ML20082L800
| ML20082L800 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 06/30/1991 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20082L795 | List: |
| References | |
| NUDOCS 9109040370 | |
| Download: ML20082L800 (23) | |
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VElulONT YANKEE NUct.. Erit POWER ColtPORATION VEllMONT YANKEE NUCl. EAR PowElt STATION VEllNON, VEIOlONT 4 l i _ . _a
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!l l EFFLUENT AND WASTE DISPOSAL SIMIANNUAL REPORT FOR jE FIRST AND SECOND QUARTERS, 1991 ii lE i l I I l VERMONT YANKEE NUCLEAR POWER STATION I 8851R I I i . - . . - . - . . . - . - . . . . - . . . . - - - . . . . _ . - - - . - - . - . . _ - . _ . . _ . . _ . _ . - . . . _ - . . . . _ . _ . . . . - _ . , . . . . . . . . . .
a IABLLIA VennonLYankee l Eff.l uen t an d_Was t e_Di s po s nLS emi annua LRepor t Fitst_and_Sccond_ Quarters._1991 Gaseouslffluenta - Summation _oLAlLReleases J , Unit Quarter Quarter Est. Total 1 2 ErInr. %
)
A. Fission and Activation Gases l
- 1. Total release Ci 8.07E+02 7.67E+02 11.00E+02
_ 2._ Average _ release..rnte_ lor J etiod__uci/sec 1,03Et02__9.11Et0L ___3 JercenLoLInch._. Spec . limit _II) 5 2,80Et0.0___2.05Et00_
.1 B. Iodines
- 1. Total Iodine-131 C1 4.15E-03 1.19E-02 .t5.00E+01
* ~l_2 uAv e r a g e_r e l e a s e . _ r a t ed o rantind___uc ils er___5,28 E 0!4 1.52E-03_
- 3. PrrcenLoLIcclLi_SntculiFlt _(2) % 2 33EtD0 8._02Et00_
t l C. Particulates
- 1. Particulates with T-1/2 ) 8 daya C1 2.27E-03 1.80E-03 15.00E+01
- 2. 4yerage._I11enac_.raic_ for._perind utilaec 2.8SE-04 2,19E-04_
s __._32_FercentoLIcch,_ Sum _ limit % (3.1 (3) A _Grosa_ alpha _rndicactlylty C1 2 A2E-06 213fi E-J6_ l i D. Tritium
- 1. Total release Ci 3.37E+01 2.09E+01 t5.00E+01 3 $___luAverage._ release _.rnte_for_ period _ ucilnec 3 t01Et00__2265EtDD_
. 3. fcccentoLIech _Speculimit % (11 (3)
(1) Technical Specification 3.8.F.1.a for gamma air dose. (2) 'Iechnical Specification 3.8.G.1 for dose f rom I-131, I-133, Tritium, and radionuclides in particulate form. (3) Per Technical Specification 3.8.G.1, dose contribution from Tritium and particulates are included with I-131 above in Part B. ND Not detected at the plant stack.
-- _ - _ - _________-mm_ _ __._m. _ _ . _ _ _ , .
I . I4BLE._13 Vermontlankee Efflu en t _andJa sic _Di. spas aLSemiannuaLRe po r1 Firs tand_Second_ Quar 1 cts._1911 Gascous.ELLluents _Elevatedlelease ' (1) Continuous _Mude Batchlade Nuclides_RcicaEcd UniL Quarter Quarter Quarter Quarter ' 1 2 L_.EiSSion_ Gases Krypton:85 Ci ND ND 4,jlE+00 4 13Ei.00 l Krypton-83m C i_
-l
- =
Krypton-87 __._Kryp t onrBfL_ Ci Ci 2 iBE Q1 1,12E+01 2.3 bet 01 L18Et01 Xenon _133 C1 _.5 d ZEtEO 5.97Et00 ___Kenon-135 Ci _ L 2hE+01 2.10E+01
$ Ci 1.25E+02 ,g _ Xenon-U;m
__ Xenon:135 Ci __1J7E+02 5.97EiO2 5.62EiO2 Q,30E+00 Unidentified C1 1. 71Et01_ TolaLinr_ period Ci 8,DZEAD2 7 dZEt02 l 2.Jodines b l5E 03 1.1 m 02 I ._ lodine-13L ___ lodine-131 lodinc._135 Ci C1 C1 1.3.9I-02 7.19E-Q2 3.53E-Q2 7,ASE-Q2 __IntaLior period Ci 9.39E-02 1.22E-01 4 L_1 articulates 1.03E-03 i __ Strontium:89 Ci___ __1.19E-04 8.55E-06 I Strontium-90 Cesium-ll4 Cesium-137 Ci C1 Ci 5.75E-06 1.Q9E-05 2.03E-05 6.20E-06 7.20E Q6 Barium-Lanthanum-140 Ci 1 12E-03 1 13E-03 Manganeae:54 Ci 5.jhE-06 1.38E-05 i Chromium-51 C1 1.UE-04 ND Cobalt-60 Ci 8 dbE-06 5.16E QS 4.40E-06 6.30E-Ob Cerium lAl C1 Unidentifled C1 l (1) There were no batch mode gasecus releases for this reporting period. ND Not detected at the plant stack. 'I lI 8851R l il
,' IAllLE_1C Vermont _Yankcc r E f I lue n Land _Was Le_Di spo s aLSemiannuaLhepo rt ( firs tand.Second_Quartera._lH1 Gascous. Ef fluents _ ._ Ground _LevcLKeleases There were no routine measured ground level continuous or batch mode gaseous releases during the first or second quarters of 1991. 8851R
IABl&_lD VermonLlankee E LilutnL and_W a ate _Di s po s a LS emiannuaL Repo rt k rit a t_and_ S econd_ Quar t e rs ,_.1911 Gaseous _Ilfluent u Ronront_incleleanes There were no nonroutine or accidental gaseous releases during the first or second quarters of 1991. 8851R
E TAliLIL2A Vermont Yankee Ef f luent and. Wasttt PisposnLSemiannuallepor t Elrs L nnd_ Second_ Quart ers ._1991 Liquid Ef fluents __ Sunscation _of All Relcasco There were no liquid releases during the first or second quarters of 1991. I I ll 5 I i i i I I 8851R I
IAl>LE 2D Vermont Jankee Ef fluenLand h'aste_ Disposal _ Semiannual Report ( first.and.Second_ Quarters._1991 Liquid _Eifluento_- Nontoutine_. Releases { J There were no nonroutine or accidental releases during the first or second quarters of 1991. I 1 1 I I I I l I 1 l l BH51R
IADLE_3 VermonLlankee E fi luca Land 3aa t e_ Dis po s a LS emi annua LRe po r t First and _Second_ Quarters.,.1991 S o l id_Wa s t e _and_I r radiat e d_fuc LShipmen ts t A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel) Unit 6-Month Est. Total l'eriod Irror.3
- 1. Type of Waste
- a. Spent resins, f11ter sludges, evaporator m3 1.95E+02 bottoms, etc. Cl 1.35E+03 17.50E+01
- b. Dry compressibic waste,'cIo~iitaminated m3 1.89E+02 equipment, etc. Ci 2.81E+01 +7.50E+01
- c. Irradiated components, control rods, m3
_ ___ etci. C1
- 2. Estimate of Major Nuclide Composition (By Type of Waste):
~__a. _Silyer - 110m _l10hE01 Xcnon_r_131m %1ASE0L Americlum _2k131,90E-03 Xenon - 133 1 1 001:0 L
_._.__rarium - 1A0.__%120E:02_ Iint - 63 3135EiDL Cnrium _1kl % A DDE-03 b2 Si her_2 l10m__1 1 151-O L ___ CerlunL:_L44 1 1 00E:03 Americium _2hil 1 00 E03_ Carbon - 14 JA 3 der 01 Carbon. _l4 % 1 50E02._ Curium - 242___.3 1 80E 02. Curium _ _ZA2 1 1 00 E03_ __ Curium. _24h %_1.00E-03 Curtum - 2hh % lt00 E03__ Cobalt _38 1 1 09E-01 Cobalt - 58 % 2 2hE0L _ Cobalt - 60 1 1 26Et01 __ Cobalt - 60 % A D3E10 L Chromium __5L__lldDEt00 Chromium _:lL_%_6. 50E_QL Cesium.el3h % A 93Et00 Cealum _l3A % 1 92E:0 L __ Cenium - 131___%_LL9EiO1 Cealum - 137 % 2.41EiDL Irca - 55 1139EtDL_ Iron _ _55 %Ab8Et0L . _ Iron - 33 %160E02 Iran _59 %.3,83E-O L liydrogen_ _l ___1 1 ADE-02 liydrogen -3 % 1 AB E01 _ Iodine - 129 1100E _03_ Iodine _c l29 %_Lt30E02__ Iodine - 13L___l112E-01 Manguncoe - 5A_l13kEiDQ__ lanthanum - IkO l 1 10E-02 Nichium - 95 %l105E0L Eanganese _5A_l_3J0Et00 Nickel _- 63_. _312ZE_0L Niobium _ _95. %1ADE02 Flutonium - 23831 DOE 03._. Elohlum - 97 %_ 1 kOE-02 fintonium - 239_11DDE-03__
, Nickel : 33 _1_3tBBEtH0 Plutoniunt-24.LlldhhDL Ilutoniunt. _2383100E 0L__ Strontium - 90_31D3E_QL
_Elutonium_- 2393 1 00 h003 Iechnetium - 993 1 10E-02_ Plutonium - 241 %11AE_0L Zinc _J5_ % 3.02Et00__ 2 Antimony - 12L%AQ0E:03 _Lirconium __95_.l_ZdQE:0L strontium - 90 % A 19E-01 _____Stcontium ._92_l100E02 Iechactium - 993 1 h0E 02 l
IAELL3 (Continued) e I ! 3. Solid Waste Disposition: NumbettoLShipments Mode _ oLIransportation Destination 50 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information
- 1) Class of solid waste containers shipped: 71A (Unstable), 15A, 23B, 3C
- 2) Types of containers used: 20 Type A, 92 Strong-Tight Container
- 3) Solidification agent or ebsorbent: None 8851R
I ' AfIENDIK A j I EEFLU ENLANDJASILDISf0 SAL _S12ilANNUAL RE PORT !l l Supplemenial_Informatinn firstand_Second_ Quarters._l991 E Facility: Ve rmonLYankee Euclear_FowerJ.tation I Licensec: VermonLYankee_Huticar_Enver Corpntation lA. Technical Specification Limits - Dose and Dose Rate ig Ie chais a LSrc c if i c ation_and_C ats gary Limil j n. Nobic_Graes 3.8.E.1 Total body dose rate 500 mrem /yr 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Gamma air dose 5 mrad in a quarter 3.8.F.1 Gamma air dose 10 mrad in a year 3.8.F.1 Beta air dose 10 mrad in a quarter
]
i 3.8.F.1 Beta air dose 20 mrad in a year
- b. lodine:13L._ Iodine 133.._lritium_sud ladionuclides in_f ar11tulatr_Ectm31thlalf-Lites Gr. cater _.lhan_6_ Days I
3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter { 3.8.G.1 Organ dose 15 mrem in a year
- c. Liquids 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 mrem in a year 3.8.B.1 Organ dose 3 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year A-1 8851R u
)
- L 2A. Technical Specification Limits - Concentration
? [ Ic c hnicaLS pe cific atiun_and_C at e gory Limit
- a. Nobic_ Gases No MFC limits
- b. Iodine-131._ Iodine 133. Tritinm_and Radionuclides.in. Parti.culatel orm_With llalf-Liyca_Greattr_ Ihan_B_ Days : No MPC limits l
- c. Liquids 3.8.A.1 Total fraction of MPC excluding noble gases (10CFR20, Appendix B, Table II, Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 uC1/cc
- 3. Average Energy Provided below are the average energy (E) of the radionuclide mixture in f releases of fission and activation gases, if applicable,
- a. Average gamma energy: 1st Quarter 1.12E+00 MeV/ dis 2nd Quarter 1.11E+00 MeV/ dis
- b. Average beta energy: Not Applicable 4 Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
A-2 8851R l
L a. Fission and Activation Gases J L Stack-continuous monitors nonnally show less than detectable releases of fission and activation gases. Therefore, to determine the level of releases, gas grab sarnples are drawn at the stack { monthly or when the noble gas monitors show an increase. The grab samples are analyzed by gamma spectroscopy to determine the isotopic composition and resultant release rate. The error .- involved in these steps may be approximately +100 percent.
- b. lodines Continuous isokinetic samples are drawn from the plant stack through a particulate f11ter and charcoal cartridge. The f11ters and cartridge are removed weekly (if releases are less than 4 percent of the Tech Spec limit), or daily (if they are greater than 4 percent of the limit), and are analyzed for radioiodine 131, 132, 133. 134, and 135. The error involved in these steps may be approximately 150 percent.
- c. Particulates I
The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately t50 percent.
- d. Liquid Effluents Radioactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liquid effluents released. For each batch, station records are retained of the total activity (mC1) released, concentration (uci/ml) of gross 1
A-3
radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River. { p Each batch of radioactive liquid effluent released is analyzed for gross gamma and gamma isotopic radioactivity. A monthly s proportional composite sample, comprising an aliquot of each batch released during a month, is also analyzed for tritium, SR-89 SR-90. gross beta and gross alpha radioactivity, in addition to gamma spectroscopy. There were no liquid releases during the reporting period.
- 5. Batch Releases
- a. Liquid There were no routine liquid batch releases during the reporting period.
I b. Gaseous i There were no routine gaseous batch releases during the reporting period.
- 6. Abnormal Releases
- a. Liquid i There were no nonroutine liquid releases during the reporting period.
- b. Gaseous There were no nonroutine gaseous releases during the reporting period.
A-4 8851R
J- ' - APPENDIX B LIQUID H01. DUP TANKS Re.quir.ement : Technical Specification 3.8.D.1 limits the quantity of { radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the lift.its of Technical Specification 3.8.D.1, a description of
- the events leading to this condition is required in the next - Semiannual Effluent Release Report per Technical Specification 6.7.C.1.
Response: The limits of Technical Specification 3.8.D.1 were not exceeded
, during this reporting period. .I 1
1 l I 4 I I I l B-1 8851R
9 P APPENDIX C RADIDACTIVE LlQUID 13Ti,UENT MONIT0hlNG INSTRUMENTATION Kequir cipent : Radioactive liquid elfluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1. If an inoperable radioactive liquid clfluent monitoring instrument is not returned to operable status priot to a telease pursuant to Note 4 of Table 3.9.1, an explanation in t.he next Semlannual Ef fluent llelease lieport of the reason (r.) f or delay in correcting the luoperability are required per Technical Specification 6.7.C.I. Response: Since the requitements of Technical Specification Table 3.9.1 governing the operability of radioactive liquid etiluent inonitoring insttumentation were met for this reporting period, no response is required. C-1 8851R
_' APPENDIX D J RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Semiannual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.1. Response: Since the requirements of Technical Specification Table 3.9.2 governing the operability of radioactive gaseous ef f luent monitoring instrumentation were met for this reporting period, no response is required. D-1 8851R
E AFPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I Re.quirement : The Radiological Environmental Monitoring Program is conducted in accordance with Technical Specification 3.9.C. With milk samples no longer availab1e from one or more of the sample locations required by Technical Specification Table 3.9.3, I Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Report: (1) identify the cause(s) of the sample (s) no longer being available, (2) identify the new location (s) for obtaining available replacement samples, and (3) include revised ODCM figure (s) and table (s) reflecting the new location (s). I Response: The control milk sampling location, "nt-20. Ranney Farm," was replaced with "D1-24, County Farm." The Ranney Farm recently I- went out of business and was replaced pursuant to Technical Specification Table 3.9.3, Footnote a. Since silage samples are collected at milk sampling locations, pursuant to Technical Specification Table 3.9.3, the contro1 silage sampling location, "TC-20. Ranney Farm," was also replaced with "TC-24, County Farm." The revised Off-site Dose Calculation Manut.1 (01CM) figure and table are included in Appendix H of this report. I I I I I I E-1 I 8851R
APPENDIX F ! 1AND USE CENSUS Requirement: A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a location (s) which yields at least a "O percent greater dose or dose commitment than the values curreatly being calculated in Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report. Response: The 1991 land use census was not performed during t is reporting period. It will be completed during the next reporting period (second half of 1991). I I I l I l l l l F-1 8851R
L* APPENDIX G PROCESS CONTROL PROGRAM Requircluent : Technical Specification 6.12.A.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made. Response: There were no licensee-initiated changes to the Process Control l Program during this reporting period. .l l a y I i I I I . I I G-1 8851R
J APPDiDIX H d OFF-SITE DOSE CALCULATION MANUAL [ L Requirement: Technical Specification 6.13.A.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) - be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (c)
]) was made effective.
i Response: The licensee-initiated changes to the ODCM were as follows:
- 1. In the Introduction, " Chemistry and Health Physics Supervisor" was changed to " Chemistry Supervisor and Radiation Protection Supervisor", and the responsibility of the administration of the septic waste program described in Appendix B was assigned to the Senior Environmental Program I Manager.
- 2. The following changes were made to Sectirn 4
" Environmental Monitoring Program":
I a. In Section 4.1., "Intercomparison Program," " Yankee Envfronmental Laboratory" was changed to " Yankee Atomic Environmental Laboratory."
- o. In Section 4.1, the description of Yankee's participation in the EPA's Intercomparison Program was changed from "all the species and matrices routinely analyzed" to "all appropriate species and matrices offered by the agency" to more accurately reflect the YAEL participation in the program, since the samples that may be analyzed are limited to those of fered by the EPA.
I H-1 i 8851R
- c. In Section 4.2, " Airborne Pathway Monitoring", the statement ".. 13 years of operational data (as of q 1985)" was updated to ".. 18 years of operational data (as of 1991)."
- d. In Table 4.1 . the control grc2nd water sampling l
i Station "WG-21. Brattleboro CC" was replaced with { WG-22. Skibt.;owsky Well." The Brattieboro CC well
! became inaccessible as a regular sampling site and was replaced pursuant to Technical Specification Table 3.9.3 Footnote a The map in Figure 4-3 was changed appropriately.
- c. In Table 4.1., the enntrol milk and silage sampling locations. "TM-20 and TC-20 Ranney Farm" were replaced with "IN-24 and TC-24, County Farm." The Ranney Farm recently went out of business and was replaced pursuant I to Technical Specification Table 3.9.3 Footnote a.
map in Figure 4-3 was changed appropriately. The
- f. The foott.otes at the end of Table 4.1 were renumbered and consolidated into one location.
The " Distance" and " Direction" coltann headings on I g. Table 4.1 were edited, with a clarification added in Footnote (6).
.i . The "DR-33" label on Figura 4-4 was moved from the ,.Je of Rt. 142 to the side of Governor ilunt Road to inors accurately reflect the TLD's acttal field placement.
The TLD locaticn itself was not changed.
- i. The station location labels on the maps in Figures 4-1 through 4-6 were replaced to afford a neater appearance. With the exceptio1 of the changes noted above, no changes were made to the content of the maps.
11 - 2 8851R
9 The above-noted changes have no relationship to the perf ormanen of dose or setpoint calculations, and therefore, will not reduce the accuracy or reliability of dose or setpoint determinations.
~
The revised ODM pages for the above revision are attached. Included is the Title / Signature page for revision 10 that documents that the revisions were reviewed and approved by the Manager of Operations (M00) and the Plat. Operations Review Comrnitt- lIORC). I d I I I I I l l I 11 - 3 8851R _ _ _ _ _}}