HNP-93-834, Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1993 & Rev 3 to Odcm
| ML18011A114 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/20/1993 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18011A116 | List: |
| References | |
| HNP-93-834, NUDOCS 9308310105 | |
| Download: ML18011A114 (34) | |
Text
ACCEI ERA DOCUMENT DIST BUTION SYSTEM REGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9308310105 DOC.DATE: 93/08/20 NOTARIZED:
NO DOCKET FACIL:50-400 Shearon Harxis Nuclear-Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION ROBINSON,W.R.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Semiannual Radioactive Effluent Release Rept 6
ODCM for 930101-0630.
DISTRIBUTION CODE:
IE48D COPIES RECEIVED:LTR L ENCLl SIZE: P. +
TITLE: 50.36a(a)(2)
Semiannual Effluent Release Reports D
NOTES:Application for permit renewal filed.
05000400 1
RECIPIENT ID CODE/NAME PD2-1 LA LE,N INTERNAL:
S EG 01 RGN2 FILE 02 EXTERNAL: BNL TICHLER,J03 NRC PDR COPIES LTTR ENCL 3
3 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD2-1 PD NRR/DRSS/PRPB11 RGN2 DRSS/RPB EGGG SIMPSONPF COPIES LTTR ENCL 1
1 2
2 2
2 2
2 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE} CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOURi MME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
D TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL 16 gr-
W
0 CSEE Carolina Power &LightCompany HARRIS NUCLEAR PLANT P.
O.
Box 165 New Hill, North Carolina 27562 AU62 0 )9B Letter Number:
HO-930141 HNP-93-834 U.S. Nuclear Regulatory Commission ATTN:
NRC Document Control Desk Washington, D.C.
20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:
In accordance with Technical Specification 6.9.1.4.,
the Semiannual Radioactive Effluent Release Report is attached for the Shearon Harris Nuclear Power Plant.
This report covers the period from January 1,
1993 through June 30, 1993.
4 Very truly yours, W. R. Robinson General Manager Harris Nuclear Plant MGW:kls Attachment cc:
Mr. S.
D. Ebneter (NRC - RII)
Mr. N. B.
Le (NRR)
Mr. J.
E. Tedrow (NRC - SHNPP)
MEM/HO-930141/1/OS1 9308310105 930820 PDR, ADOCK 05000400
.R, PDR
1 HI V
k
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1
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rt A
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I U.S. Nuclear Regulatory Commission Page 2
bcc:
Mr.
C.
W. Crawford Mr. H.
W. Habermeyer, Jr.
Mr. E.
M. Harris Mr. R.
D. Martin Mr. K. R.
McKee Mr. R.
M. Parsons Mr. L. S. Rowell Mr. B. H. Webster Mr. B.
C. White Nuclear Records INFO NLS File:
HI/A-2D (T. A. Head)
SHNPP Reg.
Compliance H-X-908 SHEEC Training Reference Library MEM/HO-930141/2'/OS1
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OS2 SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATIONMANUAL (ODCM)
Revision 3
Advance Change 3/7 Docket No. STN-50-400 CAROLINA POWER & LIGHT COMPANY PNSC Chairman's Approval Effective Date
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I OS2 2.2.1 Cumulation of Doses (continued)
The near-field average dilution factor for C< during any liquid effluent release "k."
Defined as the ratio of the volume of undiluted liquid waste released to the product of the di.luted volume from the site h(C.
gL discharge structure tc unrestricted receiving waters 3/3 times Ap, Ap is the site-specific applicable factor for the mixing effect, of,.the SHNPP discharge structure as defined in Section 4.3 in NUREG-0133.
Because of the low turnover of the Harris Lake (approximately once every 26 months),
the applicable factor Ap does not
- apply, and will therefore be set to a value of 1.
(Deleted)
(2'-la)
Thus:
F V
(Vz + Vz) x Ap (2. 2-2)
Where Ap 1 and U~ and U< are as defined in Equation 2.1-14.
In the case of a continuous secondary waste sample tank radioactive
- release, Cz the SWST composite sample activity.
For the
- NSW, Cz cooling tower basin concentration and V~
discharge from the cooling tower basin while V~
the flow from the makeup water cross-tie.
For a release through the Turbine Building Floor Drain Line to the waste neutralization
- system, C<
the Turbine Building floor drain sample I
activity (normally H-3 only),
Vq discharge from the Turbine Building floor drain line, and V~
the average flow during the period of the total Cooling Tower discharge.
The total Cooling Tower discharge is the sum of the Cooling Tower Blowdown flow and the Cooling Tower By-pass Line flow.
DCM/ODC-2 2-17 Rev. 3.0
t OS2 2.2.1 Cumulation of Doses (continued)
For the calendar year:
D 3 mrem total body 7
(2.2-6)
D s
10 mrem any organ 7
(2.2-7) where:
D Cumulative total dose to any organ t or the total body 7
from all releases, mrem:
The quarterly limits given above represent one-half the annual design objective of 10 CFR 50, Appendix I, Section II.A. If any of the limits in Expressions 2.2-4 through 2.2-7 are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC.
This report complies with Section IV.A of Appendix I, 10 CFR 50.
The calculations described in Section 2.2.1 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I on a "per-release" basis.
The NRC aproved program LADTAP II will be used to demonstrate compliance on an annual basis.
While there are substantial differences between the ODCM methodology and the methodology in LADTAP, conservative factors have been chosen for the ODCM methodology which will ensure compliance with the limits of 10 CFR 50 Appendix I.
2.2.2 Pro'ection of Doses Dose projections for this section are required at least once per 31 days (monthly) in Technical Specification 4.11.1.3.1 whenever the liquid radwaste treatment systems are not being fully utilized.
DCM/ODC-2 2-20 Rev. 3.0
ODCM Change AC 3/7 Description of Changes to the ODCM 1.
Change the value of the Applicable Factor (A) in the ODCM software from 95 to 1.
A, is a user-modifiable parameter.
2.
Section 2.2.1, Page 2-17 The definitions of Equation 4 are being changed to indicate the change in the usage of A~
3.
Section 2.2.1, Page 2-20 A new paragraph has been added to the end of Section 2.2.1 to provide additional clarification of the reason for using different methodologies.
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ODCM Change AC 3/7 In 1992, the NRC, via EG&G, performed a review of the SHNPP ODCM.
A primary finding in their review dealt with the amount of dilution that SHNPP could take credit for when making liquid effluent releases.
In reviewing their report, we found that their comments were valid, and that the SHNPP ODCM had been taking credit for too much dilution when calculating the doses due to effluent releases.
The effect of too much dilution was that doses calculated using the ODCM methodology were too low.
As a result of the review of the
The main change will be to reduce the amount of dilution used in the liquid dose calculations.
This will be accomplished by changing the Applicable Factor (A~)
from its current value of 95 to 1.
Changing A will increase the doses calculated on a per-release basis from liquid releases.
SHNPP committed to change the g component to a value of 1 by July 1, 1993.
This change to the ODCM will correct a non-conservative assumption that has been present since the ODCM was written.
While this change will increase the doses calculated by the ODCM on a per-releas'e basis, it will not have any impact on the doses calculated using the LADTAP program, since it uses a different methodology.
LADTAP is the program.used to calculate doses on an annual basis to demonstrate compliance with 10 CFR 50, Appendix I, while the ODCM is used as a "yardstick" to measure against the LADTAP doses.
This change will make the doses calculated using the ODCM higher than doses calculated using LADTAP.
4 The ODCM is an administrative program set up to control the release of radioactive effluents to the environment.
Nothing in the ODCM is concerned with the safe shutdown of the plant or the mitigation of any analyzed accident.
These changes to the ODCM do not have any affect on the probability of occurrence or the consequences of any analyzed accident.
No equipment important to safety is affected in any way, nor is any possibility of a different accident created.
This change does not have any impact on any Technical Specification margin of safety since there will be no change to the effluent mix or quantity.
Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 5
- Changes to the Environmental Monitoring Program Enclosure 1
- Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.1.c No changes to the Environmental Monitoring Program were made during this Report period.
New sampling locations were identified during the Land Use Census and will be included in the next Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 5
- Changes to the Environmental Monitoring Program Enclosure 2
- Land Use Census Technical Specifications 3.12.2.a 3.12.2.b An annual Land Use Census performed in June of 1993.
As a result of the
- census, Table 3.2.2 of the ODCM will be revised.
This table provides the distances to the nearest residents,
- gardens, milk and meat animals in each of the 16 sectors'he changes which occurred between 1992 and 1993 are shown in Table 1. Many of the differences in the distances are related to our use of a global positioning system (GPS) in 1993.
The GPS provides greater accuracy than the method employed in past years.
The 1993 receptor locations and exposure pathways were used in conjunction with historical HNP-meteorology and a Gale code source term to compare the dose estimates between 1992 and 1993.
On this basis, the likely most exposed person continues to be the teenager in the SW sector at 4666 meters.
A resident has been included in the S sector for the first time.
Although the resident is just outside the 5-mile radius, they have been included in the data because of the prevailing winds at the site.
A new nearest resident-was also detected in the SB sector.
Using the GPS, nearest garden locations with the highest D/Q values are in the NNB and the NE sectors.
We currently sample in the NNE and NNW sectors, so a sampling point in the NE will be added to the radiological environmental monitoring program.
Table 1,summarizes the locations of the nearest
- resident, milk animal,
- garden, and meat animal in each of the 16 compass sectors.
Comparison with the 1992 land use survey indicates the following:
A.
The nearest residence in the ENB and SB sectors were closer in than in 1992 and a resident was included in the S sector.
B.
New gardens were observed in the ESE. and S sectors and the nearest gardens in the E, SE,
- SSE, and NW sectors were closer in.
C.
Meat animals were observed in the WNW and S sectors in 1993.
Table 2 summarizes the type of meat animal at the closest location of the 16 compass sectors.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 TABLE 1
DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE HARRIS NUCLEAR PROJECT (HILES)"
SECTOR EXCLUSION BOUNDARY 1.32 RESIDENCE 1992 1993**
2.2 2.2 MILK ANIHAL 1992 1993**
2.2 2.2 GARDEN 1992 1993**
2.2 2.8 HEAT ANIHAL 1992 1993*"
2.2 2.2 NNE 1.33 1.8 1.9 1.7 1.7 3.1 2.2 ENE 1.33 1.33 2.3 2.3 3.6 1.8 2.3 3.8 2.3 3.6 2.3 2.3 1.33 1.9 1.8 4.7 2.0 2.2 2.0 ESE SE SSE 1.33 1.33 1.33 1.36 2.7 4.3 4.4 2.6 2.6 4.2 5.3 4.7 4 ~ 4 4 ~ 1 4.6 4.3 5.3 4.4 4.2 4.3 4.1 5.3 SSW SW WSW 1.33 1.33 1.33 3.9 3.9 2.8 2.9 4.3 4 ~ 5 3.9 3.9 2.8 2.9 4.3 4.5 WNW 1.33 1.33 2.8 2.1 3.0 2.3 2.9 3.1 2.1 2.3 2.9 3.1 2.6 NW NNW 1.26 1.26 1.5 1.6 2.1 2.4 3.8 2.7 1.7 2.0 3.8 3.7 1.7 2.0
- Distance estimates are + 0.1 miles except at the exclusion boundary.
- Sector and distance determined by Global Positioning System.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 TABLE 2 NEAT ANIMAL TYPE AT NEARESI'OCATION TO HHP BY SECTOR SECTOR DISTANCE (MILES)
MEAT TYPE OWHER NHE 2.2 2.2 2.3 BEEF/HOGS/CHICKENS BEEF/CHICKENS CHICKEHS
- GOODWIN, WOODROW JAMES REST HOME LEE ENE ESE SE SSE 2.0 4.2 4.1 CHICKENS/BEEF CHICKENS CHICKENS HARRIS, H.
MCLEAN, E.
TAYLOR, M.
SSW 5.3 CHICKENS/DUCKS REYNOLDS SW WSW WNW NNW 3.1 2.6 3.7 2.0 CHICKENS HOGS HOGS BEEF HILL, A.
RUSH STONE, D.
GOODWIN, WINSTON
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 6
- Additional Technical Specification Responsibilities : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service
> 30 Days During this Report Period No liquid effluent monitoring instrumentation specified in Technical Specification Table 3.3-12 was inoperable for greater than 30 Days during this Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2
- Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service
> 30 Days During this Report Period No gaseous effluent monitoring instrumentation specified in Technical Specification Table 3.3-13 was inoperable for greater than 30 Days during this Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 3
- Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4
- Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1993 to June 30, 1993 Appendix 7
- Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste System during this Report period.
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