following:
: 1. SHUT RM-3200A (RE-21 l/RE-212 Monitor Return)
AND allow sample inlet to back flush for at least three minutes.
CAUTION The time period that containment isolation valve RM-3200a and containment isolation valve RM-3200c are both shut with nitrogen pressure present in system shall be minimized.
: 2. SHUT RM-3200C (RE-21 l/RE-212 Monitor Supply).
NOTE:        SM approval is required prior to opening any Containment isolation valve.
: 3. OPEN RM-3200A AND allow forward flush of sample outlet for at least three minutes.
: 4. SHUT RM-3200A.
: 5. SHUT RM-3200B.
: b. Return to Facade, AND SHUT following:
: 1. RM-3200LL
: 2. Supply valves on nitrogen cylinders
: c. Position valve RM-3200Y to SHUT.
: d. Deliver samples to laboratory.
Page 12 of 23                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                     EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                        SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                         July 12, 2002 ATMOSPHERE INITIALS 5.5.4     Record any unusual conditions observed or conditions that interfered with sampling, including step number(s) and affected component ID in Comments block, below.
COMMENTS 5.5.5    Sign and date EPIP 8.4.2 under Sampling, Section 5.9.
5.6  Containment Atmosphere Sample Analysis 5.6.1    Volume Adjustments
: a. If sample hood ventilation is operable, enter N/A for Step 5.6.1.b, and GO TO Step 5.6.1.c.
: b. IF sample hood ventilation is inoperable, THEN perform following:
: 1. Ensure sacrificial glass sample vessel is at atmospheric pressure.
: 2. Insert syringe needle through rubber septum of glass sample vessel and place behind brick barricade.
: 3. Unlock syringe locking device and allow syringe and glass sample vessel to equilibrate for approximately 30 seconds, then re-lock syringe.
: 4. Withdraw syringe and store in lead syringe case.
: 5. Repeat Steps 5.6.l.b.1 through 5.6.L.b.4 for remaining syringe.
Page 13 of 23                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                      EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                          July 12, 2002 ATMOSPHERE INITIALS
: c. IF sample hood ventilation is operable, THEN perform following:
: 1. Place syringe deep inside hood and unlock syringe locking device.
: 2. Allow 30 seconds for equilibration, then re-lock syringe and store in lead syringe case.
: 3. Repeat Steps 5.6.l .c. l and 5.6. l.c.2 for remaining syringe.
5.6.2   Hydrogen Analysis Perform hydrogen analysis on 1 cc of gas sample in syringe NOT containing AgZ, in accordance with procedures for Gas Chromatograph and Integrator prepared for analysis in Section 5.3.
NOTE:   Noble gas sample, subsequent dilution(s), and iodine sample are to be labeled with sample number, sample name, date/time of sample, sample volume, and dilution(s).
5.6.3   Noble Gas Initial Dilution and Equilibration
: a. Penetrate capped, 1-liter poly bottle with needle of syringe containing 1 cc AgZ and 1 cc Containment Atmosphere sample.
: b. Eject gaseous contents of syringe (1 cc sample) from syringe into the 1-liter poly bottle using care to retain all of the AgZ in syringe.
: c. Purge syringe air space once or twice while needle is inserted in poly bottle to recover all noble gases.
: d. Remove syringe and store in lead syringe case.
: e. Tape over syringe needle hole in poly bottle.
: f. Allow a minimum of 15 minutes for gas to reach equilibrium.
Page 14 of 23                             CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                    EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                       SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                        July 12, 2002 ATMOSPHERE INITIALS NOTE:  Iodide analysis (Section 5.6.4) may be performed while Noble Gas sample is reaching equilibrium (Step 5.6.3.f).
5.6.4   Iodine Analysis
: a. Hold syringe containing AgZ deep inside hood, unscrew syringe top, and remove internal plunger.
: b. Pour the AgZ into a counting test tube and cap.
: c. IF the AgZ/iodine sample is less than 1 mR/hr contact, THEN perform the following:
: 1. Count sample directly on the MCA using test tube geometry.
: 2. Enter results in Attachment B, Section 3.0, Radioactive Iodine Analysis.
: 3. N/A Step 5.6.4.d.
: 4. N/A Step 5.7.1.
: d. IF the iodine activity is too high to count directly
(&#x17d;1 mR/hr contact),
THEN perform the following:
: 1. Determine radiation level in R/hr at one foot.
: 2. Place sample in proper geometry orientation (attenuating sample, as necessary) in accordance with CAMP procedure for MCA prepared for analysis in Section 5.3.
: 3. Count and determine percent isotopic composition in accordance with CAMP procedure for MCA prepared for analysis in Section 5.3.
: 4. Complete data evaluation in Section 5.7.1.
Page 15 of 23                        CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                     EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                        SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                         July 12, 2002 ATMOSPHERE INITIALS 5.6.5 Noble Gas Analysis
: a. Withdraw a 1 cc gas sample from poly bottle prepared in Section 5.6.3.
: b. If contact reading on syringe is less than 5 mR/hr, enter N/A for Steps 5.6.5.c, and GO TO Step 5.6.5.d.
NOTE:      Dilutions (Step 5.6.5.c) NOT required for drills or training.
: c. IF contact reading on syringe is greater than 5 mR/hr, THEN perform following:
: 1. Prepare a dilution of sample in syringe in accordance with Section 5.6.3.
: 2. Obtain new syringe OR ensure syringe is thoroughly purged, then withdraw 1 cc gas sample from second dilution.
: 3. Measure dose rate on syringe.
: 4. IF contact reading on syringe is still greater than 10 mR/hr, THEN repeat Steps 5.6.5.c.1 through 5.6.5.c.3 until dose rate on syringe is less than 5 mR/hr.
: 5. Record number of dilutions.
Number of dilutions:
Page 16 of 23                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                             July 12, 2002 ATMOSPHERE INITIALS NOTE:       Spectroscopy amplifier dead time must be less than 10%.
NOTE:       Ensure appropriate amount of air has been evacuated from gas serum vial prior to injecting sample.
: d. IF contact reading on syringe is less than 5 mRPhr, THEN inject sample into a gas serum vial and count in accordance with CAMP procedure for instrument prepared in Section 5.3.
: e. Sign and date EPIP 8.4.2 under Analyses, Section 5.9.
5.7  Calculations 5.7.1      Iodine Calculations
: a. Determine Total Gamma Energy/Disintegration (Er) using Table 1 (following).
Table 1 (1)(2)                        (1) x (2)
Total y         Fractional %       Weighted 72 Isotope     Energy/Dis         Composition           Energy (In Fraction Form) 1-130           2.130 1-131          0.380 1-132          2.260 1-133          0.608 1-134          2.600 1-135          1.560 Total Weighted 72                 (Ez.)
Energy:
Page 17 of 23                           CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                      EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                          July 12, 2002 ATMOSPHERE INITIALS INITIALS
: b. Calculate total iodine activity using following equation:
C(cl):"R/hr@lft.
6Er
: c. Calculate each individual iodine isotopic concentration
(,u Ci/cc), using Table 2 (following).
                      'UCi/cc I(j) = C(ci) x 1 x 10+6 x (Fractional % Composition)
Table 2 (1)           (2)             (3)       (1) x (2) x (3)
Isotope           C_1          lx 106      Fractional %      Isotopic (From Step                    Composition    Concentration 5.7.1.b) 1-130 1-131 1-132 1-133 1-134 1-135
: d. Enter isotopic iodine data in appropriate location of Attachment B, Section 3.0, Radioactive Iodine Analysis.
5.7.2  Pressure and Temperature Correction
: a. Obtain Containment pressure (psig) and temperature ('F) from Control Room supervision.
: b. Obtain atmospheric pressure (mbar) and temperature ('F) from Chemistry laboratory barometer.
: c. Perform pressure and temperature correction, using calculation from Attachment B.
5.7.3  Sign and date EPIP 8.4.2 under Calculations, Section 5.9.
Page IS of 23                          CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                         EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                             July 12, 2002 ATMOSPHERE INITIALS 5.8     Procedure Submittal and Sample Storage NOTE:     Steps 5.8.1 and 5.8.2 may be performed in any order.
5.8.1     Submit completed sections of procedure to the Chemistry Leader.
5.8.2     Store samples (AgZ and gases) in designated high level shielded storage area located in Auxiliary Building outside of Gas Decay Tank Room.
5.9     Performer Documentation Sampling Performer:
Printed Name                             Signature             Date Hydrogen Analysis Performer:
Printed Name                             Signature             Date Iodine Analysis and Calculations Performer:
Printed Name                             Signature             Date Noble Gas Analysis and Calculations Performer:
Printed Name                             Signature             Date Supervisor:
Printed Name                             Signature              Date Page 19 of 23                         CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                     EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                        SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                         July 12, 2002 ATMOSPHERE INITIALS 5.10 Analysis Report 5.10.1       Complete Attachment B, Containment Atmosphere Post-Accident Sampling Analysis Report.
5.10.2       Forward completed procedure (including completed Attachment B) to the Rad/Chem Coordinator.

==6.0   REFERENCES==

6.1  Calculation 97-0011, Radiation Conditions at the RC-211/212 HUT during PASS sampling, 3/10/97 6.2  NPM 94-0030, Compilation of WEPCO commitments associated with NUREG-0737, Clarification of TMI Action Plan Requirements, 1/12/94 6.3   CAMP 401, Radioactive Standard and Sample Placement for Multichannel Analyzer Calibration and Quantification 6.4   SE 97-96, Unit 2 Post-Accident Sample System Upgrades (MR-97-057/WO9700312) 6.5   SE 97-145, Unit 1 Post-Accident Sample System Upgrades (MR-97-056/WO9706481) 7.0   BASES B-1   10 CFR 50.47, Code of Federal Regulations, Emergency Plans B-2   NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Rev. 1, November 1980 B-3   NUREG-0737, Clarification of TMI Action Plan Requirements, November 1980 Page 20 of 23                     CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                              EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                 SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                  July 12, 2002 ATMOSPHERE ATTACHMENT A PASS VALVE LINEUP FOR CONTAINMENT ATMOSPHERE GRAB SAMPLING (Reference Only) 32000 FfT 3401 Pagre 21 of 23               CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                             EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                                                 July 12, 2002 ATMOSPHERE ATTACHMENT B CONTAINMENT ATMOSPHERE POST ACCIDENT SAMPLING ANALYSIS REPORT Page 1 of 2 1.0      HYDROGEN ANALYSIS Percent (% ) hydrogen from instrument output (Section 5.6.2):
Table 1: Hydrogen Percent (%) HYDROGEN (from instrument output, Section 5.6.2)                               %      I 2.0      RADIOACTIVE NOBLE GAS ANALYSIS Noble Gas @ STP, corrected, using data in Part A of Table 2 and calculations at 2.1 and 2.2, below.
Table 2: Radioactive Noble Gases A.                                                                  B.
Analysis/Calculation Data                                                 NOBLE GASES Decay time (min)                                          Isotope             i.Ci/cc                Isotope           tuCi/cc Count Time (sec)                                          Xe-133      _            _                  Kr-87 Detector                                                  Kr-85m                                   Xe-135m Geometry                                                   Kr-88                                      Ar-41
 'Number of Dilutions (D)                                Xe-133m                                      Kr-85
* Common Multiplier (CM)          _____                 Xe-135                                   Xe-131m Xe-138      _______                  _______         _______
2.1     Common Multiplier*:
1075
                    *CM   = (D)I x 17 x (Pressure- Temperature Correction) 1.0
                  '  See Step 5.6.5.c. One or more dilutions may have been performed.
2.2     Pressure-Temperature Correction:
(Psp + 1 4 .7 )(TL + 459)
PL (Tc + 459)
Where: Psp = Pressure of sample, psig from EPIP 8.4.2, Step 5.5.1.1 Tc   =  Temperature (0F) in Containment PL    = Pressure (psia) in Laboratory, where:
P (mbar)
PL =14.7 x P(br 1013(mbar)
TL     = Temperature (&deg;F) in Laboratory Page 22 of 23                                    CONTINUOUS USE

POINT BEACH NUCLEAR PLANT                                                        EPIP 8.4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                           SAFETY RELATED Revision 10 POST-ACCIDENT SAMPLING OF CONTAINMENT                                            July 12, 2002 ATMOSPHERE ATTACHMENT B CONTAINMENT ATMOSPHERE POST ACCIDENT SAMPLING ANALYSIS REPORT Page 2 of 2 3.0      RADIOACTIVE IODINE ANALYSIS Results of MCA Iodines @ STP, corrected, using data in Part A of Table 3 and calculation at 2.2, above.
NOTE:        Isotopes in Part B.2 of Table 3 are not required. However, if time permits, analysis results for as many as possible should be provided to aid in completing EPIP 10.2, "Core Damage Estimation."
Table 3: Iodines and           Nuclides For Core Damage Estimation (EPIP 10.2)
A.                                                              B.
Analysis Parameters                               B.1: IODINES                   B.2 OTHER (for EPIP 10.2)
Decay time (min)                                        Isotope          jtCi/cc               Isotope        gCi/cc Count Time (sec)                                          1-130                                 Rb-88 Detector                                                  1-131                                Cs-134 Geometry                                                  1-132                                Cs-137
* Press/Temn Correction                                   1-133                                Te-132 1-134                                Ba-140 1-135                                 La-140 Total                                 La-142 4.0       ROUTING AND APPROVAL NOTE:         Documentation of sampling, analyses, and calculations is provided in Section 5.6.3.
Chemistry Leader:
Signature                   Date Printed Name Rad/Chem Coordinator:
Signature                   Date Printed Name TSC Manager:
Signature                   Date Printed Name Page 23 of 23                                CONTINUOUS USE

EPIP 8.4.3 EMERGENCY CONTAINMENT SUMP "A" SAMPLING DOCUMENT TYPE:          Technical CLASSIFICATION:        Safety Related REVISION:    7 EFFECTIVE DATE: July 12, 2002 REVIEWER:      Qualified Reviewer APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                    Date         Time List pages used for Partial Performance              Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                                  EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                     SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                                    July 12, 2002 TABLE OF CONTENTS SECTION      TITLE                                                                                                                                    PAGE 1.0          P U R PO SE ......................................................................................................................         3 2.0          PR EREQU ISITES .....................................................................................................                      3 3.0          PRECAUTIONS AND LIMITATIONS ...................................................................                                            3 4.0          IN ITIA L CON D ITION S............................................................................................                        4 5.0          PR O C ED URE ................................................................................................................             4 5.1    Perform Preliminary Evaluation For Possible Fuel Damage .....................................                                              4 5.2    Determine Additional Radiological Protection Activities Required For Sampling .......                                                      4 5.3    Check For Loss Of Instrument Air .............................................................................                             5 5.4    Containment Sump "A" Sampling Procedure (Operations) ......................................                                                5 5.5    A nalysis (Chem istry) .................................................................................................                   5 6.0   RE FERE N CE S ...........................................................................................................................        5 7 .0  BA SE S ....................................................................................................................................... 5 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION ... 6 Page 2 of 18                                                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                              July 12, 2002 1.0   PURPOSE This procedure outlines the steps taken and precautions to consider when Operations personnel are required to sample the "A" containment sumps under accident situations.
2.0   PREREQUISITES 2.1     Responsibilities 2.1.1       The Shift Manager (SM) (Operations Support Center Coordinator if TSC is activated) is responsible for the coordination of the Control Room evolutions.
2.1.2       The Duty and Call Radiation Protection Supervisor (Rad/Chem Coordinator if TSC is activated) is responsible for the oversight of the reactor coolant sample collection and analysis.
2.1.3       The Radiation Protection Supervision is responsible for the implementation of radiological monitoring controls.
2.1.4       The Chemistry Supervision is responsible for the sample analysis.
2.2     Equipment 2.2.1       Emergency Preparedness Radiation Protection Equipment maintained in OSC 2.2.2       Clean Poly Sample Bottle 3.0   PRECAUTIONS AND LIMITATIONS 3.1     A preliminary evaluation of the conditions that may be encountered in the pipeway where the sample will be drawn must be done prior to entering the Auxiliary Building.
3.2     During sampling, personnel may be subjected to radiological hazards including high radiation, contamination, and airborne radioactivity.
3.3     Personnel shall wear prescribed protective clothing, dosimetry devices, and other protective equipment when performing radiological sampling.
3.4     Improper handling of radioactive material can result in personnel contamination, radioactive material uptake, unplanned personnel exposure, and cross-contamination of samples.
3.5     Instrument air must be available to the unit to perform sampling.
Page 3 of 18                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                              July 12, 2002 4.0   INITIAL CONDITIONS Indications of possible fuel damage per Step 5.1 evaluation.
5.0   PROCEDURE NOTE:       This evaluation shall be completed prior to entering the Auxiliary Building to obtain a containment "A" sump sample.
5.1     Perform Preliminary Evaluation For Possible Fuel Damage Evaluate all of the following for indications of fuel damage:
NOTE:       Containment isolation may invalidate readings for Steps 5.1.1, 5.1.2, and 5.1.3.
5.1.1      The letdown valve gallery monitor (RE- 116) unusually high or offscale. If greater than 200 mR/hr, do not take the sump "A" sample.
5.1.2      The failed fuel monitor 1(2)RE-109 unusually high or offscale. If greater than 100 mR/hr, do not take the sump "A" sample.
5.1.3      The containment atmosphere monitors, 1(2)RE-2 11 and 1(2)RE-212 unusually high or offscale.
5.1.4      The containment low-range monitors, 1(2)RE-102 and seal table monitors, 1(2)RE- 107 reading unusually high or offscale.
5.1.5      The Auxiliary Building vent stack monitor, RE-214, could show a significant increase due to auxiliary building airborne activity from the letdown and charging pump areas.
5.1.6      The sample room area monitor, 1(2)RE-106 and charging pump area 1(2)RE-104, would give an indication of conditions in the Auxiliary Building and sample lines.
5.2     Determine Additional Radiological Protection Activities Required For Sampling After review of the radiation monitoring system readouts, Radiation Protection will determine any airborne and radiation surveys appropriate before Auxiliary Building entry.
Page 4 of 18                            REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                              July 12, 2002 5.3   Check For Loss Of Instrument Air Verify that instrument air is still in service to the affected unit. The sample cannot be obtained without instrument air to open the sample valves.
5.4   Containment Sump "A" Sampling Procedure (Operations) 5.4.1       Do NOT initiate this procedure under emergency conditions until the evaluations of Section 5.1 have been completed and results reviewed by the following:
: a. Shift Manager (SM) (Operations Support Center Coordinator if TSC is activated),
: b. Duty and Call Radiation Protection Supervisor (Rad/Chem Coordinator if TSC is activated), and 5.4.2       IF approval is granted by those listed in Step 5.4.1, THEN obtain a Containment Sump "A" sample using Procedure 01 95, Obtaining A Sump "A" Sample.
5.4.3       Take a contact reading on the sample prior to transport and inform Radiation Protection Supervision of the value.
5.5  Analysis (Chemistry) 5.5.1       Analyze the sample for boron.
5.5.2       Perform gamma scan of sample.
5.5.3       Report results to Rad/Chem Coordinator or Shift Manager.
5.5.4        Determine if adequate sodium hydroxide has been added to containment by completing Attachment A, Calculation 99-0034, Containment Sump pH Calculation.
5.5.5       Report results to Rad/Chem Coordinator or Shift Manager.

==6.0   REFERENCES==

6.1   Calculation 99-0034, Containment Sump pH Calculation 6.2   01 95, Obtaining A Sump "A" Sample 7.0   BASES None Page 5 of 18                            REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                          EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                             SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                            July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Nuclear Power Business Unit                                          Page i of 7 CALCULATION DOCUMENT FORM Calculation!.Addendumn Number:         Title of Calculation/Addendum:                                ."! .,,-7r-. .7,+&#xfd;       ....
99-0034                                TSC/EOF Containment Sump pH Calculation......                                  ...          .
Original Calculation/Addendum                                    F-1 Supersedes CalculationlAddendum
[    Revised Calculation/Addendum Revision #
Associated Documents:
[    QA Scope
[3 Non-QA Scope                            Superseded By CalculatiomtAddendum #
This Calculation has been reviewed in accordance with NP 7.2.4. The review was accomplished by one or a combination of the following (as checked):
A review of a representative sample of repetitive               A detailed review of the original calculations.                                         .         calculation.
A review of the calculation against a similar                    A review by an alternate, simplified, or calculation previously performed.                               approximate method of calculation.
Page Inventory:
Page 1 - 4 Form PBF- 1608                                        Attachments:
Page 5 - 7                                                                  A:        Pages   1  through       6 Prepared By:                                                                                    Date:
Edward A. Hinshaw                                       .                                   2/26/99 Print Name                                        Signature Reviewed By:                                                                                    Date:
Print Name                                        Signature                '-.-..
Approved By:                                                                                    Date:
Print Name                                        Signature PBF-16SO Revision 3 09130198                                                                                          Ret;.rence's)- NP 7.2.4 Page 6 of 18                                                   REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                 EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                    SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                   July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Nuclear Power Business Unit                      Calculation/Addendum:             99-0034 CALCULATION DOCUMENT FORM                                               Page 2 of     I Preparer:      Edward A. Hinshaw Date:             2/24/99 Canlculation Checklist (Optional for Non-OA Scope)
NIo                        Attribute Description                 N/       Author               Reviewer No.
Purpose                                                                            ___________
1,
: a.      the purpose clearly stated indicating issue to                          [Eyes             Ono e resolved or information to be determined?
: 2. Methodology and Acceptance Criteria
: a. Has the method/approach been described?                                    1 Nyes              E--oo
: b. Have appropriate acceptance criteria and their                    Zii
[]       Wy                    n sresbeen identified?
: 3. Assumptions                                                                         yes           O-'no
: a.    ,Ve the assumptions provided with sufficient                   Z*, []
rationale to permit verification?
: b. Have assumptions associated with pending              NA        n          e-]yes            Fj
                                                                                                                            -no plant or procedure changes that require verification been identified?
: c. Have the requirements to revise goveming              NA        D          Elyes             Ono calculations or verify pending assumrptions been documented in a modification or an EWR?
: 5.      References
: a. Have all the appropriate references, including                   0          [Eyes              W--1no irevisions and/or dates, been identified?
: b. Are all references readily available in the PBNP                 0            -yes              -]no Records System, as public documents, or attached?
: 4.      Inputs
: a. Have the applicable inputs and sources been            ,yes      Z                            Ono identified?
: 6.      Calculation
: a. Have formulae and inputs been provided                                          s            Woo consistent with the source document, including
* engineering units?                                                                                     I
: 7.      Computer-Aided Design Calculations (NP 7.2.4 Attachment A)
: a. Has the computer program been validated per          NA         []yes              ,t1.      Wno I the requirements of Attachment A?                                                    4,
: b. Have the program version and revision been           NA         E     l   Dyes              U Fo identified on the computer run and in the                                             . ,
calculation?                                      -    -
PMF-1608 Rdfr.ae(s): NP 7.2*4 Revision 3 0913098 Page 7 of 18                                                REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                   EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                       SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                     July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Nuclear Power Business Unit                        Calculafion/Addendum:           99-0034 CALCULATION DOCUMENT FORM                                                  Paae 3,of  7 Preparer:   Edward A. Hinshaw Date:        2/24/99 Item                           Attribute Description No.
: c. Is the input to the computer program adequately documented"
: d. If spreadsheet or other simple computer aided tools are used in the calculation, have the formulae been documented in the calculation?
: e. Have the attributes been documented in the calculation for any input or output data files supporting the calculation, including file name, date stamp, time stamp (hour and minute only),
and file size?
: 8.   ] Summary of Results and Conclusions
: a. Do the summary of results and conclusions                            Z       nx yes             Dno clearly state the calculation results and respond ito the purpose?
: b. Do the conclusions address the acceptability/                     M]      Eyes               Dno unacceptability of the results?
C. Has a CR been initiated to identify any                NA                 Lyes I,'           D-no unsatisfactory conditions?
: d. Have al_ engineering judgments been provided               rpjyes                            Ono with sufficient rationale?
: 9.         Administrative
: a. Have calculation format and content as noted in                 i            ayes                  -no NP 7.2.4 been followed?
: b. Have all required attachments been included in                        Z       [pyes                   10no the document and numbered appropriately?
: c. Has the calculation been prepared neatly and                      Z]      ayes               Dno legibly with sufficient contrast to allow satisfactory record copies to be produced?
: d. Are the calculation number, preparer's initials,            .'                   yes             O.-no preparation date. and page number provided on each page?
: e. Have revisions been clearly identified by                  NAX        ]       Dyes    g,         Dno revision bars or other appropriate means (for revised calculations only)?
: f. If the calculation supersedes a previous                                     Dyes         "
calculation, is this noted on the cover sheet?         NA
: g. Has the calculation been appropriately                                        Wyes               Ljno identified as QA or Non-QA scope?
: h. Has the review method been clearly identified                                 Fdyes              D-1no on the cover page?
PIF- 1608 Revision 3 09130!98                                                                                       Refer,-'nce~): NP 7.2.4 Page 8 of 18                                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                              EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                 SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Nuclear Power Business Unit                   Calculation/Addendum:        99-0034 CALCULATION DOCUMENT FORMI                                            Page 4 of 7 Preparer:  Edward A. Hinhaaw Date:       2124199
: i. Is all information requested by PBF-1620 entered on the form?
COMMENTS AND RESOLUTION Reviewer Comments:                                        1 Resolution:
Pe3F- 1608 R,*r   .):NP 7.2.z Revision 3 09/301,98 Page 9 of 18                                      REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                   SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                  July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calc # 99-0034                     TSC/EOF Containment Sump pH Calculation

==Purpose:==
The purpose of this calculation is to support the form to be used by the TSC or EOF for determination of the approximate containment sump pH based on actual plant conditions. The form is to be used by the TSC or the EOF to determine ifadequate sodium hydroxide has been added to containment. The calculation will determine the conversion factors used on the proposed form.
Methodology & Acceptance Criteria Using plant design criteria and data, a simplified form will be developed to allow the TSC or EOF to quickly determine if an adequate minimum amount of sodium hydroxide has been added to containment following an event which would require containment sump recirculation.
Assumptions:
: 1)    The entire contents of the RCS and the Accumulators empties into the containment building.
: 2)    The volume of water contained in piping systems such as CVCS and other system connections was ignored.
: 3)    The concentration of sodium hydroxide in the spray add tank was assumed to be 31%. The average concentration over the last 11 years was 31.04/31.2 for units 1/2 respective.
: 4)    The volume for the accumulators is assumed to be the maximum as described in the FSAR.
This would be a conservative value for a low pH concern and introduces only 3.2% error on the conservative side. Therefore the accumulator volume used is 2272 cubic feet.
: 5)    Since a LOCA is assumed to occur from 100% power, the volume of water in the RCS has a specific gravity of 0.7476 (Ref 5).
: 6)    Density of sodium iydroxide can be linearly interpolated between 30 and 33%.

==Reference:==
: 1) Chemistry computer program Cequil produced all the numbers used in attachment A for the resultant pH of a mixture of sodium hydroxide and boric acid.
: 2) Calculation 89-015 determined the correlation of specific gravity to boron concentration. 1.005 g/cc for RWST and Accumulators, 1.012 g/cc for BAST.
: 3) TLB-1 0 for RWST level versus volume conversion of 2835 gallons/%.
: 4) FSAR volume in cubic feet for RCS, FSAR TABLE 4.1-1 & TS 15.5.3.B.3. Other references indicate up to 6643 cubic feet.
: 5) From ASME Steam Tables 5th Edition. Temp & Pressure from FSAR Table 4.1-2
: 6) Specific gravity of 31% sodium hydroxide from Calc N89-089, interpolated between 30 and 33% =1.35
: 7) Accumulator maximum volume 1136 cubic feet, Tech Spec 15.3.3.A.1.b.
: 8) Calculation N-89-089 for density of 30% and 33% sodium hydroxide.
Inputs:
: 1) The RCS volume is considered 6700 cubic feet. Reference 4. This value was then converted to kilograms using the specific gravity of water at operating temperature and converting to 25 degrees celsius.
: 2) Specific Gravity of 0.7476 is of water at 552.5 deg F and 2235 psig. Reference 5
: 3) Density of 30% NaOH= 11.17 lb/gal Reference 8
: 4) Amount of NaOH in 30% solution 3.35 lb/gal. Reference 8
: 5) Density of 33% NaOH=1 1.44 hb/gal. Reference 8
: 6) Amount of NaOH in 33% solution 3.78 lb/gal. Reference 8
: 7) Density of 31% NaOH=I 1.26 lb/gal (5,12Kg/gal) Interpolated from inputs 3 and 5.
: 8) Amount of NaOH in 31% solution= 3.49 lb/gal (1,586 Kg/gal). Interpolated from inputs 4 and 6.
EAH 3/5/1999                                       Page 5 of 7                      Reviewed by Page 10 of 18                                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                              EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                 SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                                July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calc # 99-0034                      TSC/EOF Containment Sump pH Calculation Calculation:
RCS VOLUME IN KILOGRAMS IS CALCULATED AS FOLLOWS:
                               - ,      lijter        ke:                                             5 RCSVO := 6700.ft".*8.312--0.7476-'g                                RCSVO = 1.418-0              ~kg ft3         liter ACCUMULATOR VOLUME IS CALCULATED AS FOLLOWS:
ACCUMVOL := 22 7 2 -fc3.28. 3 12.lter.1.005 1kg, Two accumulators at spec gravity of 1.005                                                               ft"3      liter ACCI.)NIVOL = 6.465-104                              tkg This is the total RCS and Accumulator                       TOTALRCS:= ACCU.IVOL+ RCSVO volume conversion factor.
5 TOTALRCS=2.065.10                   -kg RWST VOLUME CORRECTION IS CALCULATED AS FOLLOWS:
liter           k.,
RWSTVOL :=3.785.--t1.0            5.005 gal           liter RWSTVOL = 3.804 kg gal BAST VOLUME CORRECTION IS DEFINED AS:
BASTCOR:=3.785      3 8titer 2 t. 06 Inl* 10.81 g ].0t2.k      kgR.
This factor converts % boric acid                                                 gal          kg 61.83 g         liter concentration times gallons of BAST used to mg B BASTCOR=6,697,10               o mg gal .%
SPRAY ADD TANK CONVERSION FACTORS kg 22.99
                                           . 106 nig
                                                 " -3.7.5 .q_ liter .l.35 -kg kg SODIUM COR : -.3 0. ..                                                       SODIUMCOR =9.104-t051()
5 ma' kg 40        kg            gal        liter                                          gal to %ayweight 31%            CRsion by weightX X Ratio ofFtors NaaThis N                   factor converts gallons of SAT to mg Na to NaOH X Conversion Factors X Spec Gray of 31% NaOH (Ref 6)
This section converts gallons of spray add solution to Kilograms of water.
EAH 3/5/1999                                            Page 6 of 7                                 Reviewed by PagellIofl18                                                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                  EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                     SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                    July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calc # 99-0034                    TSC/EOF Containment Sump pH Calculation To convert gallons of Spray Add Tank solution to kilograms of water, I took the density of the spray addition solution minus the amount of NaOH in the solution. This leaves the amount of water in the spray solution.
Conversion factor= ((11.26 lb/gal - 3.49 lb/gal) /8.33 lb/gal) X 3.785 kg/gal = 3.53 Results:
The following conversion factors are to be used for the form to calculate the approximate pH of the containment sump.
Converts Accumulator volume in cubic feet and adds to RCS            206500 kg water in RCS & Accumulators Converts RCS boron concentration to milligrams of boron              141800 mg Boron/ppm Boron in RCS Converts ppm Boron for Accumulators into miligrams boron             64650/2 since the two accumulators are added together before multiplying, Converts ppm Boron and Gallons of RWST used to milligrams 3.804 mg Boron Converts Gallons of BAST at Concentration to milligrams Boron 6697 mg Boron/gallon BAST Converts Gallons of SAT added to milligrams of Sodium                910400 mg Na/gallon Converts Gallons of SAT into kilograms of Water                     3.53 kg/gal

== Conclusion:==

The conversion factors used for the determination of approximate pH in the Containment Sump were calculated in this calculation and are valid for use by the TSC/EOF to predict sump pH.
EAH 3/5/1999                                       Page 7 of 7                       Reviewed by Page 12 of 18                                              REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                            EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                               SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                              July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calc 99-0034                 TSC/EOF Containment Sump pH Calculation Containment Sump pH Calculation Form This form is to be used for determination of the approximate sump pH based on actual plant conditions. It is to be used by the TSC or the CEC to determine if adequate sodium hydroxide has been added to the containment. This calculation also includes boric acid added from the BAST Assumptions made to simplify the calculation:
: 1) The entire contents of the RCS and the Accumulators has emptied into the containment building. If the accumulators have not emptied. enter 0 for boron concentration and enter only the RCS volume in the WATER section. The volume for the accumulators is assumed to be the maximum as described in the FSAR. This would be a conservative value for a low pH concern and introduces only 3.2% error on the conservative side.
Therefore the accumulator volume used is 2272 cubic feet.
: 2) The RCS volume is considered 6700 cubic feet. This value was then converted to liters using the specific gravity of water at operating temperature and converting to 25 degrees celsius.
: 3) The volume of water contained in piping systems such as CVCS and other system connections was ignored. This assumption would introduce an error less than 1%.
: 4) The concentration of sodium hydroxide in the spray add tank was assumed to be 31%.
The average concentration over the last 11 years was 31.04/31.2 for units 1/2 respective.
Enter the most recent RCS boron.                        RCSBORON                 _    _     PPM (1)
Note: Enter Zero (0) if the Accumulators were isolated or did not inject into the RCS.
              "A" Accumulator boron concentration.                    ACCUMABO RON          A      __      PPM (2)
              "B" Accumulator boron concentration.                    ACCUMBBORON           B              PPM (3)
RWST boron concentration:                               RWSTBORON                _          PPM (4)
RWST level change in %: ___          %  X 2835 gal/%    RWST_VOL                      ___  GAL (5)
Enter the on-service BAST concentration:                BAST-BORON (6)
__GAL Enter the volume of BAST used in gallons:               BASTVOL (7)
Enter the volume of SAT used so far in gallons:         SATVOL                        ___  GAL (8)
EAH 3/5/1999                                  Attachment A                                   Page 1 of 6 Pagoe 13 of 18                                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                       EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                          SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                         July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calc 99-0034                  TSC/EOF Containment Sump pH Calculation This section calculates the amount of boron added to containment BORON=                  x 141800 + (                -,-              ) X 32325    =                   mg (1)                        (2)          (3)                            (9)
BORON1=                    -+              X             x3.804+                 x             x 6697 (9)            (4)            (5)                    (M)        (7)
BORON1=        ____mg (10)
This section calculates the amount of sodium added to containment SODIUM=                     X 910400 mg/gal                      SODIUM= __.rag (8)
(11)
This section calculates the total water added to containment WATER = 206500 + 3.804 X __                   + 3.830 X        -      + 3.53 X       -
NOTE 1                    (5)                   (7)                  (8)
* NOTE 1 Use 141800 kg if neither accumulator                                  WATER=              -       kg emptied                                                                               (12)
BORON CONCENTRATION= (10)/(12)=                   __/                 -       =-                 ppm (10)         (12)
Boron Concentration (X axis) on Figures 1& 2 SODIUM CONCENTRATION = (11) 1(12) =                    -      /            --                     ppm (11)           (12)
Sodium Concentration (Labelled lines) on Figures 1 & 2 REFER TO ATTACHED FIGURES TO FIND THE THEORETICAL PH OF THE CONTAINMENT SUMP.
SUMP pH                        Date:                       -Time:                     Initials:
THIS CALCULATION IS CONSERVATIVE LOW, ACTUAL PH WILL BE HIGHER DUE TO BORIC ACID PRECIPITATION AND REACTION OF BORIC ACID WITH MATERIALS IN CONTAINMENT. UP TO:200 PPM OF BORON COULD REACT OR PRECIPITATE AS STATED IN FSAR EAH 3/5/1999                                     Attachment A                                           Page 2 of 6 Pagre 14 of 18                                                  REFERENCE USE

K                                                        (
POINT BEACH NUCLEAR PLANT                                                                    EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                       SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                      July 12, 2002 ATTACHMENT A CALCULATION     99-0034,      CONTAINMENT SUMP PH CALCULATION Calculation 99-0034                                                                                Attachrnert A Containment Sump Calculated pH
                                                                                                    --        Na=O 10
                                                                                                    -w Na=25
                                                                                                       -- ,- Na,=75
                                                                                                       --- Na=100
                                                                                                    ---       Na=150 SNa=200
                                                                                                    -+-.--Na=250 9
                                                                                                    -Na=300
                                                                                                    -         Na=400 i---Na=500 8.5
                                                                                                           -Na=600 1                                -     -  Na=700 C.
                                                                     ....                             ---     Na=800 8
E                                                                                         ---      Na=1000
                                                                                                     --       Na=1200
                                      ... ........   .  .... ..                                            -Na=1400,;
7.5
                                                                                                     -        Na=1600.
                                                                                                     ---- Na=1800c)
                                                                                                       --- Na=2000
                 .7
                                                                                                     --- Na=2200, SNa=2400
                                                                                                     --       Na=2600 6:
6.5 i-*        Na=28000 1500      1700   1900            2100           2300      2500   2700 2900 PPM Boron EAH 2126!1999                                                                                        Page3 of 6 Page 15 of 18                                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                               EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                  SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                 July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calculation 99-0034                                                                           Attachment A Containment Sump Calculated pH 10
                                                                                                -+-Na=70
                                                                                                 -a Na=25
                                                                                                -r-- Na=75
                                                                                                -h- Na=100 A Na=150
                                                                                                      - Na=200 9                                                                                ----- Na=250 I-       Na=300
                                                                                                -       Na=400 8.5                                                                                    -Na=500
                                                                                                 &#xfd;--Na=600
                                                                                                   -Na=700 E*
2E 8                                                                                  --     Na=1800
                                                                                                 --     Na= 10001
                                                                                                 --     Na= 1200 7 .5 .........                                                                     --     Na--1400
                                                                                                  --    Na=1600i 75
                                                                                                 --     Na=1800i
                                                                                                 -   Na--2000!
                                                                                                 --9 Na=2200
                                                                                                 --&#xa2;-A-Na=24001
                                                                                               ' -,-X...Na=2600 6.5
                                                                                                     ! '-Na=2800 600  700  800    900      1000   1100      1200 1300 1400  1500 PPM Boron EAH 2/26/1999 Page -L of r Page 16 of 18                                                REFERENCE USE

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POINT BEACH NUCLEAR PLANT                                                                                                                              EPIP 8.4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                                                                 SAFETY RELATED Revision 7 EMERGENCY CONTAINMENT SUMP "A" SAMPLING                                                                                                                July 12, 2002 ATTACHMENT A CALCULATION 99-0034, CONTAINMENT SUMP PH CALCULATION Calculation 99-0034                                             Containment Sump pH                                                                        Allrhmene tA 19002000         210                  ...
2.3001 .24001
                                                               .20                          250              260        2700        2800_      _2900      3000.8Boron I           .Sodi                                                                             um
: 46. 4,63:         4.1                  4.55                                    ......                6.5.......
                                                                                                                                    ......... 4.432                      25.4 886 6.8 6.10 6.36         6.3         6.251                 6.14          6.01           604       .
6.74 6.9'.......-                                                                ......--...                        _     25 6.8;1          6.6      6I            66574                                                                                         75 6.99             -6.838        6.82     6.7676.72,                   6.6 7.19,       73           7.08         7.02;    6. W          6.92 1         6.67             6.829      6.771       671         66,       661              5
                                    .72' 7.23          7.1      7.12          7.071          7.02.            0.071w     6.92         J.7        6.83      6.79i          200 7.46        7,41       7.,3           7.29;    7,241         7.C714-.9                                    .4          99,       6.,95       6.9             ,25 7.57 7.5 /451           7.~    7.34       -7.20i            7.24: .............
7.0t9;       .4        701         70                         0 7.7   .1          7.63         7.57     7.13          7.46           7.241            7.3        7.1         7.6         122       71             40 7.777        .6           7.461          7.55              7.53        45         741737.31                           500............
80  7.5            7.9        7.841    7.79:         7.73           7.68             7.63-      7.58        7.53        7.48      7.43           600 8.4  6.08         8.02.        7.96       7.90        7.8-'          /.79             7.74&#xfd;      7.609       7.64        7.59:     7.55,          700 6.18         8.12         806      8.01.         7.95             7.9            7.4               7.79 774         7.9        .6             60 84: 8.36:         8..32        8'.26. 8.2,        614            8,09.            8m.0       7.05        7.93        7.88      7.83          1000 8.5     .9,        8.43     8.37.         831,           6.25:              0.2      8.15         8.1        6.04          8         1200 8.93.
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                          ...........                                       .9..2.................................
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EAII2/26/1    999                                                   Hi-gh Sodiurn/Boron                                                                   Pa,,e     L   o f16 Page 18 of 18                                                                                         REFERENCE USE

EPIP 10.1 EMERGENCY REENTRY DOCUMENT TYPE:          Technical CLASSIFICATION:        NNSR REVISION:    22 EFFECTIVE DATE: July 12, 2002 REVIEWER:      N/A APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title):           Group Owner OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                    Date         Time List pages used for Partial Performance              Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                             EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                NNSR Revision 22 EMERGENCY REENTRY                                                                                     July 12, 2002 TABLE OF CONTENTS SECTION    TITLE                                                                                                                                  PAGE 1.0        PU R P O SE ......................................................................................................................        3 2.0        PREREQUISITES .....................................................................................................                       3 3.0        PRECAUTIONS AND LIMITATIONS ...................................................................                                           4 4.0        INITIAL CONDITIONS ............................................................................................                           5 5.0        P R O CE D URE ................................................................................................................           5 5.1  Initial Control Room Response .....................................................................................                       5 5.2  Reentry Team Deployment .......................................................................................                           6 5.3  Reentry Teams Debriefing ..........................................................................................                       8 5.4  Work Order Control ..................................................................................................                     9 5 .5 T ag o u ts .......................................................................................................................... 10 6.0        RE FE R EN C E S ..............................................................................................................           11 7 .0       B A SE S ..........................................................................................................................       12 ATTACHMENT A REENTRY TEAM MANAGEMENT ............................................................                                                    13 ATTACHMENT B REENTRY TEAM DISPATCH .....................................................................                                             14 ATTACHMENT C REENTRY TEAM DEBRIEF .......................................................................                                            15 Page 2 of 15                                                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 22 EMERGENCY REENTRY                                                    July 12, 2002 1.0   PURPOSE This procedure provides the guidance and requirements necessary to conduct emergency reentry operations. These operations can include reentry for radiological surveys, repairs, operational functions, fire, medical emergencies, or search and rescue.
The guidance in this procedure includes directions for the proper radiological protection and monitoring of personnel involved.
2.0   PREREQUISITES 2.1     Responsibilities 2.1.1       Prior to the activation of the Operations Support Center (OSC), the Shift Manager (SM), or a designee, is responsible for
: a. Dispatch of reentry teams
: b. On-Shift Radiation Protection Technologists (RPTs)
: c. On-Shift Radiochemical Technicians (RCTs)
: d. Non-PBNP We Energies personnel, Nuclear Management Company (NMC) fleet personnel, or contractor teams that may be conducting repairs inside and outside the protected area
: e. Medical emergencies in the PBNP owner controlled area 2.1.2       The TSC Manager is responsible for the prioritization of reentry teams, coordinated with the OSC Coordinator, Reentry Team Coordinator, and SM.
2.1.3       The Reentry Team Coordinator, under the direction of the OSC Coordinator, is responsible for the oversight of all OSC Leaders, reentry teams and recovery operations (Attachment A, Reentry Team Management).
2.2    Equipment 2.2.1      FM radio base station and portable radios (EPMP 2.1).
2.2.2      Radiation Protection equipment (PIM OSC 3.2, Attachment A).
2.2.3       OSC Radiation Protection Inventory (EPMP 1.1).
2.2.4       Chemistry equipment (PIM OSC 3.6, Attachment A).
Page 3 of 15                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                          EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             NNSR Revision 22 EMERGENCY REENTRY                                                  July 12, 2002 2.2.5       OSC emergency preparedness inventory (EPMP 1.3).
: a. First aid kits, burn kits, trauma kits, and stretchers
: b. OSC tools 2.2.6        Other equipment deemed appropriate for the specific event.
3.0   PRECAUTIONS AND LIMITATIONS 3.1  Radiological controls, as specified in HP 3.2, Radiological Labeling, Posting and Barricading Requirements, are to be maintained during all reentry operations, if circumstances allow.
3.2  Radiation Protection practices must be adhered to in accordance with Radiation Protection Procedure NP 4.2.19, General Rules for Work in a Radiologically Controlled Area, if circumstances allow.
3.3  Personnel shall wear radiological protection equipment as prescribed in NP 4.2.27, Personnel Exposure Monitoring Device Minimum Requirements and General Use and NP 4.2.22, Requirements for Use of Protective Clothing; shall be used for guidance.
3.4  The use of self-contained respiratory protection equipment should be considered for on-shift RPTs and Operations personnel having a necessity to enter any area where a spill or other discharge of reactor coolant has caused, or has the potential for causing, an increase in airborne activity.
3.5  During the performance of radiation surveys, personnel may be subjected to radiological hazards, including high radiation areas, contaminated areas, and airborne radioactivity areas.
3.6  Improper handling of radioactive material can result in personnel contamination, radioactive material uptake, or unplanned personnel exposure.
3.7  When processing fire brigade teams, follow established fire brigade response policies.
3.8  Personnel should exercise the principles of time, distance, and shielding to minimize radiation exposure.
Page 4 of 15                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 22 EMERGENCY REENTRY                                                    July 12, 2002 4.0   INITIAL CONDITIONS 4.1   Assembly and accountability of personnel has been completed and/or persons are known to be missing or in need of help - Search and Rescue.
4.2   Emergency response requires reentry to support plant repair and/or recovery, radiological release termination, or damage assessment.
4.3   Fire or potential fire.
5.0   PROCEDURE 5.1    Initial Control Room Response 5.1.1       The SM shall dispatch all necessary reentry teams and maintain accountability of all on-shift personnel prior to the activation of the OSC.
5.1.2       Prior to allowing entries into and/or work to continue in the RCA, the SM and RPT shall review the radiation monitoring system area and process monitors to determine area radiation levels and possible high airborne activity that could affect personnel exposure. Possible abnormal conditions may be indicated by:
: a. Increased count rates above the alarm setpoints on the Auxiliary Building vent stack monitor (RE-214).
: b. Any continuous air sampler(s) exceeding the alarm setpoint(s) and/or indicating a rising trend.
: c. Local area monitorsabove alarm setpoints.
5.1.3        Direct personnel working within the radiation control area (RCA) to periodically check the count rate on the following continuous air samplers for indications of increasing Auxiliary Building airborne activity:
: a. C59 panel area
: b. Spent fuel pool
: c. Outside the charging pump cubicles
: d. Outside the CVCS holdup tank Page 5 of 15                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                       EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          NNSR Revision 22 EMERGENCY REENTRY                                               July 12, 2002 5.1.4      IF on-shift RPTs, RCTs, or Operations personnel need to enter an area where there is a known or suspected spill, leak, or release of radioactive material or airborne activity, THEN consult with the on-shift RPT and consider the following:
: a. Self-contained respiratory protection equipment.
: b. Dosimetry, appropriate protective clothing, and survey instruments for continuous exposure monitoring.
: c. Implementing radiation surveys of affected area(s) to determine the scope of the radiation and contamination problem.
: d. Radiation protection postings of the affected area(s), if required.
: e. Decontamination operations, if necessary.
5.1.5     Direct all entries and/or exits of personnel from the RCA to be by way of the checkpoint unless an alternate route is appropriate.
5.1.6      If appropriate, direct RCTs to report to TSC Count Room and begin activation of that area using PIM OSC 3.6, OSC Chemistry Leader.
5.2  Reentry Team Deployment NOTE:      All teams should be dispatched promptly. A 15 minute goal has been established, commensurate with urgency of the task and available resources.
NOTE:      Reentry teams for life saving, fire fighting, release termination, and search and rescue shall have the highest priority and be dispatched immediately, completing Attachment B, Reentry Team Dispatch, after dispatch.
NOTE:      Teams shall consist of a minimum of two people, both qualified in first aid/CPR if a medical emergency.
5.2.1      IF a medical emergency, THEN also implement EPIP 11.2.
5.2.2      The routine procedure for development of work orders WILL NOT be used during emergencies. An unforeseen Work Order (WO) shall be used to document and control repair work per Step 5.4.
Page 6 of 15                            REFERENCE USE

POINT BEACH NUCLEAR PLANT                                   EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                       NNSR Revision 22 EMERGENCY REENTRY                                            July 12, 2002 5.2.3   The routine procedure for development of tagouts WILL NOT be used during emergencies. An emergency Tagout shall be used per Step 5.5.
5.2.4   The Reentry Team Coordinator shall assign team priorities consistent with the priorities of the TSC.
5.2.5   IF radiological conditions are present or suspected, THEN the Reentry Team Coordinator shall notify the Radiation Protection Leader.
5.2.6   When a reentry team is required, the Reentry Team Coordinator shall assign an OSC Leader per the task required. The OSC Leader shall prepare and deploy the reentry team, completing the appropriate section of Attachment B, Reentry Team Dispatch.
: a. IF radiological conditions are present, THEN the OSC Leader shall coordinate the reentry team dispatch with the Radiation Protection Leader. The Radiation Protection Leader shall prepare and brief reentry teams, completing the appropriate section of Attachment B, in lieu of an RWP.
: b. Assign a team identifier which reflects the team's function.
: c. Determine and record the job scope and appropriate tagouts for the task.
: d. Obtain SM approval for tagouts.
: e. Determine the appropriate repair parts and tools for the task.
: f. Issue and test the FM portable radios or other communication devices, as appropriate.
: g. Select and assign personnel to the team evaluating team member qualifications for the (i.e., SCBA, First Aid, CPR) reentry per ETD 01.
: h. Assign a team lead to be responsible for communications, keys, dose checks, and the need for reliefs.
: i. Determine the appropriate personal protection equipment necessary for the task.
Page 7 of 15                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                      EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         NNSR Revision 22 EMERGENCY REENTRY                                              July 12, 2002
: j. Evaluate the safety precautions that should be adhered to.
: k. Conduct a short, concise job brief consisting of:
                         "*    Scope of task, location, hazards, and stay times.
                         "*    Reminder to maintain visual or vocal contact with other team members.
                         "*     Relevant information from other reentry teams.
                         "*     Use plant maps available in the OSC to illustrate routes and backout areas.
                         "*     During reentry task, monitor progress and be observant of unexpected conditions.
5.2.7     After team deployment, the OSC Leader shall:
: a. Inform the OSC Communicator of the team deployment.
: b. Inform the OSC Technical Monitor of the team deployment.
: c. Form a standby team to be used for reliefs and/or search and rescue if necessary.
: d. Monitor reentry team dispatched for work in progress, unexpected conditions, and safety concerns.
: e. Complete Attachment B, Reentry Team Dispatch, to track reentry team dispatch.
5.3  Reentry Teams Debriefing 5.3.1      Complete the appropriate sections of Attachment C, Reentry Team Debrief.
: a. Log exposure of each team member and obtain their initials.
: b. Anyone >4 rem, >25 rem or suspected >10,000 DAC-hours (ref. EPIP 5.1 if answer is yes).
: c. Status of task team was assigned to and related comments.
Page 8 of 15                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                       EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          NNSR Revision 22 EMERGENCY REENTRY                                               July 12, 2002
: d. General observations regarding damage, water spills, leaks, route problems, etc.
: e. Status of team members physical condition.
: f. Disposition of team members.
: g. Update OSC status boards and plant maps with current conditions.
5.3.2    Advise Reentry Team Coordinator of reentry team task status and comments for use in future reentry team assignments.
5.3.3    Ensure Radiation Protection is maintaining a running total of each persons radiation exposure upon each reentry team return and keeping the Rad/Chem Coordinator and/or Dose/PAR Coordinator advised of their radiological exposure status.
5.4  Work Order Control 5.4.1    Tasks desired by the TSC or Control Room will be defined as clearly and briefly as possible. All personnel required will be used to define and clarify the tasks (i.e., TSC Engineers, respective OSC Leaders per task requirements, etc.).
5.4.2     Obtain PBF-9923d, Unforeseen Work Order, form and a number from the Unforeseen Work Order log (located in the OSC file cabinet) and record on Attachment B, Reentry Team Dispatch. This form "becomes" the work order for emergencies.
5.4.3     Record the reentry task on Attachment B, in the "job scope" block. Attach additional sheets as necessary.
5.4.4     Ensure any required Tagout is defined    (Reference Step 5.5).
5.4.5    At the termination of the event, ensure all paperwork is collected for reconstruction of work completed, actions taken, etc.
Page 9 of 15                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                         EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            NNSR Revision 22 EMERGENCY REENTRY                                                 July 12, 2002 5.5  Tagouts 5.5.1      Determine the required boundaries to be tagged to perform the task. Ensure all sources (water, air, steam, and electricity) are addressed. All personnel required will be used to define and clarify the tasks (i.e., TSC Engineers, respective OSC Leaders per task requirements, etc.).
CAUTION If tags must be hung in a required order, ensure this is clearly indicated on both the tagout and the tags.
5.5.2      Obtain a tagging number from the PBF-1906d, Danger Tag Protected Worker log and record on Attachment B, Reentry Team Dispatch. This log may have been brought to the TSC by the TSC Manager. Attachment B "becomes" the tagout for emergencies.
5.5.3      Record the Tagout description on Attachment B. Attach additional sheets as necessary.
5.5.4      Obtain verbal approval from the Control Room SM. This may require faxing more complex tagouts or may be accomplished by verbal coordination for a few valves or breakers.
5.5.5      Record the SM initials and time per the verbal approval on Attachment B.
NOTE:      The purpose of danger tags is to protect workers and allow emergency work.
5.5.6      Complete the Danger Tags. At a minimum each tag shall include:
: a. Tagging number or Team ID
: b. Exact component description
: c. Desired position and/or state 5.5.7       Review the Danger Tag(s) with the person(s) who will be responsible for hanging the tag(s).
Page 10 of 15                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                       EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          NNSR Revision 22 EMERGENCY REENTRY                                               July 12, 2002 NOTE:      Operating Permit Tags WILL NOT be used under emergency conditions.
Instructions below will take precedence.
5.5.8      IF it becomes necessary to remove a tag (and change component status) temporarily (for example, to check pump rotation),
THEN the Reentry Team Coordinator is responsible to ensure ALL personnel are protected.
5.5.9      Obtain verbal approval to remove the tag (and change component status) from the Control Room SM.
5.5.10     Make a Gai-tronics announcement warning personnel of the impending status change.
5.5.11     Contact each team in the plant directly and warn them of the impending status change.
5.5.12     Ensure immediate means are available to contact the person lifting the tag (i.e., radio).
5.5.13     Brief person lifting tags on expected results and actions to take if the results are NOT obtained.
5.5.14      Monitor for unexpected conditions as tag is lifted.

==6.0   REFERENCES==

6.1  EPIP 4.2, Operations Support Center (OSC) Activation and Evacuation 6.2  EPIP 5.1, Personnel Emergency Dose Authorization 6.3  EPIP 5.2, Radioiodine Blocking and Thyroid Dose Accounting 6.4  EPIP 11.2, Medical Emergency 6.5  EPMP 1.1, Routine Check, Maintenance, Calibration and Inventory Schedule for Radiation Protection Emergency Preparedness Equipment 6.6  EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies 6.7  EPMP 2.1, Testing of Communications Equipment 6.8  ETD 01, Emergency Response Organization (ERO) Call List 6.9   HP 3.2, Radiological Labeling, Posting, and Barricading Requirements Page I11 of 15                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                     EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                        NNSR Revision 22 EMERGENCY REENTRY                                             July 12, 2002 6.10 HP 4.7, Emergency Response with Respiratory Equipment 6.11 NP 2.1.1, NMC Conduct of Operations (NMC FP-01) OP-COO 6.12 NP 1.9.15, Tagging Procedure 6.13 NP 4.2.19, General Rules for Work in a Radiologically Controlled Area 6.14 NP 4.2.22, Requirements for Use of Protective Clothing 6.15 NP 4.2.32, Respiratory Protection Program 6.16 NP 4.2.27, Personnel Exposure Monitoring Device Minimum Requirements and General Use 6.17 NP 8.1.5, Unforeseen Work Order Creation 6.18 PBF- 1906d, Danger Tag Protected Worker Log 6.19 PBF-9923d, Unforeseen Work Order 6.20 PIM OSC 3.2, Radiation Protection Leader 6.21 PIM OSC 3.6, Chemistry Leader 7.0   BASES B-1   10 CFR 50.47(b), Emergency Plans B-2   10 CFR 50.47, Appendix E.IV, Content of Emergency Plans Page 12 of 15                        REFERENCE USE

POINT BEACH NUCLEAR PLANT                      EPIP 10.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES         NNSR Revision 22 EMERGENCY REENTRY                              July 12, 2002 ATTACHMENT A REENTRY TEAM MANAGEMENT Page 13 of 15                 REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                            EPIP 10.1                         (
NNSR EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 22 July 12, 2002 EMERGENCY REENTRY ATTACHMENT B REENTRY TEAM DISPATCH NOTE 1: This attachment is used in lieu of an Radiation Work Permit, Maintenance Work Order, and Tagout.
NOTE 2: Teams shall consist of a minimum of two people. Each team member's qualifications required for this reentry task are current.
NOTE 3: OSC Leader can N/A RP Leader section if sending team to known clean area.
JOB BRIEF-OSC Leader                                    Date/Time                     RP BRIEF-RP Leader                                   Date/Time (Signature)                                                                        (Signature)
Team ID                          Team Lead                                           Keys (HRA)                          Stay Times Communications Equip                                               0_ w/CR         Protective Clothing El w/OSC-A/B: x           x(     x       ,x&#xfd;     L   w/OSC-E: x         x          In-Plant Radiological Conditions Keys                              Dose Checks Need for Reliefs                              Other                                Survey Instruments Job Scope & WO #                                                                     Respiratory Protection
_L Electronic Personnel Dosimeter EL      SRD/Range Tagout #s & Desc    __                                                                      Extremity Dosimetty              EL Other EL   Time keeping/High Dose Tasks SM Approval for Tagouts               /L                 SCBAs Donned - Estimated empty time Parts/Tools                                                                           El   Maps and information from other teams
_L   >4 rem or >10 CFR 20 Limits (per EPIP 5.1 prior to dispatch)
Procedures/Drawings                                                                   El   Issue KI >25 rem Thyroid (per EPIP 5.2 prior to dispatch)
Safety Precautions/PPE Review running dose records and assign dose limits (<25 rem whole body)
E-  Visual or vocal contact with team member                                                         Dose Alarm Dose Rate Alarm Allowable             Received Members           (mrem)         (mremlhr)         Dose (rem)   Dose (rem)
LI  Maps and information from other teams LI  Changing conditions (e.g., flooding, steam, damages)
LI  In-plant routes, Back-out Areas After Team Deployment:
EZ Inform OSC Communicator & Tech Monitor of team deployment El  Form standby team (for reliefs and/or search and rescue-optional)
Time Deployed:                                                   Distribution Upon Dispatch:                                          Distribution Upon Return:
Original in OSC Original to TSC Expected Return Time:
Copy to Team Lead and TSC Actual Return Time: _
Page 14 of 15                                                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                EPIP 10.1 NNSR EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 22 EMERGENCY REENTRY                                                        July 12, 2002 ATTACHMENT C REENTRY TEAM DEBRIEF Team ID                                               Task Time/Time Deployed                                    Time Returned NOTE:          Ensure Radiation Protection is maintaining a running total of each persons radiation exposure upon each reentry team return and keeping the Rad/Chem Coordinator and/or Dose/PAR Coordinator advised of their radiological exposure status.
Exposure Initials         I           I           I             I             I             I Dose (rem)
Anyone > 25 rem or suspected > 10,000 DAC-hours? If yes, remove from emergency duty and notify the Emergency Director for referral to a physician for medical evaluation (EPIP 5.1).
n    NO     DYES (Name)
Anyone > 4 rem? If yes, consult Emergency Director for potential referral to physician (EPIP 5.1)
F-1 NO H YES (Name)
Task Status/Comments General Observations Damage Water/Spills/Leaks Radiological Concerns Route Problems Other Team Members Physical Status Team Members Standby Status 7 Standby - OSC E, El. 8', El. 26', or as conditions or space allow F--  Released to go home E- Other
    -    Update OSC status boards and plant maps.
Respective OSC Leader Review                                                 Time/Date           I Time/Date           /
Reentry Team Coordinator Review I           Route to the Rad/Chem Coordinator with a copy to OSC Coordinator when completed Page 15 of 15                            REFERENCE USE

EPIP 11.2 MEDICAL EMERGENCY DOCUMENT TYPE:          Technical CLASSIFICATION:        NNSR REVISION:     16 EFFECTIVE DATE:         July 12, 2002 REVIEWER:      N/A APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title): Group Owner OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                     Date         Time List pages used for Partial Performance               Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                        EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                           NNSR Revision 16 MEDICAL EMERGENCY                                                                                July 12, 2002 TABLE OF CONTENTS SECTION       TITLE                                                                                                                           PAGE 1.0           P U R P O SE .................................................................................................................. 3 2.0           PREREQ UISITES ................................................................................................                   3 3.0           PRECAUTIONS AND LIMITATIONS ..............................................................                                        5 4.0           IN ITIA L CON D ITION S .......................................................................................                   6 5.0           PR O C ED U RE ........................................................................................................           6 5.1     Slight Personal Injury/Illness ................................................................................                   6 5.2     M inor Personal Injury/Illness ................................................................................                   6 5.3     Serious Injury/Illness ............................................................................................               7 5.4     Individual Discovering the Injured/Ill Person(s) Response ...................................                                     7 5.5     Shift M anager Response. .....................................................................................                    8 5.6     Radiation Protection Supervisor, Specialist, and/or Technologist Response ......                                                  8 5.6.1 Radiation Protection Actions - Onsite ...................................................................                         8 5.6.2 Radiation Protection Actions - Offsite ................................................................                           9 5.7     Aurora Medical Center - Manitowoc County Personnel Response ...................... 10 5.8      Security O fficers Response ...................................................................................                  10 5.9      General A dm inistrative Issues ..............................................................................                   10 6.0           REFER EN C ES ...................................................................................................                11 7.0           BA SE S ...................................................................................................................... 11 ATTACHMENT A SHIFT MANAGER/REENTRY TEAM COORDINATOR ACTIONS .......                                                                            12 ATTACHMENT B RADIATION PROTECTION ACTIONS - ONSITE....................................... 13 ATTACHMENT C RADIATION PROTECTION ACTIONS - OFFSITE .....................................                                                      15 Page 2 of IS                                                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 16 MEDICAL EMERGENCY                                                    July 12, 2002 1.0   PURPOSE This procedure is to provide Point Beach Nuclear Plant personnel with guidance for the immediate care of an injured/ill person(s) requiring onsite or offsite medical assistance. Both contaminated and non-contaminated events are considered.
2.0   PREREQUISITES 2.1     Responsibilities 2.1.1      The Shift Manager (SM) is responsible for the overall command and control of the event (Reentry Team Coordinator if the OSC is activated).
2.1.2      Radiation Protection personnel are responsible for providing radiation and contamination controls at the scene, during transport to the hospital, and at the hospital.
2.1.3      The individual discovering the medical emergency is responsible for notifying the Control Room, providing treatment if qualified, and remaining at the scene to assist.
2.1.4      Personnel trained in first aid and CPR shall be immediate responders to the scene and provide treatment as appropriate.
2.1.5      The PBNP nurse is responsible for determining the equipment for the first aid room, maintaining the supply inventory, and responding to the event if onsite.
2.1.6      The SM, Industrial Health & Safety Manager, and injured/ill person(s) supervisor, group manager, or contractor supervisor are responsible for ensuring the completion of NP 1.9.2, Accident And Personal Injury Reporting; OSHA Form 200 Requirements; Industrial Safety.
2.2    Equipment 2.2.1      On-Site First Aid Provisions (EPMP 1.3)
: a. Emergency showers throughout plant - Use with a severely contaminated but less severely injured/ill person(s).
Pag~e 3 of 18                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                 EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                    NNSR Revision 16 MEDICAL EMERGENCY                                         July 12, 2002 NOTE:     IF., for emergency reasons, it is necessary to transfer first aid supplies to the Radiation Control Area, THEN the unused supplies will be retained by Radiation Protection for release to the clean side.
: b. Defibrillators
                     "* Control Room to South
                     "* Energy Center
                     "* NSB Cafeteria
                     "* RCA Checkpoint
                     "* South Gatehouse
                     "* Training Building Medical Office
: c. Burn Kits
                     "* Control Room Interior
                     "* Control Room to South
                     "* Facades [Unit 1(2) located on El. 26' and 66' outside each containment's personnel hatch]
                     "* RCA Checkpoint
                     "* Site Boundary Control Center
                     "* Switchyard
                     "* Technical Support Center
                     "* Truck Access Unit I
: d. First Aid Kits
* Control Room Interior
* Control Room to South
* Field Monitoring Team Vehicles
* Facades [Unit 1(2) located on El. 26' and 66' outside each containment's personnel hatch]
* North Gatehouse (former)
* RCA Checkpoint
* RCA Maintenance Shop
* Sewage Treatment Plant
* Site Boundary Control Center
* South Gatehouse
* Switchyard
                     "*    Technical Support Center
                     "*    Truck Access Unit 1 Page 4 of 18                            REFERENCE USE

POINT BEACH NUCLEAR PLANT                                         EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            NNSR Revision 16 MEDICAL EMERGENCY                                                 July 12, 2002
: e. Stretcher
                           "* Control Room to South
                           "* Facades [Unit 1(2) located on El. 26' and 66' outside each containment's personnel hatch]
                           "* RCA Checkpoint
                           "* South Gatehouse (long board)
                           "* Technical Support Center
                           "* Truck Access Unit 1
: f. Trauma Kit
                           "* Control Room Interior
                           "* RCA Checkpoint
                           "* RCA Maintenance Shop
* Technical Support Center 2.2.2      First aid rooms - Extension building within protected area and Training Building Medical Office 2.2.3      Radiation Protection supplies and survey instrumentation.
2.2.4      Portable FM Radios.
2.2.5      Aurora Medical Center - Manitowoc County - Fully equipped, controlled access emergency room (Reference EPMP-1.lb) 2.2.6      Letters of agreement are in existence with ambulance services, Aurora Medical Center - Manitowoc County, and trained physicians for treating contaminated, injured person(s).
3.0   PRECAUTIONS AND LIMITATIONS 3.1  Employees rendering medical assistance for serious injuries shall be first aid and/or CPR qualified.
3.2  To eliminate or minimize occupational exposure to blood and other potentially infectious body fluids, personal protective equipment shall be used.
3.3  IF the possibility exists that treatment and transportation of a patient from PBNP may be complicated by radioactive contamination, THEN a fully equipped, controlled access emergency room shall be used at Aurora Medical Center - Manitowoc County.
3.4  IF in doubt concerning the severity of an injury or illness, THEN seek the higher level of medical attention.
Page 5 of 18                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                          EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             NNSR Revision 16 MEDICAL EMERGENCY                                                   July 12, 2002 3.5    Do NOT move the injured/ill person(s) unless in an extremely high radiation area (exposures >100 rem may result in radiation sickness) OR if failure to move the person may result in a more serious injury.
3.6    IF event declared a mass casualty incident by offsite response personnel, TH-EN coordinate all efforts with the EMS Chief Officer.
4.0   INITIAL CONDITIONS An injured/ill person(s) needing medical assistance has been discovered at Point Beach Nuclear Plant, includes both protected and exclusion areas.
5.0   PROCEDURE 5.1     Slight Personal Injury/Illness Not serious, but requiring onsite medical attention (i.e., Band-aid, small cuts where bleeding has stopped, splinters, bruises).
5.1.1       Report the injury to your supervisor.
5.1.2       Seek and receive appropriate first aid.
5.1.3       Ensure proper reporting is competed per Step 5.9.
5.2    Minor Personal Injury/Illness Not serious but requiring offsite professional medical attention (i.e., larger cuts possibly requiring stitches but bleeding stopped, sprains, strains).
5.2.1       Report the injury to your supervisor.
5.2.2       IF contamination is not involved and it is between 0800 to 1700 Monday through Friday, THEN after appropriate first aid, the injured/ill will be transported, by a supervisor from the injured/ill person's group, or a person designated by the SM, to a local physician's office, or hospital, for treatment.
5.2.3      IF contamination is involved, OR it is outside normal working hours, THEN the injured/ill person(s) will be treated and transported to the Aurora Medical Center - Manitowoc County per Step 5.4.
5.2.4      Ensure proper reporting is completed per Step 5.9.
Page 6 of IS                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                        EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           NNSR Revision 16 MEDICAL EMERGENCY                                                July 12, 2002 5.3 Serious Injury/Illness Requiring offsite emergency medical transportation per Step 5.4 (i.e., trauma, heart attacks, heat stroke, unconsciousness, broken bones). The SM (Reentry Team Coordinator if OSC activated) shall ensure immediate care is provided and an ambulance is obtained for transport, radiological monitoring and control is implemented, and Security and Aurora Medical Center - Manitowoc County are apprised of the event.
5.4 Individual Discovering the Injured/Ill Person(s) Response 5.4.1        Immediately notify the Control Room at ext. 2911 and provide the following information:
: a. Nature and extent of the injury or illness
: b. Specific location of person(s)
: c. What is needed (i.e., ambulance, first aid supplies, CPR-qualified person, radiation protection personnel, etc.)
: d. Name of the person(s)
: e. Other emergency conditions present (i.e., fire, steam, etc.)
5.4.2       Perform necessary first aid to your level of training.
CAUTION DO NOT MOVE THE INJURED/ILL PERSON(s), UNLESS:
: a. The injured/ill person(s) is in an extremely high radiation field. (Be aware that exposures of 100-200 rem may result in radiation sickness and exposures in excess of -300 rem may involve the risk of fatality to 50% of those exposed if medical treatment is not provided.) (Reference Step 6.9.)
OR
: b. Failure to move the injured/ill person(s) will result in even more serious injury.
5.4.3       Remain with the individual and keep them calm, if conditions permit.
5.4.4       Brief more qualified personnel on the person(s) condition and actions taken upon their arrival.
Page 7 of 18                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                        EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           NNSR Revision 16 MEDICAL EMERGENCY                                                July 12, 2002 5.5  Shift Manager Response (Reentry Team Coordinator if OSC Activated)
Complete Attachment A, Shift Manager/Reentry Team Coordinator Actions, to ensure:
5.5.1     Injured/ill person(s) is(are) receiving medical treatment.
5.5.2     A scene leader (with radio) reports to the area for command and control of the emergency. If declared a mass casualty incident, coordinate efforts with the offsite EMS Chief Officer assigned to the scene.
: a. Identify safety equipment needed.
: b. Evaluate potential areas for setup as triage, treatment areas, equipment staging areas, etc.
5.5.3      Radiation Protection personnel are assigned to the scene if radiological concerns are present.
5.5.4      Onsite personnel and outside agencies that will provide support to the emergency are contacted.
5.5.5      Documentation and follow-up are completed per Step 5.9, including notification of the person(s) family as appropriate.
5.5.6      The need for a eight-hour report to the NRC has been assessed.
5.6  Radiation Protection Supervisor, Specialist, and/or Technologist Response 5.6.1      If requested to report to the scene for radiological monitoring, complete Attachment B, Radiation Protection Actions - Onsite, to ensure:
NOTE:        The medical care of the person(s) always takes priority over other actions (e.g., radiation protection, contamination control, area cleanup, etc.).
: a. Report to the scene with radiation monitoring instruments suitable for direct radiation readings of area and person(s).
: b. Administer first aid if qualified and not already in progress.
Page 8 of 18                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                    EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                       NNSR Revision 16 MEDICAL EMERGENCY                                            July 12, 2002
: c. Determine the magnitude of the radiological hazard (if any) and if the person(s) is contaminated.
                     "*    IF extreme radiation exposure is being received, (>100 rem may result in radiation sickness),
THEN recommend that the person(s) be moved.
                     "     IF the injured/ill person(s) is receiving significant radiation exposure (i.e., may exceed administrative limits) and cannot be moved from the field, THEN consider use of shielding to reduce exposure.
: d. Report the following information to the Control Room (or Reentry Team Coordinator in OSC, if activated):
                     "*    Injured/ill person(s) is(is not) contaminated.
                     "*    IF contaminated, THEN provide the affected areas and highest appropriate value in cpm or mRlhr.
: e. Evaluate need to issue protective clothing and dosimetry to emergency medical technicians, based upon severity of medical injuries and scene conditions.
: f. Assist in radiological control aspects of handling the person(s) until they are safely within the ambulance.
                     "*    Deconning if actions do not escalate medical condition.
                     "*    Wrapping to prevent spread of contamination and escalation of medical condition.
: g. Route several Radiation Protection personnel to the Aurora Medical Center - Manitowoc County to assist with the radiological setup prior to the arrival of the person(s). On backshift and weekends, contact RP Duty and Call Supervisor.
: h. Accompany the injured/ill person(s) in the ambulance, providing contamination control for the person(s) and ambulance personnel, IF permitted by the Emergency Medical Technicians.
5.6.2   Complete Attachment C, Radiation Protection Actions - Offsite, to ensure:
: a. Assist in the radiological setup of the hospital and personnel.
: b. Assist in the ongoing radiological monitoring and contamination control.
Page 9 of 18                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                         EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                            NNSR Revision 16 MEDICAL EMERGENCY                                                 July 12, 2002 NOTE:       As soon as possible, assure that the hospital emergency department hallways, ambulance garage, ambulance and equipment, plus facilities and equipment, have been decontaminated and released. The various areas shall be done separately from the others to expedite public access.
: c. Perform clean release surveys at the hospital and for the ambulance.
5.7  Aurora Medical Center - Manitowoc County Personnel Response 5.7.1       IF the injured/ill person(s) is not contaminated, THEN he/she will be handled by standard Aurora Medical Center Manitowoc County procedures.
5.7.2       IF the injured/ill person(s) is contaminated by radioactive material, THEN the Aurora Medical Center - Manitowoc County will implement their "Condition Alert-Nuclear" procedure to treat him/her.
5.8  Security Officers Response Upon being notified that medical response personnel (EMTs/Ambulance/Nurse) will be arriving, the security officers will:
5.8.1       Determine the desired location(s) of the ambulance, and/or responding personnel.
5.8.2       Escort the ambulance and responding personnel to desired location(s).
5.8.3       Expedite ingress/egress of the ambulance and responding personnel.
5.8.4       If declared a mass casualty incident coordinate all security efforts with the offsite Security Personnel assigned to the site.
: a. Ambulance staging areas and loading.
: b. EMS Command Post.
5.9  General Administrative Issues The SM or Reentry Team Coordinator if OSC is activated, shall perform administrative responsibilities in accordance with NP 1.9.2, Accident and Personal Injury Reporting, OSHA Form 200 Requirements; Industrial Safety. This includes ensuring that someone has notified the person(s) family if appropriate. If the OSC is activated, the completion of this step may be delegated to someone else by obtaining the TSC Manager's approval.
Page 10 of 18                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                    EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                       NNSR Revision 16 MEDICAL EMERGENCY                                            July 12, 2002

==6.0   REFERENCES==

6.1  DCS 2.1.1, Requirements and Guidance for Immediate Notification to NRC/EPA of "Significant Events" at PBNP 6.2  EP 6.0, Emergency Measures 6.3  EP 7.0, Emergency Facilities and Equipment 6.4  EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies 6.5  EPMP-1.lb, Radiation Protection - Emergency Preparedness Quarterly Checklist 6.6  HPIP 3.51, Contamination Surveys 6.7  NP 1.9.2, Accident and Personal Injury Reporting; OSHA Form 200 Requirements; Industrial Safety 6.8  NP 4.2.25, Release of Material, Equipment and Personal Items from Radiologically Controlled Areas 6.9  Regulatory Guide 8.29, Instruction Concerning Risks From Occupational Exposure, February 1996, Revision 1 6.10 Manitowoc County Emergency Medical Services Mass Casualty Response Plan 7.0   BASES B-1   10 CFR 50.47(b), Emergency Plans B-2   10 CFR 50.47, Appendix E.IV, Content of Emergency Plans PagelIl of 18                       REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                  EPIP 11.2 NNSR EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 16 July 12, 2002 MEDICAL EMERGENCY ATTACHMENT A SHIFT MANAGER/REENTRY TEAM COORDINATOR ACTIONS Initials/Time
                                                                                                          /
1.0   Ensure injured/ill person(s) is(are) receiving first aid by two trained responders.
2.0   Assign one person (with portable radio) to report as a scene leader for command and control and to keep you apprised of the event (recommend an SRO).
NOTE: If the injured/ill person(s) is in a radiation or contaminated area where contamination cannot be evaluated and cannot be moved, then assume he/she is contaminated.
3.0   Call the Manitowoc County Sheriffs Department (9-911) to request an ambulance, if needed. Provide the following information:
3.1      Number of injured/ill persons:
3.2      Nature of the injuries:
                                                                                                           /
3.3      Radiological status (circle one) Clean - Contaminated - Potentially contaminated 4.0   Contact PBNP Nurse, if onsite, to report to the scene. Provide information of the event.
5.0   Notify security if the nurse is responding and/or if an ambulance has been requested.
Advise them to escort responding personnel to the scene and of potential radiological concerns.                                                                                           /
6.0   IF radiological concerns are present, THEN assign Radiation Protection personnel to implement Attachment B of this                          /
procedure and report to the scene.
7.0  IF the injured person will be transported contaminated, call the Aurora Medical Center Manitowoc County (              )
THEN inform     them  to implement   their Condition Alert-Nuclear Procedure and update               /
them  on the person's  radiological status.
8.0   IF the injured person is contaminated, THEN notify the Manitowoc County Sheriffs Department and request the ambulance remain at the hospital until Radiation Protection personnel release the vehicle and its              /
equipment.
9.0   Contact the State at                  and advise them that a contaminated person has                 /
been transported to the hospital.
10.0  Ensure NP 1.9.2, Accident and Personal Injury Reporting; OSHA Form 200 Requirements; Industrial Safety, is completed or assigned to someone else for completion (with TSC
                                                                                                             /
Manager's approval if OSC activated), including notifying the person family as appropriate.
11.0  Assess the need for a eight-hour event report per DCS 2.1.1, Requirements and
                                                                                                             /
Guidance for Immediate Notification to NRC/EPA of "Significant Events."
ROUTE COMPLETED FORM TO EMERGENCY PREPAREDNESS Page 12 of 18                              REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 16 MEDICAL EMERGENCY                                                    July 12, 2002 ATTACHMENT B RADIATION PROTECTION ACTIONS - ONSITE Page 1 of 2 NOTE:    The medical care of the person(s) always takes priority over other actions (e.g., radiation protection, contamination control, area cleanup, etc.)
Initials/Time 1.0  Immediately report to the scene upon being contacted by the Control Room with radiation monitoring instruments suitable for direct radiation readings of area and person(s).                                                                                    /
2.0  Administer medical treatment if qualified and first aid is not already in progress.           !
3.0  Survey the injured/ill person(s) and area for radiation and contamination, documenting the highest reading on the following page.                                        I Contact the Control Room OR the Reentry Team Coordinator if the OSC is 4.0  activated, with the results of your surveys and affected areas of injured/ill person(s) and scene.                                                                          I 5.0  IF extreme radiation exposure is being received, (>100 rem may result in radiation sickness),
OR failure to move the person(s) may result in a more serious injury, THEN recommend that the person(s) be moved.                                                   /
6.0  IF the injured/ill person(s) is receiving significant radiation exposure (i.e., may exceed administrative limits) and cannot be moved from field, THEN consider use of shielding to reduce exposure.                                            /
7.0  Evaluate need to issue dosimetry and protective clothing to offsite medical response personnel, based on severity of injury and scene conditions.                         /
8.0  Assist in radiological control aspects of handling the person(s) until they are safely within the ambulance.
8.1     Deconning if actions do not escalate medical condition.                               I 8.2     Wrapping with sheet, blanket, or plastic to prevent spread of contamination if medical condition prevents deconning.                                I 9.0  Route several Radiation Protection personnel to the Aurora Medical Center Manitowoc County to implement Attachment C, assisting with the radiological setup prior to the arrival of the injured/ill person(s). On backshift and weekends, contact on call RP Duty and Call Supervisor.                                                  I 10.0 Accompany the injured/ill person(s) in the ambulance, providing contamination control for the person(s) and ambulance personnel, IF permitted by the Emergency Medical Technicians.                                                                I Page 13 of 18                            REFERENCE USE

POINT BEACH NUCLEAR PLANT                                        EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           NNSR Revision 16 MEDICAL EMERGENCY                                                July 12, 2002 ATTACHMENT B RADIATION PROTECTION ACTIONS - ONSITE Page 2 of 2 NOTE:     The medical care of the person(s) always takes priority over other actions (e.g., radiation protection, contamination control, area cleanup, etc.)
11.0  Injured/Ill Persons Name:                                              Date/Time          /
Employer:                                                 Work Group:
12.0  Results of radiological survey of scene in cpm or mR/hr:
Comments:
13.0  Indicate wounds and/or contaminated areas in cpm or mR/hr:
Comments:
14.0  Potential for internal contamination?          0 Yes         E- No Comments:
15.0  Describe actions taken to minimize the spread of contamination (i.e., decon, wrap, etc.):
ROUTE COMPLETED FORM TO EMERGENCY PREPAREDNESS Page 14 of 18                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                                       EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                          NNSR Revision 16 MEDICAL EMERGENCY                                                                                               July 12, 2002 ATTACHMENT C RADIATION PROTECTION ACTIONS - OFFSITE Page 1 of 4 NOTE 1: The attending physician's orders must be followed and ONLY the physician is in direct charge of the situation. The medical care of the person(s) always takes priority over other actions (e.g., radiation protection, contamination control, area cleanup, etc.).
NOTE 2: As soon as possible, assure that the hospital emergency department hallways, ambulance garage, ambulance and equipment, plus facilities and equipment have been decontaminated and released. The various areas shall be done separately from the others to expedite public access.
Initials/Time 1.0   Proceed  to the Aurora  Medical          Center            - Manitowoc                  County.               If   possible,    arrive before the ambulance.                                                                                                                             /
2.0   Upon arrival, identify yourself to hospital personnel and provide setup assistance with contamination boundaries, postings and controls for the ambulance garage, emergency department hallways and emergency room.
[                    -              -Reo..                                       Am.blance .f It                                :  -         A: er Patient T'a*nster IFci                                    or adiolnq cad fh Li
                                                                                              ;. Monitoring
* Wait t."Ts 'tCev    Inside. Venicle Ue~ero.1                               Sairs               Ambuance StorageI                        n -
Mach.ara.e       alevatgi
* r c:E                 Shower      .
Lounge Staff MID          R         Toilet                           ImnmeriaLely after patient ; transferrec on- all     LoaoE                              AMe      to treatinni room. oem.RPTista
                                      ""          unoe Soile           oi=  o     #9 ent -      -Hallway, Amnbulance Garage aExam 4-             A-mrMdical Ceeter -         noewc Ceuety a     Memorial Ordve nte00
                                               - -...                          .Two                            i , Wi Ri-ers
                                                                                                 . Radiologically Controlled S r....
NOTE:     If ambulance garage is unavailable, alternate route is to park in the "ambulance relocation area" northwest of the ambulance garage. A radiologically controlled area should be set up there for patient transfer and entrance via the north door of the ambulance garage.
Page 15 of 18                                                              REFERENCE USE

POINT BEACH NUCLEAR PLANT                                              EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                 NNSR Revision 16 MEDICAL EMERGENCY                                                      July 12, 2002 ATTACHMENT C RADIATION PROTECTION ACTIONS - OFFSITE Page 2 of 4 NOTE:      PBNP personnel entering the emergency room should dress in the same protective equipment being worn by the hospital staff.
Initials/Time 3.0   Issue dosimetry for hospital and plant    personnel  and  ensure they have  appropriate protective clothing.                                                                           /
4.0   Provide a radiological status of injured person to hospital personnel.                         !
5.0   Assist in maintaining radiological and contamination controls for:
5.1     Hospital personnel and equipment leaving the restricted area.                          !
5.2     Injured/ill person(s) during treatment.                                                /
6.0   Upon transfer of the injured contaminated person into the emergency room, monitor, survey, and clean release the following areas per Step 8.0.
6.1     Emergency Department hallways                                                          /
6.2     Ambulance garage                                                                       !
6.3    Ambulance and ambulance personnel                                                      /
6.4    Ambulance Relocation Area, if implemented.                                             /
7.0   Upon completion of medical treatment and transfer of the injured/ill person into another area, monitor, survey, and clean release the following areas per Step 8.0.
7.1     Medical personnel and equipment                                                        /
7.2     Emergency Room/Emergency department hallways                                           /
7.3     Other locations and equipment set up as radiological restricted areas during the treatment of the person(s)                                                  !
8.0    Survey and Clean Release Guidelines 8.1    Masslinn (treated cloth wipes) 8.1.1        For large flat surface areas, the affected area may be wiped with masslinn. All areas where there is the potential for contamination must be wiped.
8.1.2        The masslinn should be laid flat with the dirty side up for the survey.
Page 16 of 18                            REFERENCE USE

POINT BEACH NUCLEAR PLANT                                        EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           NNSR Revision 16 MEDICAL EMERGENCY                                                July 12, 2002 ATTACHMENT C RADIATION PROTECTION ACTIONS - OFFSITE Page 3 of 4 8.1.3      Count the masslinn using an open-window, pancake type probe sensitive to beta and gamma radiation. The measurement shall be made at a distance of approximately 1/2 inch and at a scan rate of less than 4 inches per second.
8.1.4       The area may be released as clean if the count rate from the masslinn is determined to be free from detectable radioactive contamination.
8.1.5       Fixed contamination levels must be < background (none detectable). (Reference NP 4.2.25) 8.2  Direct Frisk 8.2.1       Any surface area may be surveyed directly with a hand-held frisker which is sensitive to beta and gamma radiation.
8.2.2       The area may be released as clean if the count rate determined to be free from detectable radioactive contamination.
8.2.3       Fixed contamination levels must be < background (none detectable).  (Reference NP 4.2.25) 8.3   Smear Survey 8.3.1      Any surface area may be surveyed indirectly using smears and a counting instrument.
8.3.2      The standard method described in HPTP 3.51, Contamination Surveys, for obtaining, documenting, and counting smears will be followed.
Page 17 of 18                       REFERENCE USE

POINT BEACH NUCLEAR PLANT                                        EPIP 11.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                           NNSR Revision 16 MEDICAL EMERGENCY                                                July 12, 2002 ATTACHMENT C RADIATION PROTECTION ACTIONS - OFFSITE Page 4 of 4 NOTE:      Hospital staff will work with plant personnel to eliminate the biological hazard of the radioactive waste generated prior to disposal of the material as radioactive waste.
Initials/Time 9.0   Collect any protective clothing and dosimetry that may have been issued to the ambulance EMTs and complete appropriate paperwork.                                        /
                                                                                                /
10.0  Bag and properly label all disposable and non-disposable contaminated items.
11.0  Notify the Rad Waste Supervisor of waste and quantity to ensure the immediate             /
transport and proper disposal of contaminated materials.
12.0  Identify hospital and ambulance equipment which may require replacement                   /
below.
12.1 12.2 12.3 12.4 12.5 12.6 12.7 13.0  Comments
                                                                                                /
ROUTE COMPLETED FORM TO EMERGENCY PREPAREDNESS Page 18 of 18                          REFERENCE USE

EPIP 12.1 EMERGENCY EVENT DE-ESCALATION, TERMINATION,
       .OR RECOVERY OPERATIONS DOCUMENT TYPE:          Technical CLASSIFICATION:        NNSR REVISION:    8 EFFECTIVE DATE:         July 12, 2002 REVIEWER:      N/A APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                      Date         Time List pages used for Partial Performance               Controlling. Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                                  EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                                     NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                                                                July 12, 2002 OR RECOVERY OPERATIONS TABLE OF CONTENTS SECTION      TITLE                                                                                                                                    PAGE 1.0          P U R P O SE ......................................................................................................................        3 2.0          PREREQ UISITES .....................................................................................................                       3 3.0          PRECAUTIONS AND LIMITATIONS ...................................................................                                            3 4.0          INITIAL CONDITIONS ............................................................................................                            4 5.0          PR O C ED U R E .........................................................................................................                  4 5.1    Review of Classified Event Status ............................................................................                             4 5.2    Event De-E scalation ...................................................................................................                   5 5.3    Event Termination Without Recovery ........................................................................                                6 6.0   RE FER EN C ES ...........................................................................................................................        6 7 .0  B A SES ....................................................................................................................................... 7 I ATTACHMENT A              EMERGENCY CLASSIFICATION TERMINATION CRITERIA ............. 8 Pagye 2 of 8                                                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                           EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                         July 12, 2002 OR RECOVERY OPERATIONS 1.0   PURPOSE This procedure is to specify the conditions which warrant event de-escalation, event termination, or recovery implementation.
2.0   PREREQUISITES 2.1     Responsibilities 2.1.1       The Emergency Director is responsible for determining whether it is appropriate to de-escalate an event, terminate an event, or implement recovery operations.
2.1.2       The Shift Manager (SM), TSC Manager, EOF Manager and Operations Coordinator will provide input to the decision to de-escalate an event, terminate an event, or implement recovery operations.
2.2     Equipment None 3.0   PRECAUTIONS AND LIMITATIONS 3.1     This procedure should be used based on the highest classification of the event. Site Emergencies and General Emergencies will usually require a recovery phase, whereas Unusual Events or Alerts may go directly from classification to termination, if appropriate.
3.2     Major repairs and/or decontamination may be necessary to return the plant to an operating condition.
Page 3 of 8                             REFERENCE USE

POINT BEACH NUCLEAR PLANT                                          EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                             NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                        July 12, 2002 OR RECOVERY OPERATIONS 3.3    Terminating an Emergency WHEN conditions have improved where an EAL is no longer met, and it is believed that the plant is stable, i.e., the EAL is NOT anticipated to be exceeded again, THEN the emergency may be terminated WITH THE FOLLOWING CAVEATS:
3.3.1        IF Emergency Response Facilities have been activated, or personnel have been called to activate these facilities, THEN the event shall NOT be terminated until the TSC and EOF have been activated, and the TSC Manager concurs with the assessment of plant conditions.
3.3.2        IF ANY General Emergency has been declared, or ANY Protective Action Recommendation made to or by off-site authorities, THEN the emergency shall NOT be terminated until the NRC (for any General Emergency) and/or off-site authorities (for Protective Action Recommendations) concur.
4.0   INITIAL CONDITIONS 4.1   The emergency conditions at the plant have improved and the possibility exists that the event can be de-escalated or terminated.
4.2   The emergency condition no longer exists and the plant is considered in a stable, shutdown, safe condition with no possibility of conditions degrading further.
5.0   PROCEDURE 5.1   Review of Classified Event Status Review Attachment A, Emergency Classification Termination Criteria, with the SM, TSC Manager, EOF Manager, and Operations Coordinator to determine whether de-escalation, termination, or recovery operations is appropriate. (Check one of the following.)
___  De-escalation to lower classification. (Go to Step 5.2.)
___ Terminate emergency classification. (No recovery operations are necessary. Go to Step 5.3.)
Implement recovery operations. (Exit this procedure and go to EPIP 12.2, Recovery Implementation)
___  Continue current classification. (Exit this procedure and continue to monitor EPIP 1.2, Emergency Classification)
Page 4 of 8                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                      EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                    July 12, 2002 OR RECOVERY OPERATIONS 5.2 Event De-Escalation 5.2.1     Review EPIP 1.2, Emergency Classification, with the SM, TSC Manager, EOF Manager and Operations Coordinator.
Evaluate plant and release conditions to ensure the event may be reclassified to a lower emergency classification.
Current Classification           New Classification            Time NOTE:    No PARs should be required if the release is terminated or below Tech Specs.
5.2.2    Complete EPIP 2.1, Attachment B, Nuclear Accident Reporting Form.
5.2.3    Direct the offsite communicator to complete EPIP 2.1, Section 5.2, Notifications to State and Counties (within 15 minutes of declaration).
5.2.4    Ensure personnel in all Emergency Response Facilities are aware of new classification.
5.2.5    Direct the SM to notify on-site personnel per EPIP 1.1, Course of Actions, Attachment A.
5.2.6    Ensure EPIP 2.1, Section 5.4, Notifications to the NRC, have been completed (immediately following offsite notifications, NOT to exceed 60 minutes from declaration).
5.2.7     Ensure follow-up communications, as necessary, are being completed:
: a. EPIP 2.1, Section 5.5, Status Updates to the State and Counties
: b. EPIP 2.1, Section 5.6, Status Updates to the NRC 5.2.8     Continue to review this procedure until event termination or recovery operations are implemented.
Page 5 of 8                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                      EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                     July 12, 2002 OR RECOVERY OPERATIONS 5.3  Event Termination Without Recovery 5.3.1      Discuss the following with the SM, TSC Manager, EOF Manager, and Operations Coordinator:
: a. The need for long-term cleanup or recovery operations is NOT necessary.
: b. Current conditions do NOT meet any of the emergency action levels listed in EPIP 1.2, Emergency Classifications.
Current Classification              Terminated at:
5.3.2      Complete EPIP 2.1, Attachment B, Nuclear Accident Reporting Form.
5.3.3      Direct the offsite communicator to complete EPIP 2.1, Section 5.2, Notifications to State and Counties (within 15 minutes of declaration).
5.3.4      Ensure personnel in all Emergency Response Facilities are aware of termination.
5.3.5      Direct the SM to notify on-site personnel per EPIP 1.1, Course of Actions, Attachment A.
5.3.6      Ensure EPIP 2.1, Section 5.4, Notifications to the NRC, have been completed (immediate following offsite notifications, NOT to exceed 60 minutes from declaration).
5.3.7      Direct all Emergency Response Facility personnel to complete the termination section of their Position Instruction Manuals.

==6.0   REFERENCES==

6.1  EP 4.0, Emergency Conditions 6.2  EP 9.0, Recovery 6.3  EPIP 1.1, Course of Actions 6.4  EPIP 1.2, Emergency Classification 6.5  EPIP 2.1, Notifications - ERO, State & Counties, and NRC 6.6  EPIP 12.2, Recovery Implementation 6.7  IR 90-017, dated 08/20/90, NRC Announced Emergency Preparedness Inspection, Section 3, "Emergency Plan Activations" Page 6 of 8                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                      EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                         NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                    July 12, 2002 OR RECOVERY OPERATIONS 6.8  NP 1.8.2, Event Emergency Response Report 6.9  NP 5.3.3, Incident Investigation and Post-Trip Review 6.10 RCM 96, NRC Response Coordination Manual 6.11 RTM 96, NRC Response Technical Manual 7.0   BASES B-1   10 CFR 50.47(b), Emergency Plans B-2   10 CFR 50.47, Appendix E.IV, Content of Emergency Plans Page 7 of 8                      REFERENCE USE

POINT BEACH NUCLEAR PLANT                                                                 EPIP 12.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                    NNSR Revision 8 EMERGENCY EVENT DE-ESCALATION, TERMINATION,                                               July 12, 2002 OR RECOVERY OPERATIONS ATTACHMENT A EMERGENCY CLASSIFICATION TERMINATION CRITERIA S    Start Implement Recovery Operations Requirements                      Per EPIP 12.2 Damage Occurred?                        of Table 1              (Termination of emergency Satisfied?                    classification done within that procedure)
No         >"No Long-Tr                      Continue Current Cleanup or      "b-J        Classification (Until Recovery niiae                      Recovery     Can Be Declared)
No                                                                           Table 1 The reactor and associated systems Conditions        Yes       Continue Current                are in a safe, stable, and shutdown condition, Current Claswith YfsoConinu                                       no likelihood that the initial emergency Classification Sti                                              situation will recur or that further plant "Exist?                  (Monitor EPIP 1.2)               degradation will develop.
_       Long-term core cooling has been No                                                   established.
___No          further potential exists for uncontrolled releases of radioactive materials to Sthe environment.
for Lower                    Classification                            Release of radioactive materials has Classification Exist?                  (EPIP 12.1, Step 5.2)             ceased or is within TS limits.
Containment pressure is steady or decreasing as expected.
Any fire, flooding, earthquake, or similar emergency condition is controlled or has STerminate                      Emergency              ceased.
Rquireme             Y          Classification                           All initial or previous emergency of Table 1                   Without Recovery                 notifications have been completed.
d(EPIP               12.1, Step 5.3)                       Full activation of the Emergency Response Organization or Emergency Response No                                                   Facilities is no longer required.
                                                                         ,_          NRC concurs with the decision to Continue Current                                                 terminate (G.E.) (EPIP 1.2).
Classification   (Monitoi Table 1 and/or                                                             State & Counties concur with the EPIP 1.2 as                                                   decision to terminate (any PARs implemented)
Appropriate)                                                   (EPIP 1.2).
Ifnecessary, Reference EP 4.0, Table 4-1 Page 8 of 8                                               REFERENCE USE

EPIP 12.2 RECOVERY IMPLEMENTATION DOCUMENT TYPE: Technical CLASSIFICATION:        NNSR REVISION:     14 EFFECTIVE DATE:         July 12, 2002 REVIEWER:      N/A APPROVAL AUTHORITY:             Department Manager PROCEDURE OWNER (title):          Group Head OWNER GROUP:        Emergency Preparedness Verified Current Copy:
Signature                     Date         Time List pages used for Partial Performance               Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT                                                                          EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                                                             NNSR Revision 14 RECOVERY IMPLEMENTATION                                                                            July 12, 2002 TABLE OF CONTENTS SECTION   TITLE                                                                                                                                  PAGE 1.0       PU R P O SE ......................................................................................................................       3 2.0       PRERE Q U ISITE S.....................................................................................................                   3 3.0       PRECAUTIONS AND LIMITATIONS ..................................................................                                           3 4.0       IN ITIA L C ON D ITIO N S ............................................................................................                   3 5.0       PR O C ED U R E .........................................................................................................                4 5.1 Terminate Event Classification With Recovery ........................................................                                    4 5.2 Implement Recovery Operations ...............................................................................                            4 5.3 R ecovery Term ination ...............................................................................................                   6 6.0       REFE R EN C E S .....................................            I.................................................................... 6 7 .0      B A SE S ........................................................................................................................... 6 ATTACHMENT A      PROPOSED RECOVERY ORGANIZATION AND RESPO N SIB ILIT IES .....................................................................................                       7 ATTACHMENT B      RECOVERY PLAN ACTION ITEMS ..........................................................                                            10 ATTACHMENT C      RECOVERY PLAN ACTION ITEM ASSIGNMENTS ...............................                                                            12 Page 2 of 12                                                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                           EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              NNSR Revision 14 RECOVERY IMPLEMENTATION                                             July 12, 2002 1.0  PURPOSE This procedure provides guidance for entering the recovery phase, establishing a recovery plan, restoring the plant to a normal operating status, and terminating recovery efforts.
The goals of the recovery effort are to assess the in-plant consequences of the emergency, assist the State of Wisconsin with the intermediate and ingestion phase radiological operations, and initiate plant cleanup and repair operations.
2.0   PREREQUISITES 2.1      Responsibilities 2.1.1      The Emergency Director is responsible for the oversight of the recovery organization and recovery operations.
2.1.2      The TSC Manager, Rad/Chem Coordinator, Dose/PAR Coordinator, Operations Coordinator, Engineering Coordinator, EOF Manager, JPIC Manager, and Resource Coordinator have various responsibilities for the recovery operations per Attachment A, Proposed Recovery Organization and Responsibilities.
2.2      Equipment None 3.0   PRECAUTIONS AND LIMITATIONS Recovery operations may NOT be terminated until the PBNP Recovery Organization, under the direction of the Emergency Director, and the NRC agree that the plant can be maintained within Technical Specifications.
4.0   INITIAL CONDITIONS Completion of EPIP 12.1, Emergency Event De-Escalation, Termination, or Recovery Operations, indicates that implementing recovery operations is appropriate.
Page 3 of 12                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                     EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                        NNSR Revision 14 RECOVERY IMPLEMENTATION                                       July 12, 2002 5.0  PROCEDURE 5.1 Terminate Event Classification With Recovery 5.1.1    Current Classification                   Terminated at:
5.1.2     Complete EPIP 2.1, Attachment B, Nuclear Accident Reporting Form, indicating on the form that we will be terminating and implementing recovery actions.
5.1.3     Direct the offsite communicator to complete EPIP 2.1, Section 5.2, Notifications to State and Counties (within 15 minutes of declaration).
5.1.4     Ensure personnel in all Emergency Response Facilities are aware of termination.
5.1.5     Direct the Shift Manager (SM) to notify on-site personnel per EPIP 1.1, Course of Actions, Attachment A.
5.1.6     Ensure EPIP 2.1, Section 5.4, Notifications to the NRC, have been completed (immediately following offsite notifications, NOT to exceed 60 minutes from declaration).
5.2 Implement Recovery Operations 5.2.1     Ensure personnel in all Emergency Response Facilities are aware that the event has been de-escalated and/or recovery operations are being implemented.
5.2.2     Review EP 9.0, Recovery.
NOTE:     Some of the following steps may have been completed as part of the emergency response phase.
5.2.3     Establish a recovery organization, per Attachment A, appropriate for the existing onsite and offsite conditions.
The recovery organization should consist of personnel capable of ensuring:
: a. Assessment of onsite and offsite radiological conditions.
: b. Assessment of plant operating conditions (affected and non-affected unit).
: c. Development of reentry and recovery work plans and schedules.
: d. Communications with offsite agencies.
Page 4 of 12                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                   EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                      NNSR Revision 14 RECOVERY IMPLEMENTATION                                     July 12, 2002 5.2.4   Establish an Incident Investigation Team (TSC Manager). This team will:
: a. Gather available evidence on contributing factors.
: b. Identify all causal factors.
: c. Ensure all abnormal conditions are corrected or neutralized.
5.2.5   Complete the following prior to developing recovery reentry plans:
NOTE:       Reference EPIP 10.1, Emergency Reentry, for guidance in preparing and deploying recovery reentry teams.
: a. Conduct comprehensive survey of site facilities and define all radiological problem areas.
: b. Isolate and post all radiation or contamination areas using appropriate Radiation Protection guidelines.
: c. Perform visual inspection of site areas and equipment noting any areas/equipment requiring cleanup or repair.
5.2.6   Assemble recovery managers (or designees) to develop initial Recovery Plans.
NOTE:       Following an emergency, all failed equipment NOT necessary for safe shutdown and all records are to be quarantined pending an NRC investigation.
: a. Review Attachment B, Recovery Plan Action Items.
: b. Assign action items to the appropriate group(s) for completion, completing Attachment C, Recovery Plan Action Item Assignments.
: c. Ensure the group(s) review EPIP 10.1, Emergency Reentry, for items to consider for inclusion in work plans or procedures for recovery operations.
Pagre 5 of 12                          REFERENCE USE

POINT BEACH NUCLEAR PLANT                                       EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                          NNSR Revision 14 RECOVERY IMPLEMENTATION                                         July 12, 2002 NOTE:      The recovery plan may be similar to an outage work plan; consider using the outage planning group to support recovery planning.
5.2.7      Ensure the development of a comprehensive recovery plan which includes all work orders, modifications, etc., that need to be completed.
5.2.8      Implement the comprehensive recovery plan action items determined in Step 5.2.6 and Step 5.2.7.
5.2.9      Reconvene the recovery managers (or designees) to review and revise the recovery plan as appropriate until the recovery phase is complete.
5.3  Recovery Termination 5.3.1      Recovery operations may be terminated when the PBNP Recovery Organization, under the direction of the Emergency Director, and the NRC agree that the plant can be maintained within Technical Specifications.
5.3.2      Verify all Emergency Response Facilities are restored to a state of readiness prior to leaving facilities.

==6.0   REFERENCES==

6.1  EP 9.0, Recovery 6.2  EPIP 1.1, Course of Actions 6.3  EPIP 2.1, Notifications - ERO, State & Counties, and NRC 6.4  EPIP 10.1, Emergency Reentry 6.5  EPIP 12.1, Emergency Event De-Escalation, Termination, or Recovery Operations 6.6  RCM 96, NRC Response Coordination Manual 6.7  RTM 96, NRC Response Technical Manual 7.0   BASES B-1   10 CFR 50.47(b), Emergency Plans B-2   10 CFR 50.47, Appendix E.IV, Content of Emergency Plans Page 6 of 12                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                           EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              NNSR Revision 14 RECOVERY IMPLEMENTATION                                             July 12, 2002 ATTACHMENT A PROPOSED RECOVERY ORGANIZATION AND RESPONSIBILITIES Page 1 of 3 Emergency Director
* Ensures completion of this procedure.
* Determines positions and assigns personnel necessary for recovery organization.
* Determines which facilities will be required for recovery operations (TSC, OSC, EOF, etc.).
* Ensures facilities NOT required for recovery operations are closed and returned to a ready state.
* Manages interface with NRC Site Team.
TSC Manager
"* Oversees implementation of site recovery operations.
"* Establishes an onsite personnel schedule sufficient to meet the immediate needs of the recovery organization.
"* Ensures all activities, proposed courses of action, and contingency plans receive proper analysis and coordination.
"* Ensures plant security and plant access is maintained in accordance with Security Plan.
"* Establishes an Incident Investigation Team.
Page 7 of 12                           REFERENCE USE

POINT BEACH NUCLEAR PLANT                                            EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 14 RECOVERY IMPLEMENTATION                                              July 12, 2002 ATTACHMENT A PROPOSED RECOVERY ORGANIZATION AND RESPONSIBILITIES Page 2 of 3 Radiological Assessment (Dose/PAR Coordinator for Offsite and Rad!Chem Coordinator for Onsite)
"* Coordinates post-accident offsite sampling and analysis program in support of onsite and offsite recovery activities.
"* Maintains contact with federal, state, and local agencies regarding environmental sample results and coordinates additional sampling.
"* Calculates population dose, if applicable.
"* Provides recommendations regarding public protective actions.
"* Coordinates dose management and radiation protection for WE employees involved in recovery activities.
"* Develops plans and procedures to process and control liquid, gaseous and solid wastes generates as a result of the emergency and/or recovery activities.
Operational Assessment (Operations Coordinator)
"*  Continues to manage plant operations.
"*  Determines priorities for repair work.
"*  Conducts assessment of plant equipment and systems.
"*  Ensures procedures and work plans are written for all required recovery activities.
Engineering Assessment (Engineering Coordinator)
"* Develops engineering plans and schedules for performance of recovery activities.
"* Directs and coordinates engineering, design, and construction activities required for recovery operations.
"* Ensures appropriate administrative controls are completed, i.e., 50.59s, MRs, WOs, etc.
"* Coordinates engineering functions with the Quality Assurance section.
* Coordinates activities of the NSS Supplier, the architect-engineer, various contractor forces, and other individuals and/or consultants.
EOF Manager
"*  Coordinates release of information with local, state, and federal agencies.
"*  Establishes and maintains communications with offsite agencies.
 "* Acts as liaison between WE and offsite agencies.
 "* Acts as liaison between WE and NRC Site Team and/or Augmented Inspection Team.
 "* Ensures appropriate personnel are interfacing with NRC Site Team.
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POINT BEACH NUCLEAR PLANT                                            EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 14 RECOVERY IMPLEMENTATION                                              July 12, 2002 ATTACHMENT A PROPOSED RECOVERY ORGANIZATION AND RESPONSIBILITIES Page 3 of 3 Offsite Communications (JPIC Manager)
"* Manages all public information activities relative to recovery operations.
"* Determines equipment and facility needs for the JPIC. Coordinates acquisition with Resource Coordinator.
Administrative and Resources (Resource Coordinator)
"* Implements the personnel schedules developed for all facilities based upon the anticipated duration of recovery operations.
"* Provides for acquisition of materials and services as necessary for recovery operations.
"* Provides for personnel necessities onsite, i.e., food and refreshments.
"* Provides for personnel necessities for offsite and government agencies, i.e., communications, office supplies, office space, etc.
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POINT BEACH NUCLEAR PLANT                                            EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                               NNSR Revision 14 RECOVERY IMPLEMENTATION                                              July 12, 2002 ATTACHMENT B RECOVERY PLAN ACTION ITEMS Page 1 of 2 NOTE:        Following an emergency, all failed equipment NOT necessary for safe shutdown and all records are to be quarantined pending an NRC investigation.
Perform assessments in the following areas and identify potential short-term and long-term recovery action items.
: 1. Current operational status of plant systems and equipment involved in the emergency.
: 2. Current operational status of the unaffected unit and its effect on the affected unit.
: 3. Identification of all systems, components, or equipment damaged or made inoperable.
: 4. Estimate of necessary repairs, parts and special tools to restore all affected systems and equipment back to fully-operational state.
: 5. Estimate of additional personnel resources that may be required during the restoration period and any specialized training that may be necessary.
: 6. Identification of 50.59 reviews necessary for unaffected unit.
: 7. Identification of applicable plant surveillance tests and procedures to restore plant systems to normal operational or shutdown configuration.
: 8. Identification of applicable system operability tests and procedures to restore plant systems to normal operational or shutdown configuration.
: 9. Estimate of liquid and solid radioactive waste generated during the event and recommendations on management and disposal.
: 10. Identification of special radiological considerations for personnel entry into affected areas with elevated dose rates or contamination levels (i.e., temporary shielding, engineering evaluations, robotics, etc.)
: 11. Estimate of the decontamination and monitoring activities necessary to restore affected areas inside and outside the plant site to pre-accident levels.
: 12. Identification of continued offsite radiological sampling and potential assistance to state or local agencies in the area of sampling, monitoring, and decontamination.
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POINT BEACH NUCLEAR PLANT                                           EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                              NNSR Revision 14 RECOVERY IMPLEMENTATION                                             July 12, 2002 ATTACHMENT B RECOVERY PLAN ACTION ITEMS Page 2 of 2
: 13. Identification of methodology for continuing coordination with government agencies and media.
: 14. Identification of incident investigation team.
: 15. Evaluation of controlled releases that may result from recovery operations.
: 16. Assessment of long-term Security requirements.
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POINT BEACH NUCLEAR PLANT                                  EPIP 12.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES                     NNSR Revision 14 RECOVERY IMPLEMENTATION                                    July 12, 2002 ATTACHMENT C RECOVERY PLAN ACTION ITEM ASSIGNMENTS Page __   of 41
__________-             ____-___________                            -           {7
___         I Emergency Director Approval:                             Date              Time Return this completed Attachment to Emergency Preparedness.
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