Text

Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5
	ML20094B285
Person / Time
Site:	Peach Bottom
Issue date:	07/31/1995
From:	Akers D, Morcos N; IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	; NRC (Affiliation Not Assigned)
Shared Package
ML20094B255	List: L-95-037, Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5;
References
	CON-FIN-E-2084 INEL-95-0379, INEL-95-379, NUDOCS 9510310366
	Download: ML20094B285 (23)
	v • d • e

{{#Wiki_filter:---_------_ _ _- _ - INEL-95/0379 et Evaluation of Peach Bottom Atomic Power Station Units 2 and 3 Offsite Dose Calculation Manual, Revision 5 Docket No. 50-277, Facility License No. DPR-44 Docket No. 50-278, Facility License No. DPR-56 N. Morcos D. W. Akers Published July 1995 1 idaho National Engineering Laboratory Lockheed Martin Idaho Technologies Idaho Falls, Idaho 83415 Prepared for the Division of Radiation Safety and Safeguards Office of Nuclear Reactor Regulation U.S. Nuclear Regulatorv Commission Washington, D.C. 20555 Under DOE Contract DE-AC07-941D13223 FIN E2084 pgkO3gokOO0277 , p PDR j

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i a i ABSTRACT ' ~ ne Offsite Dose Calculation Manual (ODCM) for the Peach Bottom Atomic Power Station

          , (PBAPS) Units 3 and 4 contains current methodology and parameters used to calculate offsite L            doses, dose rates, and effluent monitoring and alarm setpoints, and to conduct the radiological       i

- . environment monitoring program. The NRC transmitted the most recent PBAPS ODCM, i -Revision 5, effective July 1,1993, to the Idaho National Engineering Laboratory for review by EG&G Idaho, Inc. De ODCM was reviewed, and the results are presented in this report.

1

' He PBAPS ODCM generally uses documented and approved methods that are consistent with the methodology and guidance of NUREG-0133 and Regulatory Guide 1.109.- He ODCM ,

contains a description of all the required methodology. Fifteen primary comments on monitoring i methodology, calculational methods for gaseous and liquid effluents, and total dose should be addressed promptly. Due to several omissions and errors, it is recommended that the ODCM be revised to address and correct the most significant deficiencies identified in this review. 3 I l 4 1 1

                                                                                                        .,         I 4

I 1 I i III 1 l

i. {- a i i 4 FOREWORD This report is submitted as partial fulfillment of the " Review of Radiological Issues" project conducted by the Idaho National Engineering Laboratory for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation. He U.S. Nuclear Regulatory Commission funded this work under FIN E2084. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warrant, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, or any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. l l IV i

, CONTENTS 4 ABSTRAC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii

          ' FOREWORD . . . . . . . . . . . . .      4 ..............................................iv

1. INTR O D UCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 _ P urpose of Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4

1.2 Plant-Specific Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

2. REVIEW CRITE RIA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

3. RADIOACTIVE EFFLUENT RELEASE ROUTES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.1 Liquid Emuent Release Routes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

'I 3.2 Gascous Effluent Release Routes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 t

4. EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 l

               ~ 4.1 Liquid Emuent Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.2 Gascous Effluent Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 l

1 4.3 Concentrations in Liquid Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 I , 4.4 Dose Rates Due to Gaseous Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 1 4.4.1 Dose Rates Duc To Noble Gases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.4.2 Radionuclides Other Than Noble Gases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 4.5 Dose Due to Liquid Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 4.6 Doses Due To Gaseous Emuents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 4.7 Dose Projections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.7.1 Liquid Emuent Dose Projections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.7.2 Gaseous Emuent Dose Projections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.8 Diagrams of Emuent Release Routes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.9 To tal Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 4.10 Environmental Monitoring Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 y

l s 4.11 La nd .Use Census . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

                  '4.12 Interlaboratory Comparison Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-
                                                                                                                                                         )

5. TECHNICAL FINDINGS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 17 !

6. REFERENCES ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l FIGURES

        .- l. Liquid radwaste treatment system at PBAPS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

2. Off gas radwaste treatment system at PBAPS '. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

3. Ventilation exhaust waste treatment system at PBAPS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 TABLE

1. Summary of the contents of Peach Bottom Units 2 and 3 ODCM, Revision 5 . . . . . . . . . . 2 6

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a Evaluation of Peach Bottom Atomic Power Station Units 2 and 3 Offsite Doss Calculation Manual, Revision 5 Docket No. 50-277, Facility Ucense No. DPR-44 Docket No. 50-278, Fscility License No. DPR-56

1. INTRODUCTION 1.1 Purpose of Review This document reports the review and evaluation of Revision 5 of the Cr. te Dose Calculation Manual (ODCM) submitted by the Philadelphia Elcctric Company, the Licensee for the Peach Bottom Atomic Power Station (PBAPS). Revision 5 of the ODCM, effective July 1, 1993, was transmitted to EG&G Idaho, Inc., for review. De ODCM is a supplementary j document for implementing the PBAPS Technical Specifications (TS) in conformance with Section IV of Appendix I to 10 CFR Part 50.1 The review of this document was performed to assess conformance of the ODCM to the PBAPS TS and NRC guidelines. The ODCM consists j of two major parts.

The first part includes an introduction to the ODCM and the methodology to calculate liquid and gaseous monitor setpoints and dose calculations. This part of the ODCM ensures compliance

. with PBAPS TS 4.8.B.2,4.8 B.4.a, and 4.8.C.1,2,3,5a,6b. The methodologies for assessing the nuclear fuel cycle total dose in accordance with PBAPS 4.8.D to satisfy the requirements of 10 CFR 190.102 and the calendar year dose calculations in accordance with PBAPS 6.9.2.h are l also presented. l The second part of the ODCM provides the description of the Radiological Environmental l Program and the methodologies needed to implement the program. A summary of the contents ~ of PBAPS ODCM, Revision 5, is listed in Table 1. 1.2 Plant-Specific Background i The Peach Bottom Atomic Power Station consists of two General Electric boiling water reactor units rated at 1,051 MW(e) each. The two nuclear systems include single-cycle forced-circulation boiling water reactors, with the liquid wastes discharged to the Conowingo Pond i I ! through the circulating water discharge canal. The plant is located in a formerly wooded area with a gentle slope. It is about 14 mi northwest of the Sasquehanna river's mouth at the head of

the Chesapeake Bay and on the west bank of the pond formed by Conowingo Dam. The city of Lancaster, Pennsylvania, lies 17.9 mi north of the site. The plant grade is established at Elevation 116 ft, and inundation is considered improbable even under flood conditions.

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4 Table 1. Summary of the contents of Peach Bottom Units 2 and 3 ODCM, Revision 5. Procedural Peach

Bottom details in Technical Brief description ODCM Specifications of contents
Purpose and scope of the ODCM Sect. I. .

Sect. II.A 4.8.B.3.a Liquid effluent monitoring instrumentation and surveillance Sect. II.A B 3.8.C4.b Liquid setpoint determination Sect. III.A 3.8.B.1 Liquid effluent concentration Table 4.8.1 Liquid sampling and analys,is Sect. III.B 3.8.B.2 Liquid effluent dose commitment Sect. III.B 4.8.B.4.a Liquid radwaste treatment and dose projection Sect. II.C 3.8.C4.a Gaseous effluent monitoring 4.8.C4.a,b,c,d instrumentation and surveillance Sect. II.C, D 3.8.C1.a Gaseous setpoint determination Sect. IV.A.1 3.8.C Gaseous effluent air dose rate (noble gases) Sect. IV.A.2 3.8.C1.b Gaseous organ dose rate (iodines, tritium, and particulates)

Table 4.8.2 Gaseous sampling and analysis Sect. IV.B 3.8.C2 Gaseous air dose commitment 4.8.C2

! Sect. IV.C 3.8.C3 Gaseous organ dose commitment 4.8.C3 Sect. IV.D 3.8.C5 Gaseous radwaste treatment and dose projections l Sect. V.A 3.8.D Uranium fuel cycle (total) dose

4.8.D Table VII.A.1 3.8.E Radiological environment monitoring, l

Figures VII.A.1,2,3,4 6.9.2.h(3) sampling, and analysis Table 4.8.3 a

X/Q and D/Q methodology and data 8

     -                        3.8.E.2                 Iand use census 8
     -                        3.8.E.3                 Interlaboratory Comparison Program 8                          a
     -                                                Major changes to liquid and gaseous radwaste treatment systems 2

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l < 1 Table 1. (continued). . - Procedural Peach Bottom ! details in Technical Brief description ODCM SpeciAcations of contents l l i -- a 6.9.2.h(1) Annual Radiological Environmental l Operating Report. '

6.9.2.h(2,3) Semiannual Radioactive Emuent l Release Report i

8 6.9.2.h(2) Changes to the ODCM i

! a. Topics not addressed or identified in the ODCM. i' ) The major surficial drainage course within the property limits is Rock Run Creek, which flows generally in an easterly direction into Conowingo Pond just south of the existing Unit 1, a i j high temperature gas cooled 40 MW(e) reactor (Docket No. 50171). Units 2 and 3 are located a ' minimuni distance of 2,600 ft from the nearest site boundary. De minimum distance to the site boundary in'a downstream direction is about 3,300 ft, and in an inland direction of about 3,100 ft 1 from Unit 2. De minimum distance across the pond from either Unit 2 or 3 to the far shore of the pond (to the northeast) is 7,600 ft. De minimum distance from the stack to the site l boundary is 2,350 ft. De river below Peach Bottom is used as a source of domestic water supply l to the city of Havre deGrace, the Perry Point Veteran's Hospital, the Bainbridge Naval Trammg Station, the Conowingo Power Plant, and the city of Baltimo~re. ;

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2. -REVIEW. CRITERIA- ;

i l j- Review criteria for the PBAPS Units 2 and 3 ODCM calculational methods are provided by ) the NRC in two documents: i

1. NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Emuent Controls for Pressurized Water Reactors.2 ,

2. NUREG-0133, Preparation of RETS for Nuclear Power Plants.3 - l

- i ) 'Ihe following NRC guidelines were also used in the ODCM review: 4 1.~ Regulatory Guide 1.109, Revision 1, " Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for the purpose of evaluating Compliance with

                             .10 CFR 50, Appendix Ld

, 2. Branch Technical Position, " General Contents of the Dose Calculation Manual."5 As specified in NUREG 1302, the ODCM is to be developed by the licensee to document i the methodology and approaches used to calculate offsite doses and maintain the operability of l the radioactive effluent systems. As a minimum, the ODCI.I thould provide equations and methodology for the followmg. l

                        . Alarm and trip setpoints on effluent instrumentation
                        . Ilquid effluent concentrations in unrestricted areas                                    {
                        .   -Oaseous effluent dose rates at or beyond the site boundary
                        . Liquid and gaseous effluent dose contributions
                        . Liquid and gaseous effluent dose projections.

In addition, the ODCM should contain flow diagrams that represent plant systems and that i define the treatment paths and the components of the radioactive liquid and gaseous management l systems. A description and the location of samples in support of the environmental monitoring i program are also needed in the ODCM. NRC regulations require that the ODCM be a stand- l alone document. . I i i 4

3. RADIOACTIVE EFFLUENT RELEASE ROUTES Liquid and gaseous effluent releab routes for PBAPS are discussed in this section together with the current monitoring methodology. He descriptions in Revision 5 of the PBAPS ODCM, dated July 1,1993, were reviewed. Comments on the monitoring methodology description, its clarity, and the adequacy of the monitored release routes are included in this section.

3.1 Liquid Effluent Release Routes Liquid and solid wastes from both Units 2 and 3 are routed to a common radwaste building for collection and treatment. Radioactive liquid effluent releases from PBAPS Units 2 and 3 are discharged to the Conowingo Pond through the circulating water discharge canal in a batch mode. Liquid effluent may be released to the environment from five tanks: two waste sample tanks, a floor drain sample tank, and two laundry drain tanks. He concentration of the wastes at the

       ---discharge point into the pond complies with the requirements of 10 CFR 20.

Peach Bottom Atomic Power Station Units 2 and 3 share a common discharge point for radioactive liquid releases. Liquid radioactive waste is discharged from the Liquid Radwaste System through the circulating water discharge canal and is processed on a batch basis. Accidental discharge of radioactive liquid waste from the radwaste system is controlled through engineering designs such as redundant valving, monitoring instrumentation, alarms for abnormal conditions, and procedural controls. In addition, the discharge method is through intentional pumping of the waste into the discharge canal. Figure 1 shows a schematic diagram of the PBAPS Units 2 and 3 liquid radwaste treatment system. The diagram clearly shows the source terms and liquid flow path, and associated ! monitors. However, it should also identify the monitor labels and indicate which of these l l monitors incorporates a termination of release capability in addition to the provision for alarms. j ! In addition, it should be made clear whether all potential release pathways are monitoced and are 1 included in the ODCM calculations. I 3.2 Gaseous Effluent Release Routes l l Radioactive gaseous effluents from PBAPS Units 2 and 3 are collect 9d by the gaseous i radwaste system and released to the atmosphere through the plant stack (Figure 2). In addition, l there are radioactive gaseous releases from the ventilation exhaust waste treatment system, as shown in Figure 3. De gaseous effluent sources from both units are the main condenser air ejectors, the startup pumps, and the gland seal condenser. However, the roof vent and associated monitor are not shown in the diagram. The height of the plant vent stack should be specified in l the ODCM to support the calculation of air doses.

Many of the radioactive and potentially radioactic gaseous effluents from PBAPS Units 2 and 3 are released via the monitored plant vent. However, exhausts from the following sources l

are released through the reactor building vent stack: refueling floor (U3), reactor building (U3), reactor building equipment cell (U2), recombiner building (U2 and U3), turbine building area (U3), turbine building equipment cell (U2), turbine operating floor (U3), radwaste area (U2), 5

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(mAusi @ rtLTER Figure 3. Ventilation exhaust waste treatment system at PBAPS. 8

I radwaste equipment cell (U2), chemistry laboratory (U2), laboratory and toilet (U2), and fume hood (U2). Exhausts from the following sources are filtered prior to release into the reactor building vent stack: the reactor buildin*k equipment cell (U2), recombiner building (U2), turbine building equipment cell (U2), radwaste equipment cell (U2), chemistry laboratory (U2), and fume j hood (U2). l Radioactive gases from the air ejectors for each main condenser are passed through a l 30-minute holdup system to provide sufficient decay for 16N,190 and short lived noble gases. In addition, the 30-minute holdup allows the reactor operators time to take appropriate actions in the event of excessive release rates of noble gases. Off. gases from the air ejectors are then filtered through high-efficiency filters prior to release through the plant stack. Gland seal and 16 19 startup vacuum pump gases are held up for 1-3/4 minutes to allow for decay of N and 0 prior to release through the plant stack. . Specific comments regarding the description of the gaseous radwaste system are the following:

1. The filtration system associated with the reactor building equipment cell (U2), I recombiner building (U2), turbine building equipment cell (U2), radwaste equipment cell (U2), chemistry laboratory (U2), and fume hood (U2) should be described in the ODCM.

2. 'Ihe ODCM should include a description of the gaseous radwaste system in addition to )

t!ie schematic diagram. l l l 1 i i 9

l l* ' l l l . I 4

4. EVALUATION He PBAPS ODCM is a supporting document for the PBAPS 13. De ODCM should be a stand-alone document and should include a detailed presentation of the calculational methodology and models usal, including a complete tabulation of all values assigned to each parameter used in the calculations.

The PBAPS ODCM should include descriptions and methodology for liquid and gaseous effluents sampling and analysis, X/O and D/Q calculational methods, performance of the Land Use Census and the Interlaboratory Comparison Program, and necessary reporting actions when major changes are made to the liquid and gaseous radwaste treatment systems. b 4.1 Liquid Effluent Monitor Setpoints

;           PBAPS TS 3.8.B.3.C requires that the radioactive liquid effluent monitoring instrumentation be operable with its alarm / trip setpoints set to ensure that the limits of TS 3.8.B.1 are not exceeded. Section II.A of the ODCM indicates that the alarm and trip setpoint for each liquid effluent radiation monitor include factors of 1.25 and 1.35, respectively, to allow for analysis, calibration, and instrument errors.

Specific comments on setpoint calculations for the liquid effluent monitor setpoints are the l following: l

1. The specific monitors with alarm and/or trip capabilities should be identified in the ODCM.

2. He general methodology for calculating alarm and trip setpoints for liquid radwaste monitors is well explained in the ODCM. However, the actual calculational methods for the derivation of the conversion factor Eff W/RW is omitted and should be included in the ODCM.

3. It is not clear how the 1.25 and 1.35 factors were determined.

4.2 Gaseous Effluent Monitor Setpoints The PBAPS TS 3.8.C.4 requires that the radioactive gaseous effluent monitoring instrumentation be operable with its alarm / trip setpoints set to ensure that the limits of'IS 3.8.C.1 are not exceeded. Section II.C of the ODCM directs the user to perform the calculations in accordance with Section IV.A of the ODCM. Specific comments on setpoint calculations for the gaseous effluent monitor setpoints are the following:

1. The roof vent and its associated monitor (s) should be shown in the ODCM.

10

L

2. Sections II.C and II.D have the same title. We suggest that the title for II.C be

, changed to " Radiation Monitor Setpoint Determination for Gascous Radwaste," and l that the title for II.D be cha$ged to " Flow Monitors Setpoint Determination for

. Gaseous Radwaste.": 3. The limiting condition for operation of the off-gas treatment system as described in 1

TS 3.8.C.4 does not clearly indicate that the instantaneous release rate limits are being

met. His should be clarified.

i 4.3 Concentrations in Liquid Effluents 4 PBAPS 'I3 3.8.B.1 requires that "the concentration of radioactive material released to areas I at and beyond the SITE BOUNDARY shall be limited to the concentration specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases and 2 x 10 4pCi/mL total activity concentration for all dissolved or entrained noble gases." j Section III.A of the PBAPS ODCM directs that each tank of radioactive waste be sampled prior i to release to quantitatively analyze for identifiable gamma ray emitting radionuclides as specified l in TS Table 4.8.1. } The calculational methodology for determining the radionuclide concentrations in liquid j radwaste effluents should be included in the ODCM. 4.4 Dose Rates Due to Gaseous Effluents PBAPS TS 3.8.C requires that the dose rate in areas at and beyond the SITE BOUNDARY i due to radioactive materials in gaseous effluents released from the two reactors at the site shall be limited to s500 mrems/yr to the whole body and s3,000 mrems/yr to the skin for noble gases, and to si,500 mrems/yr to any organ for 131I , 3H, and for all radionuclides in particulate form with half-lives greater than 8 days. Section IV.A of the PBAPS ODCM describes the methodology for calculating dose rates due to gaseous effluents. The elevated finite plume model is used in the calculations for dispersion. He ODCM should provide the basis for using the elevated finite plume model for dose rate calculations. 4.4.1 Dose Rates Due To Noble Gases Section IV.A.1 of the ODCM provides two methods for calculating total body dose rates and skin dose rates due to noble gas releases. He first method, the goss release method, assumes that all noble gases released consist of the most limiting nuclide, Kr, for the total body dose due I to vent and stack releases and skin dose due to vent releases. This method is used for calculation of dose rates due to noble gases during normal operations of the plant. He second method, isotopic analysis method, is based on the results of noble gas analysis as required by specification 4.8.C.1.a. His second method is used when the noble gas releases are close to the limbs as calculated by the previous method. De second method uses data that more accurately reflects 11

4 i i the actual releases. He methodology presented for both methods is in general agreement with l Section 5.2.1 of NUREG.0133. ne ODCM should include the calculational methodology and calculational details for the ! values of V,i K,i and B, shown in Table IV.A.1 and used in the methodology section IV.A.1.b. 4.4.2 Radionuclides Other Than Noble Geses

He PBAPS ODCM section IV.A.2 provides two methods to determine dose rates to any -

4 organ due to3H, 131,133, I I and radioactive materials in particulate form with half. lives greater 1 than 8 days. He first method, the 131 I method, is based on the 131 I releases and a correction factor to calculate the dose rate from all nuclides released. His method is used to calculate dwe , rates under normal operations since 131 I is the dominant contributor to dose rates to the thyroid, which is the critical organ pathway, ne second method, the isotopic analysis method, is based on the identification and quantification of all applicable radionuclides. His second method is used ! when 131 I releases are minimal, such as during a long-term shutdown. Under these conditions, ! the lung replaces the thyroid as the critical organ. The methodology presented is within NRC guidelines. l Here are no comments on this section. 4.5 Dose Due to Liquid Effluents i i PBAPS TS 3.8.B.2 requires that the dose or dose commitment to a MEMBER OF THE i PUBLIC from radioactive materials in liquid effluent releases from the two reactors at the site to areas at and beyond the SITE BOUNDARY shall be limited to s3 mrem to the whole body and

s10 mrem to any organ during any calendar quarter, and to s6 mrem to the whole body and s20

! mrem to any organ during any calendar year.

j. Section III.B of the ODCM provides the methodology for calculating total doses due to

! radioactive liquid effluents. In general, the methodology is in agreement with the NRC guidelines. Here are no comments for this section of the ODCM. 4.6 Doses Due To Gaseous Effluents J PBAPS TS 3.8.C.2 requires that the air dose at and beyond the SITE BOUNDARY due to j noble gases in gaseous effluents released from the two* reactors at the site shall be limited during any calendar quarter to s10 mrad for gamma radiation and s20 mrad for beta radiation, and

;        during any calendar year to s20 mrad for gamma radiation and s40 mrad for beta radiation.

Section IV.B of the ODCM provides the methodology for calculating the air dose due to noble

;        gas releases in plant gaseous effluents. The methodology provides two methods for calculating the air doses due to gamma and beta radiation from noble gas radionuclides. De first method, the gross release method, is used for normal plant ogrations and assumes that all noble gases j         released consist of the most limiting radionuclides:     Kr for gamma ray emitters and "Kr for beta
 ;.      ray emitters. He second method, the isotopic analysis method, relies on an isotopic analysis of 4

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t l.^*. the released noble gases as required by 'IS 4.8.C.1.a. Both methods are in general agreement

. with Section 53.1'of NUREG-0133.3 a

! ' Specific comments concerning the air dose calculational methodology as described in the ODCM are the following:

i. 1. - ne basis and justification for the (X/Q)y values used in the ODCM should depend

upon current meteorological data.

2.' The ODCM should clearly show the calculational methods for obtaining the terms Mi j and Bi in Section IVB.1.b and N i in Section IV.B.2.b. . 4.7 Dose Projections - PBAPS TS 4.8.B.4.a requires that doses due to liquid emuent releases to areas at and ! . beyond the SITE BOUNDARY shall be projected once per month in accordance with the j methodology and parameters in the ODCM. Section III.C of the ODCM states that the dose projection calculations for liquid emuents shall be performed using the methodology shown in 4

          - Section III.B of the ODCM. Section IV.D of the ODCM states that the projected dose

calculations for gaseous emuents shall be based on expected releases from plant operations. He: calculations are based on the methodologies for normal operations from Section IV.B.1 for
gamma air dose, Section IV.B.2 for beta air dose, and Section IV.C for the critical organ dose: (e.g., liver). The basis of why the liver is considered the critical organ should be included in the

!- ODCM. f 4.7.1 Liquid Effluent Dose Projections i There are no comments on the liquid effluent dose projections methodology. 4.7.2 Geseous Effluent Dose Projections There are no comments on the gaseous emuent dose projections methodology. 4.8 Diagrams of Effluent Reiease Routes The ODCM contains three diagrams pertaining to emuent release routes. The first diagram clearly shows the offgas radwaste treatment system. He third shows the liquid radwaste treatment and effluent pathways, and the second diagram shows the ventilation exhaust waste treatment system. Comments on the diagrams were noted previously. 4.9 Total Dose

                   .PBAPS TS 3.8.D requires that the annual (calendar) dose or dose commitment to any .              ;

MEMBER OF THE PUBLIC from all uranium fuel cycles within 8 km is limited to s75 mrem to the thyroid and to s25 mrem to the total body or any other organ over the calendar year. 13

l- Section V.A of the ODCM describes the methodology to assess the total dose from uranium cycle at PBAPS. He methodology presented in the ODCM does not include any detail except with the statement that "it is in accorddhce with ANSI /ANS 6.6.1-01979." He ODCM should 1 clearly state the details of the methodology and the calculational methods and include a I comparison of the methods used with those described in Appendix E of Regulatory Guide 1.109.4 ' t 4.10 Environmental Monitoring Program ! PBAPS TS 3.8.E requires that Environmental Monitoring Program sampling shall be 4 performed in accordance with the sampling and analysis methods shown in Table 4.8.3.a. l Section VII.A of the ODCM requires the collection of environmental monitoring samples shown in Tabic VII.A.1 from the locations shown on Figures VII.A.1,2,3, and 4. The analysis of these samples are in accordance with the methods shown in Table VII.A.1. There are no comments related to the Environmental Monitoring Program. l 4.11 Land Use Census Here are no references to performing a Land Use Census in the PBAPS ODCM, and no justification is provided for this omission . 4.12 Interlaboratory Comparison Program There are no references to performing an interlaboratory comparison program in the PBAPS ODCM. and no justification is provided for this omission. 14

l. 1 I i t f

5. TECHNICAL FINDINGS Primary deficiencies and suggestions are summarized below in four categories of decreasing importance. Items in Category A identify the most serious deficiencies, including omissions that cause uncertainty about the methodology used in the ODCM. Category B contains deficiencies that are less serious than Category A, and Category C contains minor deficiencies and editorial recommendations. Category D contains suggestions for change:: the licensee may wish to make to simplify calculations, update data, or remove excess conservatism from the methodology.

Category A ne items in this category should be addressed promptly. Some items identify errors or omissions that result in erroneous calculsted doses and dose rates. Others identify omissions or inappropriate values that may result in exceeding release rate limits or insufficiently documenting reported doses.

1. De calculational methodology for determining the radionuclide concentrations in liquid radwaste effluents should be included in the ODCM.

2. The ODCM should provide the basis for using the elevated finite plume model for dose rate calculations.

3. The ODCM should include the calculational methodology and calculational details for the values of V,i K i, and B j shown in Table IV.A.1 and used in the methodology section IV.A.1.b.

4. Section V.A of the ODCM describes the methodology for assessing the total dose from uranium cycle at PBAPS. The methodology presented in the ODCM does not include any detail except with the statement that "it is in accordance with ANSI /ANS 6.6.1-1979." The ODCM should clearly state the details of the methodology and the calculational methods and include a comparison of the methods used with those described in Appendix E of Regulatory Guide 1.109.

5. The PBAPS ODCM should include descriptions and methodology for liquid and gaseous effluents sampling and analysis, X/O and DiQ calculational methods, performance of the Land Use Census and the Interlaboratory Comparison Program, and necessary reporting actions when major changes are made to the liquid and gaseous radwaste treatment systems.

Category B The items below concern information that should be added to make the ODCM complete, prevent etroneous interpretation of the methodology, or to correct erroneous methodology.

1. The general methodology for calculating alarm and trip setpoints for liquid radwaste monitors is well explained in the ODCM. However, the actual calculational methods, i

15 l i l

., i

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including the derivation of the conversion factor Eff W/RW, is omitted and should be included in the ODCM. , ,

2. The offgas filtration system associated with the reactor building equipment cell (U2),

recombiner building (U2), turbine building equipment cell (U2), radwaste equipment cell (U2), chemistry laboratory (U2), and fume hood (U2) should be described in the ODCM.

3. He ODCM should include a description of the gaseous radwaste system in addition to the schematic diagram.

4. Specific liquid effluent monitors with alarm and/or trip capabilities should be identified in the ODCM.

5. It is not clear how the 1.25 and 1.35 factors were determined for the liquid effluent monitor setpoint calculations.

6. The limiting condition for operation of the off-gas treatment system as described in

                   'IS 3.8.C.4 does not clearly indicate that the instantaneous release rate limits are being met. This should be clarified.

7. De basis and justification for the (X/Q), values used in the ODCM should be based

;                   upon current meteorological data.

8. The ODCM should clearly show the calculational methods for obtaining the terms Mi and Bi in Section IVB.1.b and Ni in Section IV.B.2.b.

9. The basis of why the liver is considered the critical organ for dose projections should be

. included in the ODCM. Category C The items in this category indicate omissions and editorial deficiencies that are not libly to l

cause significaat problems.
1. Figure 1 shows a schematic diagram of the PBAPS Units 2 and 3 liquid radwaste treatment system. The diagram clearly shows the source terms and liquid flow path, and associated monitors. It should also identify the monitor labels and indicate which of these monitors incorporate a flow shutoff capability in addition to the provision of alarms.: 2. Radioactive gaseous effluents from PBAPS Units 2 and 3 are collected by the gaseous radwaste system and released to the atmosphere through the plant stack and reactor building vent stack. He gaseous effluent sources from both units are the main condenser air ejectors, startup pumps, and the gland seal condenser. However, the roof vent and associated monitor are not shown in the diagram.

4 16 i 1

i l*.

3. The height of the plant vent stack should be specified in the ODCM to support the cilculation of air doses since ,the ODCM should be a stand-alone document.

4. There are no references to performing a Land Use Census in the PBAPS ODCM, and no justification is provided for this omission.

5. There are no references to performing an interlaboratory comparison program in the PBAPS ODCM, and no justification is provided for this omission.

Category D The following items concern methodology and parameters that the licensee may wish to change because the change may simplify calculations, remove unnecessary conservatism in the calculations, or make use of more recent data. Sections II.C and II.D have the same title. We suggest that the title for II.C be changed to

           " Radiation Monitor Setpoint Determination for Gaseous Radwaste," and that the title for II.D be changed to " Flow Monitors Setpoint Determination for Gaseous Radwaste."

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. 6. REFERENCES

1. Title 10, Code of Federal RegulatYons, Part 50, " Domestic Licensing of Production and Utilization Facilities." ,

1

2. NUREG 1302, Standard Operating Procedure for Radiological Effuent Controls for Pressurized Water Reactors,' August 198C.

3. NUREG-0133, Preparation of Radiological Effluent Technical Specificatioru for Nuclear l Power Plants, A Guidance Manualfor Uses of Standard Technical Specifications, October 1978.

4. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Ro'utine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with to CFR Part 50, Appendix I."

5. " General Contents of the Offsite Dose Calculation Manual," Revision 1, Branch Technical Position, Radiological Assessment Branch, NRC, February 8,1979.

k 6 18 s}}

L-95-037, Evaluation of Peach Bottom Atomic Power Station Units 2 & 3 Odcm,Rev 5

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