ML20212Q192
| ML20212Q192 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/30/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NLR-N86115, NUDOCS 8609040049 | |
| Download: ML20212Q192 (38) | |
Text
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Nh 1986 HOPE CREEK GENERATING STATION -
L SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-1 r
L The Energs/ Feople r DOCKET NO. 50-354 u OPERATING LICENSE NO. NPF-57 r
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NPF-57 REPORT NO. HCGS-RERR-1
': RADIOACTIVE EFFLUENT RELEASE REPORT l JUNE 28 - JUNE 30, 1986 I -
HOPE CREEK GENERATING STATION Public Servico Electric and Gas Company I
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1 HOPE CREEK GENERATING STATION I RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1986 I INTRODUCTION This report, HCGS-RERR-1, summarizes the releases of radioactive I materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period June 28, 1986 (initial criticality) to June 30, 1986.
Tne report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.7 of the Hope I Creek Technical Specifications. Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments are our responses to parts A-F of the " Supplemental Information" section of Regulatory Guide 1.21, Appendix B.
As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary' description of how measurements and approximations of the total activity discharged were developea.
To f acilitate determination of compliance with 40CFR190 require-ments, the following information on electrical output is provided.
HCGS generated 0 megawatt-hours of electrical energy (net) during the reporting period. HCGS commenced fuel load on April 11, 1986 and attained initial criticality on June 28, 1986.
Results of liquid and gaseous composites analyzed for gross
'g alpha, Sr-89, Sr-90, and Fe-55 were not available for inclusion in this report. The results of these composites will be t3
! provided in the next Radioactive Effluent Release Report.
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Part A. PRELIMINARY SUPPLEMENTAL INFORMATION 5 '
1.0 REGULATORY LIMITS 1.1 Noble Gases Release Limits The dose rate due to radioactive materials released in g gaseous offluents from the site to areas at and beyond g the site boundary shall be limited to the following:
For noble gases: Less than or equal to 500 g mrems/yr to the total body and less than or equal g to 3000 mrems/yr to the skin.
In addition, the air dose due to noble gases released E in gaseous effluents from the site to ateas at and E beyond the site boundary shall be limited to the following: g
,3 During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
1.2 Iodine, Particulates, and Tritium The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
For Iodine-131, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
In addition, the dose to a member of the public from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 3 days in gaseous effluents released from the site to g areas at and beyond the site boundary shall be limited to the following:
During any calendar quarter: Less than or equal -
to 7.5 mrems to any organ and, During any calendar year: Less than or equal to E 15 mrems to any organ. 5
1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be I limited to the concentrations specified in 10CFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For I dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per mililiter.
In addition, the dose or dose commitment to a member I of the public from radioactive materialc in liquid effluents released to unrestricted areas shall be limited:
During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and I During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radioactive releases.
- a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates,
- b. MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids.
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I 3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.
Release limits for the HCGS are not based upon average e ne rg y , hence, this section does not apply.
4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 Liquid effluents are monitored in accordance with Table 4.11.1.1.1-1 of the Technical Specifications.
During the period of record, all liquid wastes were routed to the sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be thoroughly mixed before sampling and analysis before any releases are made. Batch releases are defined as releases from equipment drain sample ,
tanks, floor drain sample. tanks, detergent drain tanks, and condensate storage tanks. There are no continuous liquid releases for this reporting period.
Specific activity from analyses were multiplied by the volume of effluent discharged to the environment in order to estimate the total licuid activity l 5
discharged.
The detection requirements of Table 4.11.1.1.1.-l of the Technicial Specifications are achieved or exceeded. Isotopes existing at concentrations below the achieved detection limit are treated as not being present.
l 4.2 Gaseous effluent streams are ruonitored and sampled in g
I accordance with Table 4.11.2.1.'2-1 of the Technical g Specifications. The north plant vent (NPV) and south plant vent (SPV) are the final release points for most A small quantity planned gaseous effluent releases.
of gaseous effluent will be released via the l
l Filtration, Recirculation, and Ventilation System (FRVS) vent during testing periods. The NPV and SPV g are continuously monitored for particulates, iodines, g and noble gases; the FRVS is continuously monitored for noble gases. The NPV and SPV have moving particulate and fixed iodine filters; the FRVS has fixed particulate and iodine filters. The filters are -
I changed and analyzed at least weekly when releases are in progress. The NPV and SPV are sampled monthly for noble gases and tritium.
The detection requirements of Tables 4.11.2.1.2-1 of g the Technical Specifications are achieved or exceeded. Isotopes existing at concentrations below I the achieved detection limit are treated as not being present.
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l I i I Continuous mode gaseous releases are quantified by routine (monthly) sampling and isotopic analyses of the plant vents. Specific activities for each isotope l
detected during the routine sampling are adjusted I using the radiation monitoring readings to obtain an average concentration for the period. This average concentration is then multiplied by the total vent I flow volume for the entire sampling period in order to estimate the normal continucus release of radioactivity through the plant vent.
Batch mode gaseous releases (primary containment purge) are quantified by pre-release sampling and isotopic analyses. Specific activities for each I isotope detected are multiplied by the total purge flow volume in order to estimate the batch release of radioactivity through the plant vent.
4.3 The estimated total error of reported liquid releases ,
is within 25%.
The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estinated total error of the reported batch gaseous releases is within 50%.
Error estimates for releases where sample activity is below the detectable concentration levels are not l included since error estimates at the LLD are not defined.
The estimated total error of reported solid releases I is within 15%.
5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.
I' 6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.
Part B. GASEOUS EFFLUENTS See fummary Tables lA thru 1C.
Part C. LIQUID EFFLUENTS See Summary Tables 2A and 2B.
Part D. SOLID WASTE See Summary Table 3.
Part E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data 1.e., food production, milk production, feed for milch animals, and seafood production.
The doses were calculated using methods described in Regulatory Guide 1.109. Individual doses from batch and continuous releases were calculated using the annual g average historic meteorological dispersion coefficients as g l described in the Offsite Dose Calculation Manual.
! Population doses were calculated using the meteorological dispersion coefficients for the six month interval from January through June, 1986.
Liquid Pathways The only isotope released via the liquid pathway was KR85m (2.24 uCi). The calculated total body dose to the population within fifty miles of the site was 1.05E-09 person-rem. The calculated average total body dose to the i
l population within fifty miles of the site was 1.94E-13 mrem.
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I Air Pathways There were no airborne releases during this reporting period; therefore, there are no air pathway doses to I report.
Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.- One method for comparing TLD measurements is by comparison with preoperational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island.
TLD's at onsite locations 2S-2 and SS-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.88 and 4.53 mrads/ month respectively. The values for stations 2S-2 and SS-1 are within the statistical variation '
associated with the preoperational program results.
All offsite monitoring locations remained within preoperational ranges until May 9, 1986 when activity from the Chernobyl reactor accident was detected. All elevated measured values were consistant with activity from the Chernobyl reactor and indicator stations were no higher than control stations. The annual radiological report will discuss the details of the measurenents. It is concluded that the elevated measurements are not the result of plant effluents.
It should be noted that the nearest resident is 3.5 miles away. It can thus be concluded that there was no measurable dose to any offsite location from direct radiation.
Part F. METEOROLOGICAL DATA Cumutative joint wind frequency distributions by atm-ospharic stability class at the 300 foot elevation are provided for the first and second quarters of 1986 as i
Tables 5 and 6.
Part G. MONITOR INOPERABILITY During the period of interest, the Cooling Tower Blowdown Radiation Monitoring System (CTB-RMS) was out of service from April 17, 1986 until May 20, 1986. The reason for this extended period of inoperability was a failed sample pump. The work order to replace the pump in kind was misplaced in the work order system and resulted in the 30 l
day limit being exceeded. A design change request has been issued to replace the pump with one of an improved design.
M M M M M M - M HOPE CREEK GENERATING STATION TABLE lA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES lst 2r.d Est. Total Units Quarter Ouarter Error %
A. Fission & Activation Gases Ci
- 0.00E+00 5.00E+01
- 1. Total release
- 0.00E+00
- 2. Average release rate for period uCi/sec.
Percent of technical specification limit %
- 3.
- 0.00E+00 (T.S. 3.11.2.2(a))
B. Iodines Ci
- 0.00E+00 5.00E+01
- 1. Total iodine-131
- 0.00E+00
- 2. Average release rate for period uCi/sec.
Percent of technical specification limit (1) %
- 3.
- 0.00E+00 (T.S. 3.ll.2.3(a))
C. Particulates Ci
- 0.00E+00 5.00E+01
- 1. Particulates with half-lives > 8 days
- 0.00E+00
- 2. Average release rate for period uCi/sec.
- 3. Percent of technical specification limit (1) %
- 0.00E+00 (T.S. 3.ll.2.3(a))
Ci
- 5.00E+01
- 4. Gross alpha radioactivity (2)
D. Tritium ci
- 0.00E+00 5.00E+01
- 1. Total release
- 0.00E+00 Average release rate for period uCi/sec.
2.
Percent of technical specification limit (1) %
- 3.
- 0.00E+00 (T.S. 3.11.2.3(a))
- No releases for this period.
(1) Iodine, tritium, and particulates are treated as a group.
(2) Alpha analyses are not available for inclusion in this report.
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HOPE CREEK GENERATING STATION TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986 GASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated releases during this reporting period.
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HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Quarter Quarter Est. Total Error, %
A. Fission and activation products ;
- 1. Total release (not including
- 0.00E+00 2.50E+01 tritium, gases, alpha) Ci
- 2. Average diluted concentration during period uCi/ml 0.00E+00
- 3. Percent of applicable limit
- 0.00E+00 (T.S. 3.ll.1.2.(a)) %
B. Tritium *
- 1. Total release Ci 0.00E+00 2.50E+01
- 2. Average diluted concentration during period uCi/ml
- 0.00E+00
- 3. Percent of applicable limit %
(T.S. 3.11.1.1)
- 0.00E+00 C. Dissolved and entrained noble gases
- 1. Total release Ci
- 2.24E-6 2.50E+01
- 2. Average diluted concentration .
during period uCi/ml
- 9.74E-12
- 3. Percent of applicable limit %
- 4.87E-6 (T.S. 3.11.1.1)
D. Gross alpha radioactivity
- 1. Total release Ci
- G.00E+00 2.50E+01 E. Volume of waste release (prior to dilution - Batch Release) liters
- 9.50E+05 F. Volume of dilution water used
- 2.50E+01 during entire period liters 2.38E+08
- No releases for this period.
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HOPE CREEK GENERATING S* ATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986 LIOUID EFFLUENTS I CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Strontium-85 Ci Strontium-89 Ci Strontium-90 Ci Fluorine-18 Ci ,
Sodium-24 Ci Chromium-51 Ci I Manganese-54 Iron-59 Cobalt-57 Ci Ci Ci I Cobalt-58 Cobalt-60 Zinc-65 Ci Ci Ci Ci I
Zirconium-95 Niobium-95 Ci Niobium-97 Ci Molybdenum-99 Ci I Technetium-99M Iodine-131 Iodine-133 Ci Ci Ci I Iodine-135 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Lanthanum-140 Ci Antimony-122 Ci Antimony-124 Ci Antimony-125 Ci Tin-113 Ci Total for period (above) Ci 0.00E+00 Tritium Ci 0.00E+00 Xenon-133 Ci Xenon-135 Ci Krypton-85m Ci 2.24E-6 Argon-41 Ci Krypton-87 Ci i
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HOPE CREEK GENERATING STATION E TABLE 3 EFFLUENT AND WASTE DISPCSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986 SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS There were no solid radioactive waste or irradiated fuel shipments this reporting period.
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HOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT gs JUNE 28 - JUNC 30, 1986 E i
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: N/A ,
- 2. Type of release: Gas !
3' . Number of releases during the 1st Quarter: N/A
- 4. Total time duration for all releases of type listed above: l minutes N/A
- 5. Maximum duration for releases of type 1isted above:
minutes N/A
- 6. Average duration for all releases of type listed above:
minutes N/A
- 7. Minimum duration for release of type listed above:
minutes N/A
- 8. Average stream flow ( dilutiori flow) during the period of release: N/A I
I O
, HOPE CREEK GENERATING STATION TABLE 4A
( con ' t)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I BATCH RELEASES ONLY
- 1. Dates: June 28 - June 30, 1986
- 2. Type of release: Gas
- 3. Number of releases during the 2nd Quarter: 0
- 4. Total time duration for all releases of type listed above:
minutes N/A
- 5. Maximum duration for releases of type listed above:
minutes N/A
- 6. Average duration for all releases of type listed above:
minutes N/A
- 7. Minimum duration for release of type listed above:
minutes N/A
- 8. The average stream flow (dilution flow) during the period of release: N/A I .
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I HOPE CREEK GENERATING STATION I
TABLE 4B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986 ,
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED
- IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: N/A
- 2. Type of release: Liquid
- 3. Number of releases during the 1st Quarter: N/A
- 4. Total time duration for all releases of type listed above: ,
minutes N/A
- 5. Maximum duration.for releases of type listed above:
minutes N/A
- 6. Average duration for all releases of type listed above:
minutes N/A
- 7. Minimum duration for release of type listed abover minutes N/A
- 8. Average stream flow (dilution flow) during the period of release: N/A gpm I
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, I HOPE CREEK GENERATING STATION ~
TABLE 42
( con' t)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JUNE 28 - JUNE 30, 1986
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l
BATCH RELEASES ONLY 4
- 1. Dates: June 28 - June 30, 1986
- 2. Type of release: Liquid
- 3. Number of teleases during the 2nd Quarter: 20
- 4. Total time duration for all releases of type listed above:
1.87E+03 minutes
- 5. Maximum duration for releases of type listed above:
1.18E+02 minutes
- 6. Average duration for all releages of type listed above: F 9.3E+01 minutes
- 7. Minimum duration for release of type listed above:
8.lE+01 minutes
- 8. Average stream flow (dilution flow) during the period of release: 3.34E+4 gpm I
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M M M M M M M Table 5 g2 8 of 8) 1184-3/84 JOINT SISTRISUTION OF WIND DIRECTION AND SPEED DES C#100n LAPSE RATE
! ARTIFICIAL ISLANS LOCATION 300FT ALL ST ASILITIES I I3GO-30FT3 I
SPEEDS (RI/Nel 25 PLUS Sun PERCENT 8-12 13-18 19-24 1-3 4-7 SUM PERCENT SUR PERCENT SUN PERCENT SUM PERCENT SUN PERCENT SUM PERCENT DIRECTION 0.3 141 4.6 39 1.8 45 2.1 25 1.7 4 3 0.1 23 1.1 5 0.2 1 0.0 79 3.7 l
N 04 32 1.5 30 1.4 84 3.9 NNE 2 0.1 9 33 1.5 9 0.4 0 0.0 2.9 0.0 9 0.4 32 1.5 0.2 0 0.0 63 i NE 1 0.4 20 0.9 30 1.4 4 59 2.8 ENE O 0.0 9 0.5 4 0.2 0 0.0 0.0 12 04 32 1.5 11 0.1 3 0.1 37 1.7 E O 0.3 8 0.4 15 0.7 2 88 4.1 ESE 2 0.1 7 1.1 32 1.5 to 0.5 11 0.5 5.2 SE 2 0.1 10 0.5 23 1.4 26 1.2 22 1.0 112 0.5 20 0.9 31 168 7.8 SSE 2 0.1 11 45 3.0 47 2.2 11 0.5 0 0.0 20 0.9 25 1.2 1.7 27 1.3 137 4.4 5
17 0.8 48 2.2 37 7.2 0.0 7 0.3 2.5 , 26 1.2 9 0.4 154 Ssw 1 40 1.9 54 80 3.7 1 0.0 24 1.1 0.4 7 0.3 SW 16 0.7 24 1.1 19 0.9 f, 9 1.0 152 7.1 WSW 5 0.2 28 40 1.9 33 1.5 21 w 7 0.3 23 1.1 1.3 36 1.7 42 2.0 235 11.0 0.5 53 2.5 87 4.1 2.2 344 14.1 7 0.3 10 110 5.1 48 NuW 10 0.5 34 166 134 4.3 0.2 209 9.8 NW 8 0.4 2.'1 , 81 3.8 55 2.4 4 NNW 5 0.2 19 0.9 45 20.4 312 99 2142 100.0 472 22.0 755 35.2 438 9, 44 2.1 219 10.2 f MISSING NOURS 18 l
CEAN WINE SPEtt 15.5 S PERCEKT 0.0 ISTAL NURSER OF CALM NOURS l
26 1
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Table 6 (Paga 8 of 8)
LAPSE RATE SEE C/1 DON ALL STASILITIES 4/46-6/86 JOINT 815TRIOUTION LOCATION 300ff OF UIND DIRECTI6N ANS SPEED (300-30ff)
ARTIFICIAL ISLANs SUN PERCENT 19-24 25 PLUS SPEEDS (RI#Nel 13-14 4-7 s-12 1-3 SUN PERCENT SUN PERCENT SUN PERCENT 124 6.0 SUN PERCENT SUN PERCENT 1.9 5 0.2 93 4.5 SUN PERCENT 1.8 39 6 0.3 DIRECTION 1.6 36 16 0.s 62 30 12 0.6 32 1.3 25 1.2 5 0.2 2.7 N O 0.0 0.9 26 16 0.8 9 0.4 0 0.0 56 0.1 18 24 1.2 0.0 65 32 NME 2 7 0.3 19 0.9 1 0.2 0 0.0 2.4 1 0.0 0.6 23 11 0.9 4 9 0.4 50 NE 0.0 13 1.2 18 3 0.1 172 8.4
' ENE O
14 0.T 25 11 0.5 24 1.2 9.6 4 0.2 0.3 18 0.9 3.1 43 2.1 1.0 197 E
0.1 7 18 64 2.6 20 135 6.6 2 0.2 36 3.3 5s 0.0 ESE 0.0 5 1.7 48 37 1.9 1 129 4.3 SE O 14 0.7 34 33 1.4 2 0.1 7.8 3 0.1 1.0 42 2.0 2.0
- 39 1.9 0.1 160 SSE 0 0.0 20 29 1.4 41 34 1.7 3 111 5.4
$ 15 0.7 2.1 56 2.7 0.4 0 0.0 155 7.5 l 3 01 1.1 44 46 2.2 9 0 0.0 l
SSW 1 0.0 2I 0.7 41 2.0 3.1 15 0.7 0.2 141 4.9 I
SW 0 0.0 15 59 2.9 63 34 1.7 5 218 10.6 WSW 17 0.8 2.0 44 2.1 2.6 30 15 185 9.0 1 0.0 0.8 41 3.3 57 0.3 W 16 48 2.5 6 WNW 1 0.0 0.7 48 '2.3 57 2.4 51 00 14 2.4 J
Nd 1 0.8 54 ,
0.0 17 NNW 0 9 100.0 5.7 2053 451 22.0 116 28.1 665 32.4 131
\ 11.0 576 n SSths Nova $
0.9 224 f
19 l
I l 14.7 REAN NIND SPEED 0.0 l
1 0 PERCENT
'leTAL NUReER OF CALM NOURS I
34 i
d 1
4 .
m
- - - ~ - - . _ ,,
?
s .
3 Public Service Electric and Gas Cornpany Ctrbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box 236. Hancocks Bnc:ge.NJ 08038 609 339-4800 Vice President -
f4uclear s August 29, 1986 NLR-N86115
,. a United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Dr. Thomas E. Murley Regional Administrator
Dear Dr. Murley:
RADIOACTIVE EFFLUENT RELEASE REPORT - 1 HOPE CREEK GENERATING STATION As required by Section 6.9.1.7 of Appendix A to the Operating Licenses for the Hope Creek Generating Station (HCGS), Unit No.
1, we hereby transmit two copies of the semi-annual radioactive Effluent Release Report, RERR-1. This report summarizes liquid and gaseous releases and solid waste shipment from the HCGS for the period January - June 1986.
Should you have any questions regarding this material, please feel free to contact us.
Sincerely, Attachment 1
4@
/
l
\
. r \
r -
r
'7 Dr. Thomas E. Murley 2 8-29-86 No. of Copies w/ attach.
C Director, Office of Inspection and Enforcement (6)
,\ U. S. - Nuclear Regula tory Commission c/o Distribution Services Branch, DDC, f Wa sh i ng ton , DC 20555 0 ~
Director - Of fice of Nuclear . Reactor. Regulation :(1)'
{ U.S. Nuclear Regulatory Commission"
\
\ . Washing ton, DC 20555 No. of Copies w/o attach.
Mr. D. Wagner (1)
Licensing Project Manager -
Mr. R. Borchardt (1)
Senior Resident Inspector
--