Text

Final As-Administered Administrative Jpms for the Kewaunee Initial Examination - November 2005
	ML060830331
Person / Time
Site:	Kewaunee
Issue date:	11/14/2005
From:	Palagi B; NRC/RGN-III/DRS/OLB
To:	;
References
	50-305/05-301 50-305/05-301
	Download: ML060830331 (126)
	v • d • e

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 1 of 16 Reviewed By Bart Steckler Approved By Tom Schmidli Nuclear Yes PORC ; Yes SRO Approval Of ; Yes Safety Review Temporary Related ; No Required No Changes Required No 1.0 Plant Initial Conditions 1.1 This procedure is used, in conjunction with Procedure HP-01.012, RETSCODE Computer Program Operating Guide, to generate radioactive gaseous effluents release reports for batch releases from the Kewaunee Nuclear Power Plant (KNPP). It quantifies radioactive gaseous effluents for batch releases from the following locations:

Waste Gas Decay Tanks (WGDT)

Containment Building Purge, which is defined as the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Reactor Building Vent (RBV) System operation after reactor plant shutdown.

Power Operated Relief Valves (PORV), during periods of primary-to-secondary leakage.

1.2 This procedure is performed under all plant conditions.

Note For other batch releases, refer to Procedure HP-05.015, Miscellaneous Gaseous Radwaste Releases.

2.0 Precautions 2.1 A WGDT having a total noble gas activity concentration exceeding 1.0E-02 µCi/cc, shall NOT be released until evaluations listed in Gas Decay Tank Prerelease Evaluation, Attachment A, are completed.

2.2 Both trains of the Auxiliary Building Ventilation (ABV) System shall be in operation during the release of a WGDT exceeding 1.0E-02 µCi/cc total gas activity concentration.

2.3 A WGDT having a total noble gas activity concentration exceeding 1.0E-01 µCi/cc, shall be placed on hold for decay prior to release.

sp-32b-116 documentation.docMichael W. Ahearn/Amy KudickMichael W. Ahearn REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 2 of 16 2.4 A WGDT may contain explosive levels of hydrogen, therefore:

2.4.1 Samples should NOT be taken using a RAP pump. These pumps are NOT designed for use in an explosive atmosphere. See Procedure HP-06.063, Instrument Operating Procedure - Air Sample Pumps: RAS-1, RAP-1, RAP-1Q, and RAP-3.

2.4.2 Silver Zeolite sample cartridges should NOT be used when sampling a WGDT. A reaction may occur within the cartridge causing a rapid increase in temperature and possibly an explosion. See OEA 86-52.

2.5 IF during an outage, the RBV system is OOS for less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , THEN no discharge permit is required to restart containment vent.

2.6 IF noble gases are identified from samples being analyzed for effluent releases, THEN the Iodine sample cartridge should be purged with air for at least 5 minutes. This is done to remove noble gases entrapped in the cartridge so they are NOT misidentified as Iodine peaks.

2.7 For non-routine batch discharges (e.g., CVCS hold up tanks) NOT included in this procedure, contact RP supervision for specific work instructions. [PCR 8891]

3.0 Limiting Conditions for Operation 3.1 For actions to be taken if any gaseous effluent radiation monitors are out of service refer to the ODCM, Table 3.2 or SP-45-290, Radioactive Gaseous Effluent Monitoring Instrumentation, Compensatory Actions for Channels Out of Service.

3.2 IF site-boundary dose estimates exceed the limits stated in SP-32B-268, Site Boundary Doses from Gaseous Effluents, THEN the Gaseous Radwaste Treatment System or the Ventilation Exhaust Treatment System, whichever is applicable, shall be used.

4.0 General Instructions 4.1 Description 4.1.1 The RETSCODE Computer Program is used to calculate the gaseous activity released to the environment and the dose rates at the site boundary. IF the RETSCODE Computer Program is unavailable, THEN manual calculations are required.

4.1.2 Gaseous effluent monitor setpoints are determined in accordance with ODCM methodology so they will alarm and automatically terminate a release prior to exceeding site boundary dose rates based on values from 10CFR20, Appendix B, Table II, Column 1. Generally, these alarm/trip setpoints are conservatively set.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 3 of 16 4.1.3 Procedure HP-05.004, Radiation/Contamination Survey and Airborne Radioactivity Sampling Schedules, contains the sampling requirements for the WGDTs.

4.1.4 Sample results from the R-11/12 sample point are used for containment purge batch releases. See procedure HP-05.004.

4.1.5 Sample results from the Air Ejector gas sample point and Steam Generator Blowdown point are used for PORV releases. See procedure HP-05.004 for air ejector samples and contact chemistry for blowdown results.

Note Steam releases through the PORVs can NOT be sampled directly. Therefore, controlled plant cool downs performed by dumping steam to the atmosphere through the PORVs must be quantified indirectly.

Iodine concentrations may be reduced by a factor of 10 in the Pre-release Dose Estimate per USAR, Section 10.2.

4.2 Definitions 4.2.1 Off-site Dose Calculation Manual (ODCM) - A document that contains the current methodology and parameters used in the calculation of off-site doses and alarm/trip setpoints for radioactive gaseous and liquid effluents.

4.2.2 Gaseous Radwaste Treatment System - A system used to reduce the radioactivity of gaseous effluents by collecting off-gases from the reactor coolant system and holding them for decay prior to release to the environment, i.e., WGDTs.

4.2.3 Ventilation Exhaust Treatment System - A system used to reduce radioactive Iodine and particulate effluents through the use of charcoal absorbers and/or HEPA filters prior to release to the environment, i.e., Containment Purge Exhaust Filter.

4.2.4 Engineered Safety Feature (ESF) Systems - These are considered atmospheric cleanup systems, which include:

Auxiliary Building Special Ventilation (ASV)

Shield Building Ventilation System (SBV)

Spent Fuel Pool Ventilation System (part of the Auxiliary Ventilation System)

These systems are NOT considered to be Ventilation Exhaust Treatment Systems.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 4 of 16 4.2.5 Purge - The controlled process of discharging air or gas from a compartment to maintain temperature, pressure, humidity, concentration, or any other operating condition in such a manner that replacement air or gas is required.

4.2.6 Vent - The controlled process of discharging air or gas such that replacement air or gas is NOT provided or required.

5.0 Equipment Required 5.1 Personal computer loaded with RETSCODE software.

6.0 Procedure Note For non-routine batch discharges Attachment E, Gas Decay Tank Discharge Permit, may be used to document the release. Contact RP supervision for specific work instructions. [CAP 12763]

6.1 WGDT Note Pre-release sampling is required for WGDTs.

6.1.1 Sample the tank to be discharged per HP-05.004.

6.1.1.1 IF noble gases are identified, THEN purge the Iodine sample cartridge with air for at least 5 minutes.

Note A WGDT having a total noble gas activity concentration exceeding 1.0E-01 µCi/cc shall be placed on hold for decay prior to release.

6.1.2 Analyze the sample per HP-05.001, Survey and Sampling Techniques.

6.1.3 Complete Attachment A if the total noble gas specific activity concentration exceeds 1.0E-02 µCi/cc. [PCR 12651]

6.1.4 Enter the sample results into the RETSCODE Computer Program using HP-01.012, RETSCODE Computer Program Operating Guide.

6.1.5 Complete Attachment B, Pre-release Dose Estimate.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 5 of 16 6.1.6 Review Attachment B to ensure no Technical Specification (TS) limits will be exceeded for the release:

6.1.6.1 IF TS limits are NOT exceeded, THEN continue with the release.

6.1.6.2 IF TS limits are exceeded, THEN contact RP Supervision.

6.1.7 Complete the upper portion of Attachment E, attach the sample results and Attachment B, and Attachment A, if applicable. Sign all forms where applicable.

6.1.8 Route the discharge permit to RP Supervision for signature and review.

6.1.9 Route the discharge permit to the Shift Manager for disposition of the WGDT.

6.1.10 Upon receiving the discharge permit back from operations, verify PRIOR TO DISCHARGE and END OF RELEASE data has been completed.

6.1.11 Enter post-release data into the RETSCODE program using HP-01.012.

6.1.12 Complete Attachment C, Post-Discharge Summary Sheet, and sign the form.

6.1.13 Initial near the bottom of Attachment E upon completing all post-discharge data and the Post-Discharge Summary Sheet.

6.1.14 Route to RP Supervision for signatures and subsequent routing to the KNPP QA Vault.

6.2 Containment Building Purge Note Pre-release sampling is required for Containment Building Purge.

6.2.1 Sample the Containment Building per HP-05.004.

6.2.2 Analyze the sample per HP-05.001.

6.2.2.1 IF noble gases are identified, THEN purge the Iodine sample cartridge with air for at least 5 minutes.

6.2.3 Enter the sample results into the RETSCODE Computer Program using HP-01.012.

6.2.4 Complete Attachment B.

6.2.5 Review Attachment B to verify no TS limits shall be exceeded for the release:

6.2.5.1 IF TS limits are NOT exceeded, THEN continue with the release.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 6 of 16 6.2.5.2 IF TS limits are exceeded, THEN contact RP Supervision.

6.2.6 Complete the upper portion of Attachment D, attach the sample results and Attachment B. Sign all forms where applicable.

6.2.7 Route the discharge permit to RP Supervision for signature and review.

6.2.8 Route the discharge permit to the Shift Manager for disposition of the permit.

Note Containment is sampled every hour for radioactive gases after the release is started until gaseous isotopes are no longer identified. This is done to allow for a more accurate quantification of activity being released to the environment.

6.2.9 Upon receiving the discharge permit back from Operations, verify PRIOR TO DISCHARGE and END OF RELEASE data has been completed.

6.2.10 Calculate the post-release volume by multiplying the containment fan flow by the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months run time for the purge.

6.2.11 Enter post-release data into the RETSCODE program using HP-01.012.

6.2.12 Complete Attachment C and sign the form.

6.2.13 Initial near the bottom of Attachment D upon completing all post-discharge data and Attachment C.

6.2.14 Route to RP Supervision for signatures and subsequent routing to the KNPP QA Vault.

6.3 PORV Release with Primary-to-Secondary Leakage Note Steam releases through the PORVs can NOT be sampled directly. Therefore, controlled plant cool downs performed by dumping steam to the atmosphere through the PORVs must be quantified indirectly.

6.3.1 Obtain a copy of the latest air ejector gas sample results and the latest Steam Generator (SG) blowdown sample results.

Note Iodine concentrations may be reduced by a factor of 10 in the Pre-release Dose Estimate in accordance with USAR, Section 10.2.

6.3.2 Enter the sample results into the RETSCODE Computer Program using HP-01.012.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 7 of 16 6.3.3 Determine the estimated PORV steam release volume:

6.3.3.1 Access file J:\AppData\rxeng\STMRLS.EXE 6.3.3.2 Enter Y to answer the first question.

6.3.3.3 Enter SG pressure in psig for the SG to be used for cool down.

6.3.3.4 Enter 1 for PORV release.

6.3.3.5 Steam release rate is given in cc/sec. Multiply this value by the estimated release time in seconds to get the release volume in ccs.

6.3.3.6 Exit the STMRLS program by entering N.

6.3.4 Enter estimated release volume into the RETSCODE program.

6.3.4.1 IF the calculated activity could cause the site boundary dose limits to be exceeded, in accordance with SP-32B-268, THEN, if possible, the duration of the release should be shortened.

6.3.5 Complete Attachment B.

6.3.6 Review Attachment B to verify no TS limits will be exceeded for the release:

6.3.6.1 IF TS limits are NOT exceeded, THEN continue with the release.

6.3.6.2 IF TS limits are exceeded, THEN contact RP Supervision.

6.3.7 Complete the upper portion of Attachment F, attach the sample results and Attachment B. Sign all forms where applicable.

6.3.8 Route the discharge permit to RP Supervision for signature and review.

6.3.9 Route the discharge permit to the Shift Manager for disposition.

Note Since a release from a PORV is NOT monitored during the release, consider taking a field sample down wind of the PORV at the site boundary to assist in verifying the activity released.

6.3.10 Upon receiving the discharge permit back from operations, verify PRIOR TO DISCHARGE and END OF RELEASE data has been completed.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 8 of 16 6.3.11 Enter post-release data into the RETSCODE program using HP-01.012.

6.3.12 Complete Attachment C and sign the form.

6.3.13 Initial near the bottom of Attachment F upon completing all post-discharge data and Attachment C.

6.3.14 Route to RP Supervision for signatures and subsequent routing to the KNPP QA Vault.

6.4 Manual Generation of Batch Release Reports 6.4.1 Obtain the applicable hard copy sample cover sheets and pre-release sheets contained in this procedure.

6.4.2 Enter the sample results onto the applicable sample cover sheet.

6.4.3 Complete any necessary attachments required by this procedure based on sample results.

6.4.4 Calculate the volume for the applicable sample as follows:

a. WGDT

1. Pre-release and post-release volumes are calculated as follows:

([Tank pressure in psig + 14.7 psia] ÷ 14.7 psia)x(1.33 E+7 cc)=Tank volume in ccs

b. Containment Building Purge

1. Based on elimination of airborne radioactivity in containment after five air changes with a fan flow rate of 33,000 cfm and containment volume of 1.32 E+6 ft3, the pre-release volume would be 1.87 E+11 ccs.

2. Post-release volume is calculated per Step 6.2.10 of this procedure.

c. PORV

1. PORV volumes are calculated per Step 6.3.3 of this procedure.

6.4.5 Enter the volume onto Attachment B.

6.4.6 Complete the rest of the Attachment B.

6.4.7 Assign the next discharge permit number to the release paperwork.

6.4.8 Attach sample results and Attachment B to the applicable sample cover sheet. Sign all forms where applicable.

REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 9 of 16 6.4.9 Route the discharge permit to RP Supervision for signature and review.

6.4.10 Route the discharge permit to the Shift Manager for disposition of the permit.

6.4.11 Upon receiving the discharge permit back from Operations, verify PRIOR TO DISCHARGE and END OF RELEASE that data has been completed.

6.4.12 Calculate post-release data and then complete Attachment C and sign the form.

6.4.13 Initial near the bottom of the applicable sample cover sheet upon completing all post-discharge data and Attachment C.

Note The discharge data should be entered in the RETSCODE Computer Program as soon as the system is back in service.

6.4.14 Route to RP Supervision for signatures and subsequent routing to the KNPP QA Vault.

7.0 Problems 7.1 Complete an Action Request (AR) Form, NMC FP-PA-ARP-1, to document and assess for any problems encountered during the performance of this procedure.

8.0 Acceptance Criteria 8.1 This procedure is considered complete and acceptable when the batch release has been completed and none of the following limits have been exceeded:

8.1.1 Dose Rate, per ODCM Specification 3.4.1 8.1.2 Dose - Noble Gases, per ODCM Specification 3.4.2 8.1.3 Dose - Iodine-131, Iodine-133, and radionuclides in particulate form, per ODCM Specification 3.4.3 REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 10 of 16 9.0 References 9.1 HP-01.012, RETSCODE Computer Program Operating Guide 9.2 HP-05.015, Miscellaneous Gaseous Radwaste Releases 9.3 HP-06.063, Instrument Operating Procedure - Air Sample Pumps: RAS-1, RAP-1, RAP-1Q, and RAP-3.

9.4 OEA No. 86-52, Off-Gas Hydrogen Explosion While Sampling 9.5 PCR8891, Guidance for non-routine batch discharges 9.6 ODCM, Offsite Dose Calculation Manual 9.7 SP-32B-268, Site Boundary Doses from Gaseous Effluents 9.8 SP-45-290, Radioactive Gaseous Effluent Monitoring Instrumentation, Compensatory Actions for Channels 0ut of Service 9.9 10CFR20, Appendix B, Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure 9.10 HP-05.004, Radiation/Contamination Survey and Airborne Radioactivity Sampling Schedules 9.11 USAR, Section 10.2 9.12 HP-05.001, Survey and Sampling Techniques 9.13 NMC FP-PA-ARP-01, Action Request Process 9.14 COMTRAK 89-078 (LER 89-003), Committed to the USNRC to provide operators with valve settings during WGDT releases to prevent automatic actuation of ASV System due to R-13/R-14 alarm 9.15 COMTRAK 89-207, Committed to INPO to establishing methods for determining Iodine release from S/G PORVs during periods of pri-sec leakage 9.16 CAP 1403, Nitrogen Purging of Waste Gas Decay Tanks 9.17 PCR 12651, Resolve inconsistency between SP-32B-116 Attachment E and N-GWP-32B REFERENCE USE

GAS DECAY TANK PRERELEASE EVALUATION DISCHARGE PERMIT 05-XXXXX Complete this attachment when sample results of a gas decay tank indicate total gas activity greater than 1.0E-2 µCi/cc.

TANK NO. A DATE/TIME SAMPLED __11-16-05_/ 0320___________

TOTAL GAS ACTIVITY 1.71E-02 µCi/cc

1. Will this tank be put on hold for decay prior to release? YES / NO

2. IF YES, THEN how long will it take for this tank to decay to less than 1.0E-2 µCi/cc? Days (Attach decay calculations)

This tank should then be resampled for release no sooner than: Time/Date

3. IF NO, THEN use the following chart to determine release parameters to be used. Circle appropriate values.

GDT Concentration Allowable Release Rate WG-36 Setting Estimated Release Time

(µCi/cc) (SCFM) (% OPEN) (HOURS) 1.0 E-2 110 100 0.6 2.0 E-2 55 75 1.2 3.0 E-2 36 65 1.8 4.0 E-2 27 55 2.4 5.0 E-2 22 50 3.0 6.0 E-2 18 45 3.7 7.0 E-2 15 40 4.4 8.0 E-2 13 37 5.2 9.0 E-2 12 35 5.5 1.0 E-1 11 30 6.0 Holdup for decay is mandatory for any gas decay tank exceeding total gas activity concentration of 1.0 E-1 µCi/cc.

4. Attach to appropriate discharge permit.

Prepared By Date Reviewed By HP Supervisor Date Attachment A SP-32B-116 Rev. X Date: MAY 27 2004 Page 11 of 16 REFERENCE USE

PRERELEASE DOSE ESTIMATE DISCHARGE PERMIT 05-XXXXX A. Volume to be released __3.09+07 ____ cc B. Concentration of all Noble Gas isotopes __1.71E-02 ___ µCi/cc C. Concentration of I-131 and all particulate isotopes half live > 8 days ___1.00E-04___ µCi/cc D. Multiply A time B to get microcuries of noble gases to be released ___5.28E+05 __ µCi Multiply A times C to get microcuries of I-131 and > 8 day E.

particulates to be released ___3.09E+03 __ µCi F. Multiply D times 1.2 E-10 to find estimated dose due to Gamma __6.34E-05____ mRAD G. Multiply D times 2.5 E-10 to find estimated dose due to Beta __1.32E-04____ mRAD Multiply E times 9.32 E-5 to find estimated dose due to Iodines H.

and > 8 day particulates ___2.88E-01___ mRem I. Add F plus cumulative quarterly Whole Body total __6.34E-05____ mRAD J. Add G plus cumulative quarterly Skin total __1.32E-04__ mRAD K. Add H plus cumulative quarterly Organ total ___2.88E-01___ mRem L. Is I 0.62 mRAD? YES NO M. Is J 1.25 mRAD? YES NO N. Is K 0.94 mRem? YES NO IF L, M, or N is answered No, THEN notify HP Group Supervisor. Release may NOT proceed unless Treatment Systems are used. See ODCM Specification 3.4.4.

Prepared By Date Reviewed By HP Supervisor Date Attachment B SP-32B-116 Rev. X Date: MAY 27 2004 Page 12 of 16 REFERENCE USE

POST-DISCHARGE

SUMMARY

SHEET DISCHARGE PERMIT NO.

Type of Discharge Start Date and Time End Date and Time Volume Discharged (ccs)

Duration of Discharge (sec.)

List microcurie amounts for all isotopes released during this discharge:

ISOTOPE µCi RELEASED ISOTOPE µCi RELEASED Prepared By Date Reviewed By HP Supervisor Date Attachment C SP-32B-116 Rev. X Date: MAY 27 2004 Page 13 of 16 REFERENCE USE

CONTAINMENT PURGE DISCHARGE PERMIT PERMIT NO. 05-XXXXX Total Gas Activity _1.71E-02 _ µCi Part Alpha __________ µCi/cc Part. Beta-Gamma _1.00E-04 _ µCi Tritium Activity __________ µCi/cc Total Halogens _0.0E+00 _ µCi RBV SYS Lineup Requested:

__________ 36 Normal Purge Attach sample results and Pre-release Dose Estimate. __________ 36 Purge via Purge Filter Radiation Technologist __________________________________ Time/Date _______________________________

HP Supervisor _________________________________________ Time/Date _______________________________

PRIOR TO DISCHARGE:

RM-11 Indication = _________ CPM RM-11 Source Check = _________ CPM RM-12 Indication = _________ CPM RM-12 Source Check = _________ CPM RM-21 Indication = _________ CPM RM-21 Source Check = _________ CPM Notify HP to install fresh filters in the RM-21 Sampler. _________ Initials Position RM-11 Samples Selector Switch to VENT. _________ Initials Obtain current Meteorological data from PPCS and attach to this permit. _________ Initials Authorization to Start (Shift Mgr.) Time/Date HP notified prior to start of release. _________ Initials Release Started By Time/Date Release Ended By Time/Date AT END OF RELEASE:

RM-11 Indication = _________ CPM RM-21 Indications = _________ CPM RM-12 Indication = _________ CPM Notify HP of release completion and for filter change out in RM-21 Sampler. _________ Initials Obtain current Meteorological data from PPCS and attach to this permit. _________ Initials AR Initiated: YES NO AR No. ________________

Discharge Permit Reviewed By Shift Manager Time/Date Route completed Discharge Permit to HP Group Supervisor.

Complete all post-discharge data. _________ Initials Complete and attach Post-Discharge Summary Sheet. _________ Initials HP Supervisor Date Attachment D SP-32B-116 Rev. X Date: MAY 27 2004 Page 14 of 16 REFERENCE USE

GAS DECAY TANK DISCHARGE PERMIT PERMIT NO. 05-XXXXX TIME/DATE 0600 11/16/2005 Total Gas Activity _1.71E-02 _ µCi/cc Tank Number __A_______________

Part. Beta-Gamma _1.00E-04 ___ µCi/cc Part. Alpha _0.00E+00___ µCi/cc Tank Pressure

___1.98E+01____________________ PSIG Total Halogens _0.00E+00___ µCi/cc Tritium Activity _2.13E-05 ___ µCi/cc Radiation Technologist Time/Date Do NOT exceed ______75__% open on Valve WG-36. (See Attachment A, SP-32B-116.)

Attach all sampling results sheets and pre-release dose estimate.

HP Supervisor Time/Date PRIOR TO DISCHARGE:

RM-13 Indication = _________ CPM RM-14 Indication = _________ CPM RM-13 Source Check = _________ CPM RM-14 Source Check = _________ CPM Aux. Bldg. Vent Sys lineup: TRAIN A B BOTH (Both required when Total Gas 1.0 E-2 µCi/cc.)

Obtain current Meteorological data from PPCS and attach to this permit. _________ Initials Authorization to Start (Shift Manager) Time/Date HP notified prior to start of release. _________ Initials Release Started By ___________________________________________________ Time/Date __________________

Release Ended By ____________________________________________________ Time/Date __________________

AT END OF RELEASE:

RM-13 Indication = _________ CPM RM-14 Indications = _________ CPM Tank Pressure = _________ PSIG HP notified after completion of release. YES NO Initials Tank was purged: YES NO Initials Obtain current Meteorological data from PPCS and attach to this permit. Initials AR Initiated: YES NO AR No. ________________

Discharge Permit Reviewed By Shift Manager Time/Date Route completed Discharge Permit to HP Group Supervisor.

Complete all post-discharge data. _________ Initials Complete and attach Post-Discharge Summary Sheet. _________ Initials HP Supervisor Date Attachment E SP-32B-116 Rev. X Date: MAY 27 2004 Page 15 of 16 REFERENCE USE

PORV DISCHARGE PERMIT PERMIT NO.

ISOTOPE ACTIVITY ISOTOPE ACTIVITY AIR EJECTOR GAS RESULTS µCi/cc µCi/cc

µCi/cc µCi/cc STEAM GENERATOR BLOWDOWN RESULTS: (µCi/ml) 1A 1B ISOTOPE ACTIVITY ISOTOPE ACTIVITY Iodine Activity Tritium Activity All Other Isotopes Attached sample results and pre-release dose estimate.

HP Supervisor _____________________________________________ Time/Date ______________

PRIOR TO DISCHARGE:

Obtain current Meteorological data from PPCS and attach to this permit. _________ Initials HP notified prior to start of release. Initials During PORV operation for plant cool down, log the following:

S/G PORV OPENED PORV CLOSED (A or B) DATE TIME S/G psig DATE TIME S/G psig AT COMPLETION:

Obtain current Meteorological data from PPCS and attach to this permit. _________ Initials HP notified after completion of release. Initials Reviewed by Shift Manager _______________________________________________ Time/Date Route completed Discharge Permit to HP Group Supervisor.

Complete all post-discharge data. _________ Initials Complete and attach Post-Discharge Summary Sheet. _________ Initials HP Supervisor Date Attachment F SP-32B-116 Rev. X Date: MAY 27 2004 Page 16 of 16 REFERENCE USE

WISCONSIN PUBLIC SERVICE CORP. No. SP-32B-116 Rev. X Title Gaseous Radioactive Effluents - Reports Kewaunee Nuclear Power Plant for Batch Releases Surveillance Procedure Date MAY 27 2004 Page 1 of 16 Reviewed By Bart Steckler Approved By Tom Schmidli Nuclear Yes PORC ; Yes SRO Approval Of ; Yes Safety Review Temporary Related ; No Required No Changes Required No 1.0 Plant Initial Conditions 1.1 This procedure is used, in conjunction with Procedure HP-01.012, RETSCODE Computer Program Operating Guide, to generate radioactive gaseous effluents release reports for batch releases from the Kewaunee Nuclear Power Plant (KNPP). It quantifies radioactive gaseous effluents for batch releases from the following locations:

Waste Gas Decay Tanks (WGDT)

Containment Building Purge, which is defined as the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Reactor Building Vent (RBV) System operation after reactor plant shutdown.

Power Operated Relief Valves (PORV), during periods of primary-to-secondary leakage.

1.2 This procedure is performed under all plant conditions.

Note For other batch releases, refer to Procedure HP-05.015, Miscellaneous Gaseous Radwaste Releases.

2.0 Precautions 2.1 A WGDT having a total noble gas activity concentration exceeding 1.0E-02 µCi/cc, shall NOT be released until evaluations listed in Gas Decay Tank Prerelease Evaluation, Attachment A, are completed.

2.2 Both trains of the Auxiliary Building Ventilation (ABV) System shall be in operation during the release of a WGDT exceeding 1.0E-02 µCi/cc total gas activity concentration.

2.3 A WGDT having a total noble gas activity concentration exceeding 1.0E-01 µCi/cc, shall be placed on hold for decay prior to release.

sp-32b-116 documentationro.docMichael W. Ahearn/Amy KudickMichael W. Ahearn REFERENCE USE