ML20135D031
| ML20135D031 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/31/1996 |
| From: | Mckeen A POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20135D029 | List: |
| References | |
| DPV-01.02, DPV-1.02, NUDOCS 9703050019 | |
| Download: ML20135D031 (6) | |
Text
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCUMENTS AND VENDOR PROCEDURES RADIOLOGICAL EFFLUENT CONTROLS AND
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OFFSITE DOSE CALCULATION MANUAL
- I DVP-01.02 REVISION 4 REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE
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MEETING NO.
DATE t
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i (W) k kbJ 9iM DATE APPROVED BY:
RESPONSIBLE PROCEDURE OWNER
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DATE APPROVED BY:
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GEt RXL MANAGE V August 1, 1996 EFFECTIVE DATE:
FIRST ISSUE O FULL REVISION O LIMITED REVISION E INFORMATIONAL USE TSR TECHNICAL CONTROLLED PORC i
PERIODIC REVIEW DATE:
9703050019 970228 PDR ADOCK 05000333-R PDR
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PROCEDURE
SUMMARY
SHEET RE9.NO.
REASON FOR CHANGE 4
1)
Per ACTS Item 19716, revised Steps 3.3.1 and 4.3.2.A (Part 2 of DVP-01.02) to require that an implementation plan be developed for ODCM revisions that affect setpoints. This is a Corrective Action for LER-96-001 which dealt with the stack low range monitor setpoint.
2)
Minor editorial corrections.
i 3
1)
K-f actor of 2.5 was based on 1989 data. K-factor of 1.2 is based on 1994 and 1995 data.
2)
New setpoint limit calculated by dividing release rate of 300,000 Ci/sec by new k-f actor of 1.2 pCi/sec/ cps.
3)
Provide clarification of worst case as stated in the ODCM.
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DVP 01.02 l
RADIOLOGICAL EFFLUENT CONTROLS AND l
OFFSITE DOSE CALCULATION MANUAL
- i l
l PARTI RADIOLOGICAL EFFLUENT CONTROLS (REC)
1.0 INTRODUCTION
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1.1 Purpose This Radioactive Effluent Controls Program (REC) was added to the Offsite Dose Calculation Manual (ODCM) in response to NRC generic letter 89-01. The program intent is to conform with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public as low as reasonably achievable.
Generic letter 89-01 described the NRC's determination that the Radiological Effluent Technical Specification (RETS) should be simplified to improve Technical Specifications (TS) by implementing programmatic controls into the TS and procedural details into the ODCM.
The REC program relocates the procedural details of the RETS into the ODCM. The RETS provide the current requirements for effluent controls. The REC program may provide effluent control af ter the plant technical specifications are ammended to l
relocets the programmatic and reporting requirements of the RETS into the j
Admir.istrative Controls section of the Technical Specification.
i 1.2 Document Revision Overview This is Revision 4 of the ODCM under the procedure designation of DVP-01.02.
There were 9 revisions under the previous procedure designation of CDP-15. This revision constitutes the 13th revision of the ODCM since its inception as Rev. O of CDP-15.
Rev.No.
4 Page 1 of REC
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DVP-01.02 RADIOLOGICAL EFFLUENT CONTROLS AND OFFSITE DOSE CALCULATION MANUAL' PART 11
1.0 INTRODUCTION
1.1 Purpose i
This manual provides the methodology to calculate radiation doses to individuals in the vicinity of the James A. FitzPatrick Nuclear Power Plant. It also provides methodology for calculating effluent monitor set points and allowable release rates to ensure compliance with the Technical Specifications. Appendix B, of the New York Power Authority, James A. FitzPatrick Nuclear Power Plant.
l Docket Number 50333, and 10 CFR 20 release criteria, t
1.2 Methodologies and Parameters The ODCM follows the methodology and models suggested by the " Guidance Manual For Preparation of Radiological Effluent Technical Specifications for i
Nuclear Power Plants" (NUREG 0133 October 1978) and " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I" (Regulatory Guide 1.109, i
Revision 1 dated October 1977). Simplifying assumptions have been made and justified where applicable to provide a more workable document for 1
implementing the Technical Sp'ecifications, Appendix B, requirements. Alternate calculating methods to those presented here may be used provided the general methodology is similar, well documented and the results are more precise.
Additionally, as available, the most up to-date revision of the Regulatory Guide 1.109 dose conversion f actors and site specific environmental transfer f actors may be substituted for those currently included and used in this document.
1.3 Document Revision Overview This is Revision 4 of the ODCM under the procedure designation of DVP-01.02.
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There were 9 revisions under the previous procedure designation of CDP-15.
This revision constitutes the 13th revision of the ODCM since its inception as Rev. O of CDP-15.
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l Rev.No. 4 Page 1 of ODCM
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3.3
' Determination of Setpoints for Radioactive Liquid Effluent Monitors 3.3.1 Requirements l
Technical Specifications, Appendix B, Section 2.1.a requires that the radioactive liquid effluent monitor be operable and set to initiate an alarm and/or trip in the event that the limits of Technical Specifications, Appendix B, j
Section 2.2 are approached. The alarm and/or trip set points shall be determined and adjusted by the methodology which follows. The set point values should be applied above normal background levels.
l The alarm set point for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR 20, Appendix B, Table ll, Column 2 applied at the unrestricted area boundary where the discharge tunnel flows into Lake Ontario.
l An implementation Plan as defined in AP-02.04 shall be initiated and included j
in any ODCM revision whenever the methodology for calculating liquid i
setpoints is changed and the change in methodology results in a new 2
calculated setpoint.
l 3.3.2-Methodology The alarm set points do not consider dilution, dispersion, or decay of radioactive material beyond the unrestricted area boundary (i.e., the alarm j
setpoints are based on a concentration limit at the end of the discharge j
tunnel).
I 3.3.3 Radwaste Liquid Effluent Monitor i
A sample of each batch of liquid radwaste is analyzed for 1-131 and a.
other principal gamma emitters prior to release. The fraction F of t
i 10 CFR 20, MPC limits and the minimum required dilution factor to i-achieve F = 1 is determined in accordance with the preceding section t
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for the activity to be released. For cases other than minimum dilution calculation, F <0.5.
t b.
A conservative alarm and/or trip setpoint (pCi/ml) is determined in accordance with the following equation.
Eq. 3-3 S = 0.5 x S Ft Where:
The alarm and/or trip set point above background corresponding to S
=
' the limiting concentration of undiluted liquid effluent (pCi/ml).
Page _,1_Q_ of ODCM Rev.No. 4
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= $. 7 '.. a k
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l The sum of skin dose rate contributions DR
=
SMN (mrem /sec) from all noble gas nuclides from all concurrent releases, i
4.3.2 Set Point Determination a.
Requirements t
To comply with Technical Specifications, Appendix B, Section 3.2.a(1),
the alarm / trip set points are established to ensure that the noble gas releases do not exceed the appropriate cumulative (or gross) noble gas l
release rate limit specified in Limited Analysis Approach -Instantaneous Noble Gas Release Rate.
An implementation Plan as defined in AP-02.04 shall be initiated and included in any ODCM revision whenever the methodology for calculating gaseous setpoints or gaseous monitor k-factors are changed and the change to the methodology or k-factors results in a new calculated setpoint.
i b.
Methodology This section describes the methodology for determining alarm / trip set points for the stack and vent gaseous release pathways. To allow for multiple sources of releases from different or common release points, the allowable operating set points will be administratively controlled to
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allocate a percentage of the total allowable release to each of the j
release sources. The cumulative noble gas release rate limit for the i
stack (elevated) release is 3.0E+5 pCi/sec. The individual release rate limits for the other gaseous release points (assumed to be vent releases), are based upon an allocated percentage of the cumulative vent release rate limit (6.98E+4 pCi/sec).
The sum of the four vent release points cannot exceed 6.98E+4 pCi/sec.
The setpoint release rates for the vents follow.
Setpoint Release K-factor Setpoint Release Point Rate (uCi/sec)
(uCil/(sec-com)
Limit (com)
Turbine 42,000 0.56 75,000 Building Reactor 9,600 0.32 30,000 Building -
Refuel Floor 11,100 0.37 30,000 Radwaste 5,100 0.17 30,000 Building Rev.No. 4 Page 43 - of ODCM