ML12338A665

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Official Exhibit - ENT000327 -00-BD01 - 3-CY-2325, Rev. 10, Radioactive Sampling Schedule (June 16, 2011)
ML12338A665
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 06/16/2011
From: Sandike S
Entergy Nuclear Northeast
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 22135, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 3-CY-2325, Rev 10
Download: ML12338A665 (19)
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Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 ENT000327 Exhibit #: ENT000327-00-BD01 Identified: 10/15/2012 Submitted: March 29, 2012 Admitted: 10/15/2012 Withdrawn:

Rejected: Stricken:

Other:

-=Entergy Procedure Use Is:

o Continuous Control Copy:_ _ __

~ucle~ ~or~east o Reference Effective Date :-

1--16-11 fP o Information Page 1 of 19 NON-QUALITY RELATED RADIOA~IIVE SAMPLIN~ S~HEDULE APPROVED BY:

.*J(1dian POint Steven Sandike June 16, 2011 Procedure Writer / Date EDITORIAL REVISION

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 2 of 19 REVISION

SUMMARY

1.0 REASON FOR REVISION 1.1 This procedure was revised to incorporate user feedback.

2.0

SUMMARY

OF CHANGES 2.1 Modified Section 4.5 to reflect voluntary compensatory action for R-56C as well as R-56A and R-568 being out of service (Site Sewage monitors)

[Editorial 4.6.13].

No: 3-CY -2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 3 of 19 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ...... ... .. ... .... ...... .. ... .... ...... ..... ... ........ ....... ....... ... ...... ......... ... .. .. .... .... . 4 2.0 PRECAUTIONS AND LIM ITATIONS ... .. .... ...... ........ ....... ..... ..... .... .. ... .. .. ......... 4 3.0 PREREQUISITES .... ... ... ..... .. .. .... ... .. .... .. ..... .. .... .... ..... ... .. ... .... .. ..... ... .......... ..... 6 4.0 PROCEDURE .. .. ... ... .... ..... ... .. .. ... .. .... .. ... ..... ...... ...... .. ... ........ .... .. ... ...... ..... ..... .. 6 4.1 Sampling .... .. .. .... ... .. .. ... .. ..... ............. .. ..... ... ... ..... ...... .. ... ... .. ... ..... ..... .... ... . 6 4.2 In Plant Radioactivity Sampling Schedule .. .. ..... .... .... ... .. ...... ... ... ... .. .... ... . 7 4.3 Liquid Effluent Radioactivity Sampling Schedule ..... .. .. .... .. ...... ... ... .. ....... 9 4.4 Gaseous Effluent Radioactivity Sample Schedule ... .... .. ......... .... .. .... ... . 11 4.5 Actions Required When Radiation Monitors Are Out of Service ... ...... .. 12 4.6 Footnotes ...... ... .... .. .. ... ... ...... .. .... ..... ...... .... .... ... .. ..... ....... .. ... .... .. ..... ... ... . 14

5.0 REFERENCES

...... .... ...... .. ... .... .. .. ... ....... .... .... .... .... ...... .......... .. ....... .. .... ........ 19 6.0 RECORDS AND DOCUMENTATION ... ........ ..... ......... .... .... ..... .... ...... .. .... .. ... 19

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 4 of 19 1.0 PURPOSE 1.1 This procedure establishes a radioactive effluent and in-plant monitoring schedule, which will fulfill plant license requirements and ensure compliance with quantitative information on radionuclides released to the environment.

1.2 This procedure applies to radioactive effluent and in-plant monitoring schedule.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions and Limitations 2.1.1 During startup, shutdown or a 15% change in thermal power (in one hour), Dose Equivalent Iodine and/or Building Vent noble gas monitors (Rams, Admin, and PV) shall be monitored to determine if increased Building Vent sampling is necessary as per the Offsite Dose Calculation Manual (ODCM).

2.1.2 IF the plant is in the same condition mandated from an unsatisfactory Technical Specification sample result, THEN the performance of applicable actions is not required. See Technical Specifications and associated Limiting Conditions for Operation (LCO).

2.1.3 The following tabl~s ar~ int~ncl~d to provid~ information for sampling requirements during power operation. Chemistry Management will consult Technical Specifications or the Offsite Dose Calculation Manual (ODCM) for requirements during transient, off normal, or shutdown conditions AND will direct the assignment of required samples through the appropriate schedule sheets.

2.1.4 This procedure is not intended for interpretation of Technical Specifications; consult Technical Specifications or the Offsite Dose Calculation Manual (ODCM) for clarification.

2.1.5 WHEN a radiation monitor is out of service, THEN systems shall be sampled per Section 4.5, as applicable. {Reference 5.1.2}

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 5 of 19 2.1.6 The delay between sample collection and start of sample counting (sample transit time) is limited as follows: {Reference 5.1.3}

Plant effluent samples: count as soon as possible after collection, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> maximum for Noble Gas All other analyses: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> maximum 2.1.7 Footnote (41), referenced in Sections 4.2 (In-Plant Radioactivity Sampling Schedule) and 4.3 (Liquid Effluent Radioactivity Sampling Schedule) identifies systems, structures and components (SSCs) that interface with the Radiological Groundwater Monitoring Program (Reference 5.3.10). A leak from these SSCs, can result in significant contribution to ground water contamination. Therefore, a large increase in SSC radioisotope concentration should be evaluated for impact to the Radiological Groundwater Monitoring Program (RGVVrvlP), defined in th~

aDeM.

2.2 General Information 2.2.1 In the following tables, ">MDA" shall be defined as the minimum detectable activity above background for any effluent-related radioanalysis.

2.2.2 All units are IlCi/cc or IlCilml unless otherwise noted.

2.2.3 Systerns that are monitored by a process radiation monitor are identified by an asterisk (*), in the Sample Point column.

2.2.4 The frequency of sampling for items NOT involved with the ODCM or Technical Specifications is at the discretion of Chemistry Management.

2.2.5 A verification check for completed Technical Specification/ODCM analyses will be performed in the interval between the required sample frequency. This ensures the Technical Specification maximum time between analyses will not be exceeded. {Reference 5.1.1}.

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 6 of 19 3.0 PREREQUISITES NONE 4.0 PROCEDURE 4.1 Sampling 4.1.1 Sample plant and effluent systems according to the following tables, per the delineated required sampling and analysis frequency.

4.1.2 Record analyses results in WinCDMS or as directed by Chemistry Management.

4.1.3 Any analytical results substantially different from previous results of the same sample point should be reported to Chemistry Management.

4.1.4 Data from samples of gaseous or liquid waste which are to be released shall be supplied to the Operations Department in accordance with the following procedures:

  • IP-SMM-CY-001 (reference 5.3.1), Radioactive Effluents Control
  • 3-S0P-WDS-13 (reference 5.3.2), Gaseous Waste Release Permits
  • 3-S0P-WDS-14 (reference 5.3.3), Liquid Waste Releases

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 7 of 19 4.2 In Plant Radioactivity Sampling Schedule Max Time Action Sample Point Analysis Frequency Between Level Analysis Reactor Gross Activity 4 I Week Coolant * (Gamma Spectroscopy) N/A (1 )(7)(14)(2) (typically)

Tritium Activity Weekly (FSAR) 10 Days (38) 1.0(15)

{Ref 5.1.1}

Reactor Coolant Dose I 1 17 Days Equivalent Xe-133 (Verify 8.75 Days (SR 3.4 .16.1) O-CY-2765

< 652 uCilgm) (3) (11)

Reactor Coolant Dose Equivalent 1-131 (Verify 1 114 Days 17.5 Days 0-CY-2765 (SR 3.4.16.2)

< 1.0 uCi/gm) (3) (5}

Total RCS Activity (6):

(Crud Analysis, Decayed 2 I Month N/A Count, and Split Gas and Degassed Liq Count)

Refueling Water Gross Activity (41) Monthly 45 Days (8)

Storage Tank (7) Tritium Activity (41) Quarterly 1.0(15)

Dose Equivalent Iodine Monthly 37 Days 0.1 Secondary (TS 3.7.17)

Coolant*

GS-"]:-+fit~l;Jmt39l Quarterly (12) N/A Feed Water Tritium (39) (each)

Component Gross Activity Monthly 37 Days (38)

Cooling Water

  • I Spent Fuel Pool Gross Activity and Tritium Monthly 37 Days (38)

Gamma Emitters (16) (41) Monthly 45 Days (8)

Primary Water Storage Tank Tritium Activity (41) Quarterly

  • Denotes that this system includes a process radiation monitor

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 8 of 19 4.2 Plant Radioactivity Sampling Schedule (cont)

Max Time Sample Point Analysis Frequency Between Action Level Analysis Monthly Gamma Emitters Auxiliary Steam (41) (When sample > MDA is available)

Condensate* (10)

> Secondary Tritium (22) (41) Monthly System Baseline Instrument Air (10) Gamma Emitters Monthly > MDA (23)

CVCS Degassed or Monthly, when Decayed Liquid operating Letdown Demin Out activity Noble Gas Gamma Weekly ForVCPR Emitters quantification Vapor Containment Tritium Quarterly Per RP Any Release, Outside Radioactive Gamma Emitters Monthly when 45 Days Temporary Tanks (9) (41) (8) volume added Noble Gas, Weekly, when

> MDA Breathing Air (10) Gamma Emitters in use Iodine, Particulates Initial Use Potable Water Gamma Emitters

......*. Monthly - -> MBA ( 231---

(Inside RCA) (10) and TnHum Potable Water Gamma Emitters Monthly > MDA (23)

(conventional side) (10) and Tritium Spent Fuel Pool Auxiliary Daily (when in >MDA Gamma Emitters, Heat Exchanger service) & prior and Tritium (23)(40)

(Secondary Side) (10) (41) to draindown

- Gamma Emitters Spent Fuel Pool Liner Monthly, when >10% of

- Boron ppm a water sample the current Tell-Tale Drain (10) (41) - Volume collected is available

- Tritium uCilml SFP values

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 9 of 19 4.3 Liquid Effluent Radioactivity Sampling Schedule Minimum Sampling Sampling Action Sample Point Analysis Analysis Method Frequency Level Frequency Gamma Emitters Prior to Prior to Grab (17) (13) (8) release Release Batch Waste Dissolved and Each Each Release Tanks

  • Grab Entrained Gases Batch Batch (Monitor Tanks, S/G Draindown) Monthly Composite Each (41) Tritium (39) When (18) Batch Releasing Monthly Composite Each Gross Alpha When (18) Batch Releasing Quarterly Sr-89, Sr-90, Composite Each When Fe-55, Ni-63 (18) Batch Releasing Composite Weekly Continuous* Gamma Emitters Daily (21) Composite Releases Dissolved and (19) (20) (41)

Entrained Gases Grab Monthly S/G Slowdown, Monthly (gamma (21) Grab emitters)

Could also (Weekly) Monthly include Service Water, or Turb Tritium (39) Composite Daily When Hall drains, etc (18) Releasing _ --

with known (Monthly) Monthly contamination in Gross Alpha Composite Daily When the system (18) Releasing (Monthly) Quarterly Sr-89, Sr-90, Composite Daily When Fe-55 (18) Releasing Raw Gamma Emitters Grab Monthly Monthly >MDA

Sewage, IP2 and IP3
  • Tritium Grab Monthly Monthly (23)(24)

(10) (41)

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 10 of 19 4.3 Liquid Effluent Radioactivity Sampling Schedule (cont)

Minimum Action Sampling Sampling Sample Point Analysis Analysis Method Frequency Level Frequency Any Gamma Site Storm RiverFront Grab Drains (10) Drains for H-3 Monthly (Liquid) H-3> limit and gamma (Details are (22) (26) provided in Prescribed 0-CY-1510) Any Gamma Effluent Grab Drains for Quarterly (Liquid) H-3> limit Note: (41) Gamma and In addition to this (22) (26)

Tritium periodicity, drains 81, 86, MH-5 are Other drains Any Gamma sampled at least identified in Grab Annually QUARTERL Y for 0-CY-1510, for (Liquid) H-3> limit the RGWMP, for gamma & H-3 (22) (26) gamma spec, H-3, and Sr-90, at the Gamma Grab Annually >3.0E-6 (25) contractor lab .. Emitters (sediment)

> Secondary House Service Tritium Grab Quarterly System Boiler (When Baseline Operating) (10) Gamma Grab Weekly Weekly >MDA (23)

Emitters Service Watef ..Ggmma .._--

fV'Ionfnly

>lVIDA*

Emitters and Grab (In RCA) * (10) (27) (23) (28)

Tritium Gamma TDS Tanks * >MDA Emitters and Grab Monthly (CPF) (10) (12) (22) (28)

Tritium Prior to pump >MDA gamma CPF Sanitary Gamma out, when a Sewage Holding Emitters and Grab Pri to Sec LR Tank (10) Tritium exists per IP- >1E-6 H-3 SMM-CY-001 (24)

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 11 of 19 4.4 Gaseous Effluent Radioactivity Sample Schedule Minimum Sampling Sampling Sample Point Analysis Analysis Method Frequency Frequency Principle Noble Waste Gas Storage Gas Gamma

  • (37) Grab Prior to release Each Tank Emitters (35)

Principle Noble Containment Purge

  • Gas Gamma Each Purge Does NOT include VC Grab Prior to release Emitters Pressure Reliefs. See Section 4.5 for VCPR Requirements, R11/12 . Iodine &

Particulates Grab Prior to release Each Purge Weekly (34J Principle Noble -or- As defined Condenser Air Gas Gamma by applicable Ejector

  • Grab per O-CY-2450 Emitters condition, in and Chemistry 0-CY-2450 Management Principle Noble Environmental Gas Weekly Grab Weekly (29)

Release Points

  • Gamma Emitters Monthly Tritium Grab (30)(31 )(33) Monthly Plant Vent, Continuous RAMS Vent, 1-131 Charcoal Weekly **

(32)(36)

Admin Bldg Vent, Continuous etc. Gamma Emitters Particulate (32)(36) Weekly **

Gross Alpha Particulate Continuous Weekly Sr-89, Sr-90 Particulate Continuous Weekly Daily at the PV, for the first 7 days 24 hr following a typical plant shutdown, 1-133, 1-135 (36) AND Charcoal Monthly, whenever lodine-131 is identified in the weekly routine.

    • Constitutes a ITechnical Specification" (RECS) Channel Check

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 12 of 19 4.5 Actions Required When Radiation Monitors Are Out of Service Page 1 of 2 Date Date Rad 2300- 0700- 1500-System '7 OOS l\Il()n(~) 0700 1500 2300 Both WHEN operating (TAVE > 500°F), THEN sample RCS R-63A & Reactor Coolant for gross activity once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> R-63B of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period. (4)

  • VC Purges are prohibited Vapor Containment
  • VC Press Reliefs may be performed IF a grab R-12 sample of the VC atmosphere noble gas has been (VC) Noble Gas obtained within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, per IP-SMM-CY-001 and 3-S0P-WDS-13.
  • Sample the VC for Noble Gas once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Technical Specification 3.4.15 -OR-Vapor Containment Both (VC) Particulate R-11 &

R-12 AND Noble Gas

  • OPS must perform a water inventory balance once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Technical Specifications 3.4.15 and 3A13
  • Sample the Plant Vent for noble gas activity once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.

Both R-14 &

Plant Vent R-27

  • Prior to release of gas decay tanks, 2 independent samples must be analyzed and 2 technically qualified individuals must independently verify the release calculations and the discharge lineup.
  • Sample the Condenser Air Ejector once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, for noble gas activity. IF a Primary to Secondary Leak Condenser Air exists (> 30 gpd) THEN increase this sampling R-15 frequency to once 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 0-CY-2450.
  • Additionally, Health Physics will survey the area at R-15 for uR/hr and record conversions to gpd per 3-AOP-SG1.

Both Fan Cooler Unit Sample FCU service water once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the R-16A &

Service Water first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, for gross activity.

R-16B Component R-23 Cooling Water Sample CCW service water once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the (CCW) Service first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, for gross activity.

Water

No: 3-CY -2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 13 of 19 4.5 Actions Required When Radiation Monitors Are Out of Service Page 2 of 2 Date Date Rad 2300~ 0700- 1500-System Compensatory Action OOS Mem(s) 0700 1500 2300 Both R-17A Component IF both monitors are OOS, THEN sample and R-17B Cooling Water for gross gamma activity once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

R-18 during Liquid releases, Prior to a waste tank release, 2 Radwaste independent samples must be analyzed (at or or least 15 minutes apart) and 2 technically R-61 during a Pri qualified individuals must verify the release CPF Waste calculations and the discharge lineup.

to Sec Leak, Ref Effluent Line 5.3.1.

!E SG blowdown or sample system water is going to river in Modes 1-4 (including any from the AVT panel & R-19), OR steam releases are occurring (atmospherics, safeties, or 32 aux feed pump), THEN immediately sample the SGs for gross gamma activity, and initiate periodic Steam sampling at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> R-19 Generator thereafter while R-19 is OOS.

(SG)

IF performing DRAINDOWNS in Modes 5-6, THEN sample the effected Steam Generator prior to the draindown (within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) for gross gamma activity. Obtain an additional sample during the release or within an hour after termination of draindown.

Sample the inlet activity of the tank on R-20 Waste Gas receipt once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, for noble gas activity. (35)

Aux Sample for gross gamma activity once per R-37 Condensate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (when monitor is OOS and sample Return is available).

R-46 Admin Bldg Sample Admin Vent exhaust for noble gas Vent activity once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.

IF R-56C is OOS-along with either R56A OR R-56B THEN:

R-56A (U3)

IF the monitors are verified as indicating Raw Sewage R-56B (U2) correctly (per OAP-035) THEN obtain a to Buchanan reading once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift and log in R-56C (Combined) eSOMS. IF indication is unavailable (OOS)

THEN take grab samples daily from the combined system for gross activity.

Sample RAMS bldg exhaust for noble gas R-59 RAMS Bldg activity once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, in the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Exhaust of each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 14 of 19 4.6 Footnotes (1) A gross activity analysis shall consist of the quantitative measurement of the gamma radioactivity of the primary coolant in units of /-lCi/cc.

(2) The daily gross activity is routinely performed from a depressurized liquid sample of reactor coolant, measuring the gamma-emitting nuclides only. This analysis is performed after a specified uniform decay time and used for trending only.

(3) Reactor Coolant specific activity (uCi/gm) is limited by Technical Specifications 3.4 .16.

Surveillance Requirements are established for Noble Gas and Iodine limits in the form of Dose Equivalent Xenon-133 and lodine-131. Procedural guidance is established within O-CY -2765, Coolant Activity Limits, for incrementing action levels.

(4) The accelerated sampling frequency (depressurized routine sample) need only be performed until EITHER R-63A or R-638 is declared operable . This requirement is currently located in FSAR 11.2 (relocated from Tech Specs per ITS).

(5) In addition to the 14 day requirement, an analysis for DEI is also required as follows:

a) When DEI is > 1.0 uCi/gm, verify DEI is ~ 60 uCi/gm once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and return DEI to < 1.0 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. IF this condition cannot be met, THEN the unit must be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. (Additionally, the unit must be in Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ANYTIME DEI is > 60 uCi/gm).

b) Analyze Reactor Coolant Dose Equivalent lodine-131 between 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following each thermal power change exceeding 15 percent of the RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

These DEI requirements apply in MODES 1-4.

(6) Analyses are performed per 3-CY-2320 for total RCS activity.

(7) After refueling operations, liquid from the reactor cavity will be sampled for radioactivity content prior to being pumped into the Refueling Water Storage Tank.

(8) Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to liquid radwaste treatment systems.

Adm inistrative concentration limits, in uCilml, are applied to assist in controlling the total activity in the tank to less than 10 curies, per References 5.2 .2 and 5.3 .1. This concentration limit is applicable for FULL tanks and should be re-evaluated when applied to tanks that are LESS than full.

No: 3-CY -2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 15 of 19 (9) Liquid will be sampled for radioactive content prior to being pumped into the tank.

(10) These systems are normally uncontaminated and are monitored to detect for possible contamination per NRC IE Bulletin 80-10.

(11) The application of Dose Equivalent Xenon-133 replaced the notion of N/Ebar in Tech Spec Amendments #237 (unit 3) and #254 (unit 2).

(12) The Condensate Polisher and Steam Generator Blowdown demineralizers should not be placed in service when Steam Generator activity exceeds 1.4E-4 !-lCilml of Co-58 or 4.0E-6 !-lCilml of 1-131 .

WHEN activity in the Condensate polisher waste tanks is > MDA, THEN a release permit is required and the tanks shall be sampled in accordance with Section 4.3, Batch Waste Release Tanks.

For plant Modes 1, 2, 3 or 4, the specific activity of the secondary coolant system is limited to sO.10 uCilgm of Dose Equivalent 1-131 per Technical Specification 3.7.17.

(13) The ODCM requires monthly assurance that activity in outdoor tanks (such as 31 and 32 Monitor Tanks) is less than 10 curies. Normally, while the tanks are in use, this surveillance is accomplished from monthly samples, each limited to 0.22 uCilml (per IP-SMM-CY-001), which ensures less than 10 curies in the tank.

During periods when there is little or no water is added to the tank (and subsequently no recirculation or sample), verification of the curie level and compliance with the surveillance may be accomplished as follows:

e from the last sample of the tank (when there is ~Viq~Ilce QfJ}Q _'ltYru~Ladded), or eaefermiriing the-rntegrate-crtotaI cu-r=les-from-the volume and concentration of the water added, and the known curie level from the last surveillance.

(14) IF Gross Failed Fuel Detector readings exceed 5 !-lCi/cc, THEN sample the reactor coolant once a day to monitor for fuel element failures.

(15) !E Tritium concentration exceeds 1 !-lCi/cc in the refueling water, during refueling operations, THEN notify Chemistry and Rad Support {Reference 5.1.6}.

(16) !E short-lived isotopes are identified in the activity sample, THEN notify Chemistry Management.

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 16 of 19 (17) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch tank shall be isolated, and then thoroughly mixed for two tank volumes to assure representative sampling. Steam generator draindowns are considered batch releases for reporting purposes during shutdown condition, and shall be mixed prior to sampling per IP-SMM-CY-001.

(18) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. Should there be cause for further investigation (as determined by Chemistry Management), individual pathway or system samples can be drawn and re-analyzed.

(19) A continuous release is the discharge of liquid waste of non-discrete volume.

(20) In addition to S/G samples, additional secondary fluid shall be sampled as determined by Chemistry Management (more frequently than once per week) for principle gamma emitters whenever a primary to secondary leak exists, as defined by IP-SMM-CY-001.

(21) Individual steam generator samples shall be composited proportional to the amount of blowdown per steam generator.

(22) Due to continued presence of trace levels of tritium in systems associated with secondary fluid, Action Levels are established (typically at 1E-6, 5E-6, and 1E-5 uCilml) and managed within WinCDMS for each specific system. While these systems have already been evaluated for effluents and 80-10 concerns, NEWLY discovered tritium above these levels requires an additional investigation (system integrity, etc) per ANI 07-01 and NEI environmental initiatives.

(23) A~e:rifie:9 positive value forplcu"}t-related .ft?Q1rTlC3()Ltritium~t:?9veMQA[aQuire£"__ "-""

Tn vesligafio"i iby Ch"emisfry Management and/or Radiological Support.

!E the investigation shows a release to the public of 2 mCilyear or greater, THEN the release should be included in the effluent releases and a 50.59 evaluation should be written, covering the level of contamination, any potential releases to the environment, and dose as compared to NRC and EPA regulations. In addition, any results greater than MDA need to be evaluated for potential dose to personnel on site, regardless of whether or not any offsite release has occurred.

No: 3-CY -2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 17 of 19 (24) UPON verified positive plant-related gamma activity (not medical isotopes), OR verified positive tritium activity above MDA in raw sewage, THEN perform the following:

  • immediately contact Chemistry Management,
  • manually divert sewage to holding tanks,
  • obtain a sample for offsite analyses (gross alpha and pure beta emitters), and
  • initiate an investigation of the source per Ref 5.3.9.

(25) !E gamma activity concentration in storm drain sediment exceeds 3E-6 /lCi/gram of plant-related, short lived activation products, THEN Chemistry and Rad Protection should perform an evaluation of the possible sources. The evaluation should include establishment of additional measurements to assist in determining the magnitude of the release as well as disposition of the contaminated sediment.

(26) The effluents of the storm drain systems are analyzed at least on an annual average basis for effluent (curie and dose) contribution in the annual effluent report.

(27) Two service water (SW) samples are required. A composite sample of the SW from 31

& 32 CCW heat exchangers, (R-23 SW header) and a SW sample from the return line of the fan cooler units (R-16A and R-16B SW header).

(28) A verified reading above minimum detectable activity requires investigation. IF the activity is greater than minimum detectable activity, THEN a release permit is required and monitoring is required per Section 4.1.3 for Batch Waste Release Tanks or Continuous Releases (which ever is appropriate).

(29) The Plant Vent (PV) should be sampled and analyzed following shutdown, startup, or a thermal power change (within one hour) exceeding 15 percent of RATED THERMAL PGWER, if the Dose Equivaienfl6dTne andflleBDildfrigVerit (Rams,Admin,orPV) noble gas monitors increase greater than a factor of three, per the ODCM.

(30) Plant vent tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded unless continuous sampling equipment is in use.

(31) Plant vent tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust of the spent fuel pool area whenever spent fuel is in the spent fuel pool unless continuous sampling equipment is in use.

(32) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler, per the ODCM.

(33) Plant vent tritium should be monitored continuously (lPEC requirement.)

No: 3-CY-2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 18 of 19 (34) Grab sample only required while a release is in progress. IF activity is identified, THEN calculate a primary to secondary leak rate and adjust grab sampling frequency per Reference 5.3.4 and Chemistry Management. After plant startup, daily samples are required for approximately 1 week till primary gas is available, per Ref 5.3.5.

(35) Gas decay tank activity should not exceed 1.17E+02 I-lCi/cc (ODCM concentration Limit). Grab samples taken to verify this activity are taken on the inlet to the tank on receipt, per 0-CY-1500, Sampling Locations. The Technical Specification limit of 50,000 Ci Xe-133 equivalent (19,400 curies per the ODCM) per tank shall not be exceeded.

(36) Sampling shall be performed at least every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, for at least 7 days following shutdown, startup or a 15% change in power in one hour, analysis to be completed within 48 hrs of changing. This augmented sampling is required only if Dose Equivalent Iodine increases greater than a factor of three AND the Building Ventilation (RAMS Building, Admin Building and Plant Vent) noble gas monitors increase greater than a factor of three.

(37) Gaseous waste release tanks are normally allowed to decay as long as is reasonable prior to sampling for release (ALARA).

(38) A verification check for completed required analyses will be performed in the interval between the required sample frequency {Reference 5.1.1}.

(39) IF there is evidence of a secondary plant tritium trend upwards to 5.00E-6 uCi/ml over baseline, THEN initiate actions to determine the presence of an actual Primary to Secondary leak. These actions should include additional sampling, determination of secondary plant effluent impact (airborne and liquid), investigation of activities in the Condensate Polisher, and other actions identified in Reference 5.3.4.

DaC:K-UID SFP secondary cooling system sample is required in two cases:

1) Daily, while the system is in service; and,
2) Prior to draining IF contamination is identified in the secondary system, THEN inform Chemistry Management immediately so that a determination of potential release impact can be performed. Additionally, draining the system requires a temporary open vent from inside the SFP building. Therefore, prior to draining, the FSB Ventilation System should be verified in-service. IF it cannot be placed in service, THEN obtain a noble gas sample of the FSB atmosphere so that Chemistry Management can determine if there is a potential for a release pathway through this vent line.

(41) These samples are also in support of the RGWMP. IF an analytical result supporting this program is found to be out of specification, THEN notify Chemistry Management and the Ground Water Technical Specialist for initiation of investigation.

No: 3-CY -2325 Rev: 10 RADIOACTIVE SAMPLING SCHEDULE Page 19 of 19

5.0 REFERENCES

5.1 Commitment Documents 5.1.1 IPN-96-076, Notification of a Change to a Previous Corrective Action in LER 93-021 -00 5.1.2 LER 91-009-01, Inadvertently Missed Backup Sample for Inoperable Radiation Monitor 5.1.3 ACTS 14420, from QA Audit 91-111, Nov 95, regarding delay between noble gas sample and count time.

5.1.4 ACTS 00-49953, regarding Technical Specification Channel Checks.

5.1.5 Tech Spec Amend 223 limiting DEI for Control Room Habitability.

5.1.6 Final Safety Analysis Report Section 11.2 5.2 Development Documents 5.2.1 Technical Specifications 5.2 .2 Offsite Dose Calculation Manual 5.2.3 NRC I.E, Bulletin 80-10 "Contamination of non-Radioactive Systems .. ."

5.2.4 Calculation No. IP3-CALC-RAD-00028, "Radiological Assessment of Postulated Steam Generator Tube Rupture Accident".

5.3 Interface Documents 5.3.1 IP-SMM-CY-001, Radioactive Effluents Control Program 5.3.2 3-S0P-WDS-13, Gaseous Waste Release Permits 5.3.3 3-SgP-Wp§-14, biquid Waste Releases 5.3.4 0-CY-2450 , Primary to Secondary Leak 5.3.5 EPRI PWR Primary to Secondary Leak Guidelines Revision 3 5.3.6 3-CY-2320, Total Reactor Coolant Activity Determination 5.3.7 0-CY-2765, Coolant Activity Limits - Dose Equivalent Iodine/Xenon and Average Energy (E-bar) 5.3.8 0-CY-1510, IPEC Storm Drain Sampling 5.3.9 EN-CY-108, Monitoring of Non-radioactive Systems 5.3 .10 IP-SMM-CY-110, Radiological Groundwater Monitoring Program 6.0 RECORDS AND DOCUMENTATION NONE

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