ML20082L769

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Effluent & Waste Disposal Semiannual Rept 1991, Reflecting Gaseous effluents-summation of All Releases for First & Second Quarter
ML20082L769
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/30/1991
From:
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
Shared Package
ML20082L764 List:
References
NUDOCS 9109040338
Download: ML20082L769 (17)
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{{#Wiki_filter:TABLE 1A 

                                }7FIEENT AND WASTE DISICSA1. SIM1 ANNUAL REIORT 1991 CASFIKIS 17FLUl:NTS-SItHATION OF All Rt2. EASES Unit        Quarter     Quarter   Est. Total SEABROOK STATION                                       1             1         2       Error. I A. Fission & activation gases
1. Total telease C1 2.57 E+01 4.27 E-01 1.70 E01
2. Average release rate for period Ci/sec 3.31 E+00 5.43 E-02
3. Percent of technical specification lintit 2 2.31E-02(1) 1.33E-03 (2)

B. Iodinen

1. Total iodine-131 Ci 10. E ND. E 1.50 E01
2. Average release rate for period C1/sec ND. E ND. E
3. Percent of technical specification limit 2 1.13 E-05 1.16 E-02 C. Particulates
1. Particulates with half-lives >8 days Ci ND. E ND. E 1.80 E01
2. Average release rate for period C1/sec ND. E 10. E
3. Percent of technical specification limit Z 1.13 E-05 1.16 E-02
4. Gross alpha radioactivity Ci NA. E NA. E D. Trititan
1. Total release Ci 4.40 E-03 2.83 E+00 1.60 E01
2. Average release rate for period C1/sec 5.66 E-04 3.60 E-01
3. Percent of technical specification limit Z 1.13 E-05 1.16 E-02 ND = none detected (1) Based on the beta air dose.

(2) Based on the gaan air dose. l 9109040339 910929 PDR ADOCK 05000443 R PDR

TABLE IB EFFIEINT AND WASTE DISPOSAL SIMIANNUAL REIVRT 1991  ! i GASIXUS EFFLUENTS-ELEVATED RELEASES I 1 i I l CONTINUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter Nuclides Released 1 1 2 1 2

1. Fission gases krypton-85 Ci ND. E ND. E ND. E ND. E krypton-05m _

Ci 8.83 E-01 ND. E ND. E_ ND. E krypton-87 Ci ND. E ND. E ND. E ND. E krypton-88 Ci ND. E ND. E ND. E ND. E 4 xenon 133 Ci 8.86 E+00 ND. E 1.39 E-03 1.60 E-01 xenon-135 Ci 1.34 E+01 10. E 1.58 E-04 1.03 E-02 xenon-135m Ci ND. E ND. E 10. E ND. E xenon-138 Ci 10. E ND. E ND. E 10. E , , Others (specify) Ci ND. E ND. E ND. E ND, E Ci E E E E Ci . E . E . E . E unidentified Ci ND. E ND. E ND. E ND. E Total for period C1 2.31 E+01 ND. E 1.55 E-03 1.70 E-01 B. Todines iodine-131 Ci ND. E ND, E ND. E ND, E iodine-133 Ci ND. E ND. E ND, E ND. E iodine-135 Ci ND, E ND. E 10. E ND. E Total for period Ci ND. E ND. E ND, E ND. E C. Particulates 

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stfontium-89 Ci ND. E ND. E !ID. E ND. E , strontium-90 Ci ND, E ND. E ND. E ND. E cesium-134 C1 ND, E ND. E ND, E ND. E cesium-137 Ci ND, E ND, E ND. E ND. E 

     -barium-lanthanum-140                    C1       ND.      E    ND. E   ND.      E       ND. E Others (specify)                    Ci       ND.      E    ND,    E   ND.      E       ND. E Ci          . E     . E      . E        . E Ci          . E     . E      . E        . E unidentified                            Ci       ND.      E    ND. E    ND.      E       ND. E ND = none detected

i TABLE IC EFF1111NT AND WASTE DISICSAL SIMIANNUAL RE10RT 1991 CAS1HIS I:FFLUENTS-CP.UUND 1.EVEI. RELEASES CONTINUDUS MDDE BATCH MODE Unit Quarter Quarter Quarter Quarter Nuclides Released 1 1 2 1 2

1. Pission gases krypton _C1 ND. E ND. E ND. E 71D. E ,

krypton-85.T. Ci ND. E ND. E ND. E ND. E krypton-87 Ci ND. E ND. E ND. E ND. E  ; krypton-88 C1 ND. E ND. E ND. E ND. E  ! xenon-133 Ci ND. E ND. E ND. E ND. E  ? xenon-135 C1 ND. E ND. E ND. E TJD, E_ _ xenon-135m Ci ND. E ND. E ND. E ND. E xenon-138 Ci ND. E ND. E ND, E~ NI' . E Others (specify) Ci ND. E ND, E ND. E ND. E Ci . E . E . E . E Ci . E . E . E . E l unidentified Ci ND, E ND. E ND. E ND. E  ; Total for period Ci ND. E ND. E ND. E ND. E  ; B. Iodines  ; iodine-131 Ci ND. E ND. E ND. E ND. E , lodine-133 Ci ND. E ND. E ND, E ND. E iodine-135 Ci ND. E ND. E ND, E ~ND. E Total for period Ci ND, E ND. E ND. E ND, E C. Particulates strontium-89 Ci ND. E ND. E ND, E ND. E  ; strontium-90 C1 ND. E ND. E ' ND. E ND, E cesium-134 _Ci ND. E ND. E ND. E ~ LID. E_ i cesium-137 Ci ND. E ND. E ND. E ND. E i barium-lanthanum-140 _ Ci ND. E ND. E ND. E ND. E l Others (specify) Ci ND. E ND. E ND. E ND. E Ci . E , E . E . E Ci . E . E . E . E ~ unidentified Ci ND, E ND. E ND. E ND. E ND = none detected l. l l t I i i [ b 1

TABLE 2A i EFFIDENT AND WASTE DISPOSAL SIMIANNGAL REIMT 1991  ; i LIQUID EFF11&NTS-SIMIATION OF AI.L R12. EASES { Unit Quarter Quarter Est. Total 1 1 2 Error, ! A. Fission and activation products

1. Total release (not including tritium, C1 2.20 E-03 4.28 E-03 6.00 E00 gases, alpha)
2. Average diluted concentration during period Ci/ml 1.16 E.11 2.14 E-11
3. Percent of applicable limit 2 2.36E-03(1) 6.94 E-03(2)

[- l B. Tritium

1. Total release Ci 8.67 E+01 1.03 E+02 8.00 E00
2. Average diluted concentration during period C1/ml 4.56 E-07 5.15 E-07
3. Percent of applicable limit 2 2.36E-03(1) 6.94 E-03(1)

C. Dissolved and entrained gases 

                                                                                                            ~l
1. Total release Ci ND. E ND. E 1.90 E01 l
2. Average diluted concentration during period C1/ml ND. E ND. E
3. Percent of applicable lindt 2 NA. E NA. E i

D. Cross alpha radioactivity l i 1. Total Release Ci ND, E ND, E 1.00 E01 E. Volume of waste released (prior to dilution) liters 4.75 E07 5.17 E07 1.30 E00 l F. Volume of dilution water used during period liters 1.90 E11 2.00 Ell 9.00 E00 l l ND = none detected (1) Based on total body dose. (2) Based on the maximum organ dose.

TAhLE 2B EFF111DfT AND WASTE DISPOSAL SIMIANNUAL RENW.T 1991 LIQUID EFF11TDITS CONTINUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter 2 tNelides Released 1 1 2 1 strontium-89 C1 ND. E 14D. E ND. E ND. E strontitun-90 Ci ND. E ND. E ND. E ND. E Ci ND. E ND. E ND, E cesium-134 ND. E cesium-137 Ci ND. ND. E ND. E ND. E iodined31 Ci IF. E E ~ NO. E ND. __E 8.48 E-06 cobalt-58 Ci ND, E ND. E 1.80 E-03 2.82 E-0T cobalt-60 Ci ilD. E ND. E 7.76 E-05 7.84 E-05 iron-59 Ci ND. E ND. E 8.77 E-06 1.83 E-05 zinc-65 Ci ND. E ND. E 11D . E ND. E manganese-54 Ci ND. E ND. E 3.47 E-05 1.28 E-04 chr omium- 51 Cl ND. E ND, E 1.64 E-04 1.06 E-03 zirconium-niobium-95 Ci ND. E ND. E 1.09 E-04 5.87 E-05~ nolybdenum-99 Ci ND. E ND. E ND. E ND. E technetium-9%n Ci ND. E ND. E . 4.31 E-06 _7.93 E.06 Iv.r.itun-lanthanum-140 Ci ND. E ND. E ND. _E _ND. E_ ceriinn-141 Ci ND. E ND. E ND. E ND. E Other (specify) Ci IID. E ND. E ND, E _ ND . E Sodium-24 Ci . E . E NP. E 7.94 E-0_5_ ND, 2.03 E-05 Cesium-138 Ci . E . E_ E 7.86 E-06 Iodine-133 Ci . E . E ND. E Ci . E , E . E . E unidentified Di ND. E ND, E ND. E y. E flotalforperiod(above) l Ci lND. E lND. E l2.20 ~ E-03l4.28E-03l xenon-133 Ci ND. E ND. E ND. E ND. E " xenon-135 C1 ND. E ND. E ND. E' ND. E ND = none detected

T TAN.E 3 EFFIRENT AND WASTE DISIOSAL SIMIMMIAL REPORT 1991 SOLID WASTE AND 1RRADIATED 14fEL SilllMtNTS A. SOLID WASTE SIIIPITD OFFSITE FOR NRIAL OR DISICSAL (Not irradiatal fuel) Unit First Est. Total l 6-month Error, 2

1. Type of waste (No shipnents made) Period
e. Spent resins, filter sludges, evaporator m3 . E bottcras, etc. Ci . E . E
b. Dry camp essible vaste, contaminated m3 . E equip, etc. Ci . E . E
c. Irradiated components, control rods etc. m3 . E Ci . E . E
d. Other (described) m3 . E Ci . E . E
2. Estimate of najor nuclide composition (by type of vaste) l l l
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3. Solid Waste Disposition Numtmr of Shhrnent s Mode of Transportation Destinatis Nor.e B. IRRADIATED FUEL SIIIIMENTS (Disposition)

Number of Shig ents Mode of Transportation Destination None I- { 1

i Page 1 EFFLtlENT AND WASTE DISPOSAL SEMIANNUAL llEPollT Supplemental information 1991 First and Second Quarters Facility: Seabrook Station Unit i Licensee: Public Service Compariy of New llampshire, et.al.

1. ily,gylatory 1.imits A. Gaseous Effluents
a. Fission and activation gases: 5.0 mrad per quarter gamma air dose,10.0 mrad per quarter beta air dose.
b. lodines: 7.5 micm per quaiter to any organ,
c. Particulates, half-live; > 8 days: Particulates and iodines are included in step b,
d. Tritium: 7.5 mrem per quarter to any organ,
c. Liquid Effluents: 1.5 mrem per quarter total body and 5 mrem per quarter to any organ.
2. Maximum Permissible Concentrations Provide the MPC's used in determining allowable releases rates or concentrations,
a. Fission and activation gases: 1 MPC
b. Iodines: 1 MPC
c. Particulates, half-lives > 8 days: 1 MPC
d. Liquid effluents: 1 MPC
3. Ave ace EnerEY Not applicable.
4. Measurements and Approximations of Total fladioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
a. Fission and activation gases: Determined by gamma spectroscopy. Total error is based on stack flow error, analytical error and calculated sampling error.
b. Iodines: Determined by collection on charcoal wit h subsequent gamma spectroscopy analysis. 'lotal error is based on stack flow error, analytical error and calculated sampling error.

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c. Particulates: Determined by ccticetion on fixed filter with subsequent gamma spectroscopy analysis. Strontium is determined by composite analysis of filters by liqaid scintillation, gross alpha by proportional counier, and iron 55 by liquid scintillation. Total error is based on stack flow error, analytical error and calcuiated sampling error,
d. Liquid Effluents: Determined by gamma spectroscopy. A composite sample is analyzed for strontium by liquid scintillation, tritium by liquid scintillation, alpha by proportional counter, and iron 55 by liquid scintillation. Total error is based on the volume discharge error and analytical error.
5. Ilatch Releasn Previde the following information rela ng, to batch releases of radioactive materials in liquid and gaseous effluents,
a. L J 1 . umber of betch releases: 107
                  ?    Totd time for batch releases: 19538 minutes
3. Maximum time period for batch releases: 528 minutes
4. Average time period for batch release: 183 minutes
5. Minimum time period for a batch release: 35 minutes
6. Average stream flow during periods of release of effluent into a flowing stream: 1.53 E06 liters per minute.
b. Gaseous
1. Numbu of batch releases: 37
2. Total tirae period for batch releases: 41473 minutes
3. Maximum time period for a batch release: 7233 minutes 4 Average time period for batch releases: 1121 minutes
5. Minimum time period for a batch releases: 6 minutes
6. Abnormal Releases
a. Liquid
1. Number of releases: 0
2. Total activity releases: N/A
b. Gaseous .
1. Number of releases: 0
2. Total activity released: N/A

APPENDIX A Off-Site Dose Calculation Manual Reauirement: Technical Specification 6.13.2.b requires that licensee initia_ted changes to Part B of the Off Site Dose Calculatiuu Manual (ODCM) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. Resnonse: One revision was made to the ODCM during this reporting period. Revision 7 of the. ODCM (Enclosure 4, Attachment 1) was issued to address NRC Staff comments A.I through A.5 provided in a USNRC Letter dated January 31,1991, "Seabrook Offsite Dose Calculation Manual (TAC No. 77672)" (Enclosure 4; Attachment 2). The NHY response to the Staff's coriments was prov ded in NHY Letter NYN91053, dated March 29, 1991 (Enclosure 4, Attachment 3). Additional revisions to the ODCM are planned fer the sect,nd half of 1991 to address the remainder of the Staff's comments, nurriers B.4 through B.16, and to incorporate revisions to Part A of the ODCM that were approved by the NRC in July 1991. No changes wert. inade to the Radiological Environmental Monitoring Program during this reporting period. t L , W I I f t 

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APPENDIX Il Process Control Provram Reunirement: Technical Specification 6,12.2.a requires that licensee initiated changes to the Process Control Program be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the changes (s) were made. Response: No changes were made to the Process Control Program during this reporting p;riod.

APPENDIX C. Radioactive 1.iould Effluent Monitorine instrumentglign 1 Reuuirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.9 b. With less than the minimum number of channels operable for 30 days. Technical Specification 3.3.3.9.b requires that an explanation - for the delay in correcting the inoperability be provided in the next Semiannual Effluent. Release Report pursuant to Technical Specification 6.8.1.4 Resnonse: No radioactive liquid effluent monitors were out of service for more than 30 days during this reporting period. t J 

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APPL!NDIX D Radioactive Gaseous Effluent Monitorins Instrumentation 

                   - Recuirement:       Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical' Specification 3.3.3.10.b. ;With less than the minimum number of channels operable for 30 days, Technical Specification 3.3.3.10.b requires that an explanation for the delay'in correcting the inoperability be provided in the next Semiannual Effluent Release Report pursuant to Technical Specification 6.8.1.4.

Resoonse: Technical Specification 3.3.3.10 was never entered for more than 30 consecutive days during this reporting period. t e E 

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l. I APPENDIX E 2 1.lauid Holdun Tanks I Reauirement: Technical Specification 3.11.1.4 limits the quantity of radioactive material j contained in any temporary unprotected outdoor tank. Should the quantity- l of radioactive material in any temporary unprotected outdoor tank exceed l the limits.of Technical Specification 3.11.1.4, a description of the events ! - leading to this condition is required to be provided in the next Semiannual Effluent Release Report pursuant to Technical Specification 6.8.1.4.  ; Resnonse: No temporary tanks were in uso during the reporting period. < I-i. i 

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API'ENDIX F Radwaste Treatment Systems Reauirement: Technical Specification 6.14.1 requires that licensee initiated major changes to the Radwaste Treatment Systems (liquid, gaseous, and solid) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change was made. Resnonse: No major changes to Radwaste Treatment Systems were made during the reporting period.

APPENDIX G Unolanned Releases Reauirement: Technical Specification 6.8.1.4 requires a list and description of unplanned releases of radioactive materials in gaseous and liquid effluents made during the reporting period from the site to UNRESTRICTED AREAS. Response: No unplanned releases to UNRESTRICTED AREAS were made during the reporting period.

New llampshire Yankee August 29, 1991 ENCI.OSURE ? TO NYN-91133 

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4 i I During a review of the Seabrook Station Semi Annual Radioactive Effluent Release Report l1 1 1990 (Second Half), dated February 28,1990 several discrepancies were noted. In the fourth P ' quarter the liquid Cobalt-58 activity was overestimated due to a typographical error. This i- error resulted _in discrepancies in Table 2A, Liquid Effluent Summation Of All Releases and 1 

             - Table 28 - Liquid Effluents. This error also affected Table 4 of the Semiannual Effluent l               Waste Disposal Report dated March 29, 1991. Additionally, an error was found in the Average Diluted Concentration in Table 2A. These discrepancies caused erroneous reporting
. in the conservative direction. Revisions to the February 28, 1991, Semiannual Radioactiv j Effluent Release Report Table 2A and Table 2B are provided in Enclosure 2. Revisions to j- the March 29, 1991, Semiannual Effluent and Waste Disposal Report, Table 4 are provided j in Enclosure 3.
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