ML19325C173
| ML19325C173 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1989 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17056A271 | List: |
| References | |
| NUDOCS 8909180395 | |
| Download: ML19325C173 (18) | |
Text
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diA - NINE MILE POINT NUCLEAR STATION - UNIT 2 l i i ( 'l SDtI-ANNilAL RADI0 ACTIVE EFFLUENT . 1 RELEASE REPORT i f.' January through June 1989 . i p: s I
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i P E i o s NIAGARA MOHAWK POWER CORPORATION
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4 , 4, . .e i NINE MILE POINT h'UCLEAR STATION - UNIT ? ! p 4 ,, L SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT j i L January through Juno 1989 : ( L' ! Facilityt Nine Mile Poirt Unit #2 Licenseet Niagara Mohawk Power ! Corporation i i !
- 1. Technical Specification 1.imits:
{
- A) Fission and activation gasest l 1.- The dose rate limit of noble gases from the site to areas at and !
beyond the site boundary shall be less than or equal to 500 i eresi/ year to the whole . body and less than or equal to 3000 mres/ year to the skin. i i
- 2. The air dose from noble gases released in gaseous effluents from ,
the Nine Mile Point 2 Station to areaa at and beyond the site boundary shall be limited during any calendar quarter to less , than or equal to 5 mrad for gamma radiation and less than or equal to 10 airad for beta radiation and, during any calendar- ! year to less than or equal to 10 mrad for gamma radiation and s less than or equal to 20 mrad for beta radiation. l t B&C) Tritium, Iodines and Particulates, half lives > 8 dayst I
- 1. The dose rate limit of Iodine-131 Iodine-133. Tritium and all radionuclides in particulate form with half-lives greater than ;
eight days, reIer. sed gaseous effluents from the site to areas at or beyond the site boundary, shall be less than or equal to 1500 ! mres/ year to any organ, i
- 2. The dose to a member of the public f rom Ior'.ine-131. Iodine-133, l Tritium and all radionuclides An partic' late form with half 1
> 1ives greater te.an 8 days as part of gaseous ef fluents released +
f rce the Nine Mile Point 2 Station to areas at and beyond the , site boundary shall be limited during eny calendar quarter to , g less than or equal to 7.5 mrem to any organ and, during any j 1 relendar year to less than or equal to 15 m em to any organ. ' 1' D) Liquid Effluents i L 1. The concentration of radioactive material released in liquid L effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20. Appendix B, Table , II, Column 2 fer radionuclides other than dissolved or entrained lj noble gases. For dissolved or entrained noble gas, the ! H concentration shall be limited to 2E-04 microcuries/mi total activity.
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V .c l j' 4. .. I ,, , D. Liquid Effluents (Cont'd)-
- 2. The dose or dose commitment to a member of the public from e radioactive materials in liquid effluents relecsed from Nine fK Mile. Point Unit 2 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and'
' during any calendar year to less than or equal to 3 mrem to the whole body and to less than nr equal to 10 mram to any organ.
l-
! 2. Maximum Permissible Concentrations A) .Fissica and activation gases
- j. None specified B&C) Iodines and particulates, half lives E 8 days None specified D) Liquid Effluents:
Nuclide MPC - uC1/mi Strontium-89 3E-6 Strontium-90 3E-7 Cesium-134 9E-6 Cesium-137 2E-5 lodine-131 3E-7 Cobalt-58 9E-5 Cobalt-60 3E-5 Iron-59 SE-5 Zinc-65 IE-4
-Mangnnese-54 1E-4 Chromium-51 2E-3 Zirconium-Niobium-95 6E-5 Molybdenum-99 4E-5 Technetium-99m 3E-3 Barium-140 2E-5 Cerium-141- 9E-5 Tungsten-187 6E-5 Arsenic-76 2E-5 i Iodine-133 1E-6 Hydrogen-3 3E-3 ,
Iron-55 8E-4 ! Manganese-56 IE-4 l Sodium-24 3E-5 Xe-133 2E-4 Xe-135 2E-4 I l l
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- 3. . Average Energy (Fission and ActiUntion gases - Mev)- !
1
' First Quarter * : Ey = 0.00 ; gg ;= 0.00 l Second Quarter's Ey= 0.798 ; Eg = 1.04
- 4. -Measurements'and Approximations of Total Radioactivity Described below are the methods used to measure or approximate the total }
radioactivity and radionuclide composition in effluents. l t A) Fission and Activation Gases: Noble gas effluent activity is a determined by on-line garama . spectroscopic monitoring (intrinsic j ge:sanium crystal) of an isokinetic sample stream.
- B)' . Iodines: lodice effluent- activity is determined by gamma ,
spectroscopic' analysis .(at least weekly) of charcoal cartriages t manually or automatically sampled from an isokinetic sample stream. . C) Particulates: ' Activity released is determined by gamma spectroscopic , analysis; (at' least weekly) of particulate filters manually or : automatically. sampled from an isokinetic sample stream. l D) Tritium: Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken- ; with an air sparging/ water trap apparatus. E) 1.iquid Ef fluents: Isotopic Analysis of a repr2sentative sample of - each batch, j
- F) -Solid Effluents: Isotopic contents of waste shipments are determined ,
by gansna spectroscopy and water content analyses of a representative ! sample of each batch. Scaling factors established from primary , composite sample analyses conducted off-site -are applied, where , appropriate, to find estimated concentration of non-gamma emitters. . For low activity trash shipments, curie content 13 estimated by dose [ rate measurement and application of appropriate scaling factors. i
- 5. Batch Releases The following information relates to batch releases of radioactive 4 materials in liquid and gaseous effluents. -
A) Liquid - $ r 1. Number of batch releases: jijk ,
- 2. Total time period for batch releases: 191 hours _31_ min.
- 3. Maximum time period for a batch release _ _3 hours _ 2fL min. >
- 4. Average time period for a batch release ___3 hours 14._ min. 4
- 5. Minimum time period for a batch release ____3 hours ._l2_ min.
- 6. Average stream flow during period of release of effluent into a flowing stream: Not Applicable l
- 7. Total volume of water used to dilute the liquid effluent during release periods: 1.31E+09 liters ,
- 8. Total volume of water available to dilute '
the liquid effluent during reportir.g period 2d3EtLO liters
- Unit Shutdown - no radiological releases during period.
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4' .. _ ! B) Gaseous (Primary Containment Purge) "c-T 1. Number of batch releases .JL_
- 2. Total time period for batch releases: _60_ hours 4
3.- Maximum time period for a batch release ._12_ hours [
' 4. Average time period for a batch releases _12_ hours
- 5. Minimum time period for a batch release .12_ hours !
- 6. Licornal Releases '
A .' Liquids - April, 13, 1989 between approximately.1100 and 1230 the ' cooling - tor. : overflowen at a rate of approximately 15000.gpm to a drainage ditch. No radioactivity was detected. t B. Gaseous - none i e F t l t I I h t t 1 jeiers , 4
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p g-. . e n r i ..,/ - . , TABLE 1A' i g CEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT , NINE MILE POINT NUCLEAR STATION #2 ' GASEOUS ETFLUENTS-SUMMATION OF ALL RELEASES
' E12VATED AND GROUND LEVEL l January through June 1989 ,
i Isti 2nd EST. TOTAL I!HII OUARTER QUARTER EER0Rd : 1 A. Eission & Activation nasts
~
- 1. Total release C1 0.00E+00 1.38E+01 5.0E+01 !
- 2. Average. release rate g for period pC1/sec 0.00E+00 1.76E+00 *
. 3. Percent of Technical l
. Specification Limit % *
- l B. .losinta
- 1. Total iodine-131,133,135 Ci 0.00E+00 5.78E-04 5.0E+01 -
- 2. Average releese rate t for period pCi/sec 0.00E+00 . 7.35E-05
. 3. Percent rf' Technical i Specificatic.4 Limit % *
- C.- farticulates
- 1. Particulates with half- <
lives > 8 days # Ci 0.00E+00 8.02E-05 5.0E+01 >
- 2. Average release rate
.for period pCi/sec 0.00E400 1.02E-05 '1 Percent of Technical 3.'
Specification Limit 1 * *
- 4. Gross alpha radio-activity C1- 7.74E-05 1.08E-04 5.0E+01 D. Iritium Total release 0.00E+00 2.49E+00 5.0E+01
~
- 1. ci
- 2. Average release rate for period pCi/sec L 00E+00 3.16E-01 '
- 3. Percent of Technical i SpecificaLion Li. nit 1 * *
*See Item E attached.
#1nclude Mo-99 also t Unit Shutdown During 1st Quarter
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TABLE 1A. I I * (Cor.tinued) ' { I
- SEMI-ANNUAL RADI0 ACTIVE EFTLUENT RELEASE REPORT i
NINE MILE POINT NUCLEAR STATION #2 CAFECb3 EFFLUENTS-SUt9tATION CF ALL RE'. EASES
~ ELEVATED AND GROUND LEVEL
. January through June 1989 l 1
1st* 2nd I
< EIT QUARTER DUARIER i I
E. Egicent of Technieml Specification limits Eiss_ ion _and Activation GastEl i 1. Percent of Quarterly 7 Cansna Air Dose Limit % DJ0E+00 B.82E-02 !
- 2. Percent of Quarterly Beta Air Dose Limit 1 Q.JDEf00 1.51E-03 3.. Percent of Annual Gamma .
Air Dose Limit to Date % 0.00E400 4.41E-02
- 4. Percent of Annual Beta 7 Air Dose Limit to Date % 0.00E+00 7.55E-QA
- 5. ._ Percent of Whole Body. ,
Dose Rate Limit % 0.00E+00 3.3BE-03 i
-6 . Percent of Skin Dose Rate Limit % 0.00E+00 6.67E-Oh r Iritium. IodingA._And Particulattsldjji half-lives mrgalgt than 8 daysli
- 1. Percent of Quarterly
. Dose Limit % D_dQEiHQ 3.86E-03 '
- 2. Percent of Annual Dose .
' Limit to Dr,1e 1 0.00E+02 1.J3E-03 ?
Percent of Organ Dose 3. Rate Limit % 0.00E+00 1.56E-04 : e
'* Unit Shutdown During First Quarter
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l fi TABLE IB SEMI-ANNUAL RADI0 ACTIVE EFFLULWT 1.ELEASE REPORT -i NINE MILE POINT NUCLEAR STATION #2 F GASEOUS EFFLUENTS-ELEVATED (STACK) Lt : January through June 1989 t CONTINUOUS MODE BATCH MODE i Nue11 des Released Unit la.t Ouarter 2nd Ouarter lat Ouarter* 2nd_QuatLcI I Fission cames 3 1. Argon-41 C1 ** 9.71E-01 0.00E+00 ** ! Krypton-85m Ci ** ** 0.00E+00 ** Krypton-87 Ci ** 2.33E-0? 0.00E+00 ** Krypton-88 Ci ** 1.31E+00 0.00E&D0 ** i Xenon-133 Ci ** ** 0.00E+00 ** i
> Xecon-135 Ci ** ** 0.00E+00 ** ,
' Xenon-135m Ci ** 5.60E-01 0. 40 ** ,
Xenon-137 Ci ** 5.65E+00 0.00E+00 ** Xenon-138 01 ** 4.02E+00 0.00E+00 1.05E+00 l
- 2. Indines Iodine-131 Ci ** 4.17E-05 0.00E+00 ** +
Iodine-133 Ci ** 5.36E-04 0,00E+00 ** Iodine-135 Ci ** ** 0.00E+00 ** l
- 3. Ent1Laulate.a Strontium-89 Ci #** 4.99E-5 0.00E+00 **
Strontium-90 Ci #** ** 0.00E+00 ** Strontium-91 Ci ** ** 0.00E+00 ** Cesium-134 Ci ** ** 0.00E+00 ** ! Cesium-137 Ci ** ** 0.09E+00 ** Cobalt-60 Ci ** 9.40E-07 0.00E+00 ** Cobalt-58 Ci ** ** 0.00E+00 ** Manganese-54 Ci ** 6.80E-07 0.00E+00 ** Barium-Lanthanum-140 Ci ** ** 0.00E+00 ** Antimony-125 Ci ** ** 0.00E+00 ** Niobium-95 Ci ** ** 0.00E+00 ** i Cerium-141 Ci ** ** 0.00E+90 ** Cerium-144 Ci ** ** 0.00E+00 ** -' Iron-59 Ci ** ** 0.00.5500 ** i Ci ** ** 0.00h+00 ** Cesium-136 1 Chromium-51 Ci ** 1.78E-05 0.00E+00 **
** 1.52E-06 0.00E+00 **
Zinc-65 Ci i Iron-55 Ci f** ** 0.00E+00 ** l
** 2.85E-06 0.00E+00 ** j Molybdenum-99 01
- 4. Tritium Ci ** 9.08E-01 0.00E+00 8.58E-01
- There were no batch releases during the first quarter.
** Less than sensitivity of 1.00E-04 poi /mi for noble gases 1.00E-12 pCi/ml I f or iodines,1.00E-11 p i/n.1 for particulates and 1.00E-06 pCi/ml for 1 tritium as applicable in Technical Specifications.
# None of these nuclides were released during the fourth quatter of 1988 from the stack. .. j I
-7 - - - - - -
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@!I-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT' NiNE MILE POINT NUCLEAR STATION #2-CASEOUS EFFLUENTS-COMBINED GROUND LEVEL-ELEVATED (REACTOR BUILDING VENT)
January through June 1989 CONTINUOUS MODE BATCH MCDE Nuclides Released I!Dit lat Ouarter 2nd Ouarter 1st Ouarter* 2ni_ Quarter *
'1.- Fiesion Casta' Argon-41 Ci ** ** 0.00E+00 0.00E+00 Krypton-85 Ci ** ** 0.00E+00 0.00E+00 Krypton-85m Ci ** ** 0.00E+00 0.00E+00 Krypton-87 Ci ** ** 0.00E+00 0.00E+00 i: Krypton-88 C1 ** '** 0.03E+00 0.00E+00 Xenon-133 Ci ** ** 0.00E+00 0.00E+00 Xenon-135 Ci ** ** 0.00E+00 0.00E+00 Xenon-135m Ci ** ** 0.00E+00 0.00E+00 Xenon-137 Ci ** ** 0.00E+00 0.00E+00 Xenon-138 Ci ** ** 0.00E+00 0.00E+00
- 2. Indines Iodine-131 Ci ** ** 0,00E+00 0.00E+00 Iodine-133 Ci ** ** 0.00E+09 0.0]E+00 Iodine-135 Ci ** ** 0.00E+00 0.00E+00
- 3. EArticulgtgA Strontium-89 Ci #** ** 0.00E+00 0.00E+00 Strontium-90 Ci #** ** 0.00E+00 0.00E+00 Cesium-?34 Ci ** ** 0.00E+00 0.00E+00 Cesium-137 Ci ** ** 0.00E+00 0.00E+00 Cobalt-60 Ci ** ** 0.00E+00 0.00E+00 Cobalt-58 Ci ** ** 0.00E+00 0.00E+00 Manganese-54 Ci ** ** 0.00E+00 0.00E+00 Barium-14nthanum-140 01 ** ** 0.00E+00 0.00E+00 Antimcny-125 C1 ** ** 0.00E+00 0.00E+00 Niobium-95 Ci d* ** 0.00E+00 0.00E+00 Cerium-141 Ci ** ** 0.00E+00 0.00E+00 Cerium-144 C1 ** ** 0.00E+00 0.00E+00 Iron-59 Ci ** ** 0.00E+00 0.00E+00 Cesium-136 Ci ** ** 0.00E+00 0.00E+00 Chromium-51 Ci ** 6.51E-06 0.00E+00 0.00E+00 Zine-65 Ci ** ** 0.00E+00 0.00E+00 Iron-55 Ci #** ** 0.00E+00 0.00E+00 Molybdenum-99 Ci ** ** 0.00E+00 0.00E+00
- 4. Irltium Ci ** 7.21E-01 0.00E+00 0.00E+00
- There were no batch releases f rom this release point.
** Less than the sensitivity of 1.00E-04 pC1/mi for noble gases 1.00E-li pCi/mi for iodines, 1.00E-11 pCi/ml for particulates and 1.00E-06 pCi/mi for tritium as applicable in Technical Specifications.
# None of these nuclides were released from the vent during the fourth quarter i
of 1988. . ., ,,,
-8 -
- - _= - . - .- - - -.- .
[ _ [
N , , a et . L e .'- M ;, .., TABLE 2A ] i SEMI-ANNUAL RADICACTIVE EFFLUENT RELEASE REPORT l i NINE MILE POINT NUCLEAR STATION #2 d E LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l January through June 1989 ; let 2nd Est. Total l l! nit Ouarter hsrter Error. 1.
- 4. f11Ajon and activation products 1.. Total release (not ;
including tritium, ! gases, alpha) Ci 2.07E-02 3.17E-03 5.00E+1 !
- 2. Average diluted con-centr.stion during reporting period pC1/a1 1.39E-09 2.21E-10 ;
- 3. Percent of applicable ;
limit % 2.56E-03 4.55E-04 i
~
B. Iritium
- 1. . Total release ci 6.54E-01 8.58E-01 5.0CF+1- l
- 2. Average diluted con- !
centration ~during reporting period pCi/ml 4.38E-08 5.98E-08 ,
- 3. Percent.of applicable i limit % 1.46E-03 1.99E-03 ,
t C. Digagliggi and entrained naggs :
- 1. Total release Ci 0.00E+00* 3.185-04 5.00E+1 l
- 2. Average-diluted con- !
centration during reporting period pCi/ml 0.00E+00 2.22E-11
- 3. Percent of applicable limit ~ % 0.00E+00 1.11E-05 D. Ernss alpha radigactivity
- 1. Total release Ci ** ** - - ---
E. Volumes
- 1. Prior to dilution lit 2 rs 2.58E+06 2.81E+06 5.00E+1
- 2. Volume of dilution ,
water used during release period liters 6.39E+08 6.700 08 5.00E+1
- 3. Volume of dilution vater used during reporting period liters 1.49E+10 1.43E+10 5.00E+1 ,
- Unit Shutdown - none detected. ,
** <1.00E-07 pCi/ml sensitivity for gross alpha radioacENifyl.
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2 . 4 4 7ABLE 2A (Continued) l SD4I-ANNUAL kADI0 ACTIVE EFFLUENT RELEASE REPOR1' NINE MILE POINT NUCLEAR STATION #2 i LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES January through June 1989 o ist t..d linit Dumi tet. Duarter F. Percent of Technical Soetification Llmlth -
- 1. Percent of Quarterly Whole Body Dore Limit 1 3.91E-01 6.34E-02
- 2. Percent of Quarterly Organ Dose' Limit (Liver) % 2.63E-01 4.21E-02
- 3. Percent of Annual Whole Body Dose Limit to Date % 1.96E-01 2.28E-01
- 4. Percent of Annual Organ Dose Limit te Date (Liver) 1 1.31E 1.52E-01
- 5. Per:ent of 10CFP20 Concentration Limit 1 4.02E-03 2.45E 6.- Percent of Dissolved or Entrained Noble Gas Limit % 0.00E+00 1.11E-05 1
I l 1 1 I
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j e , .,>' r' l c- j. , TABLE 2B j i
.i/ : RADIDACTJVE EFFLUENT RELEASE SD!I-ANNUAL REPORT ~ j)
NINE MILE POINT NUCLEAR' STATION #2 j 1 ,
-LIQUID EFFLUENTS RELEASED ;
' January through June 1989 -
,. CONTINUOUS MODE BATCH MCDE -{
~"
Lhil 1st Ouarter 2nd Ouarter 1 ' ist ouarter 2nd Ouarter ! Nuclides Released j Strontium-89 Ci * * *
- St.rontium-90' Ci '* *' * *: 1
- Cesium-134~ Ci * * * * ;
Cesium-137 '. ** * * * *
,, C1
. Iodine-131 Ci * *
- Cobalt- 58 : Ci *
- 2.19E-03 7.99E-05 :
e - Cobalt-60 'Ci *
- 6.92E-03 8.57E-04 5 Iron-59 Ci * * * *-
Zinc-65 CI *
- 6.62E-03 1.09E-03 .
Unganes2-54 Ci *
- 4.96E 4.93E-04' l l
Chromiuw51, Ci * *
- 6.52E ,
' Zirconium-Nicbium-5 Ci * * * *
-' Molybdenum-99 01 * * *
- Technetium-99m. Ci. * * *
- Barium-lanthanum-140Ci * * *
- h Cerium-141 Ci * * *
- j Hydrogen-3' Ci *
- 6.54E-01 8.58E-01 Sodium-24' Ci * * *
- 1ron Ci * * *
- Manganese-56 Ci * * * * ,
1,1ckel-65 Ci * * *
- l Arsenic Ci * * *
- Iodine-133 Ci * * * * !
i' Tungsten-187. Ci * * * * -[ Xenon-133 Ci * *
- 2.79E-04 Xenon-135 Ci * *
- 3.94E-05 ;
- Less than sensitivity of 5.00E-07 pCi/r,1 for ga - emitting nuclides, l .00E-05 pCi/mi for dicsolved and entrained noble gases and tritium, 5.00E-08 pCi/mi for Sr89 and Sr90 and 1.00E-06 pCi/mi for Fe55 as applicable in Technical Specifications.
t:
- . . . . . . - . nn.
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SEMI-ANNUAL RADI0 ACTIVE EFFLUENT REI, EASE REPORT -
~ NINE MILE POINT NUCLEAR STATION #2 j SOLID WASTE AND IRRADIATED FUEL 5HIPMENTS January through Jeae 1989 l A. .Eolid Waste Shioned Off-Eite for Burini or Dianomal (Not irradiated fuel).
i EST. TOTAL ,.
- 1. Troe of Wate UNIT k J0FTl! PE%10D F_RROR.J l t
a.* Spent resins, filter sludge bottoms, etc. me 1.20E+02 5.00E+01 Ci S JwGi 5.00E+01 !
- b. : Dry compressible .
3 waste, contaminated
- equip., ett. as done Ci None - - - -
- c. Irradiated components, control rods, etc. 2 8 None - --
l r Ci None -
-d. 0ther ** m8 - 1.45E+02 5.00E401 Ci 1.13E+01 5.00E+01
*All were solidified in cement' as -Class A weste in strong, tirbt containers. All was shipped as radioactive LSA.
**Noncompacted commingled trash shipped to Oakridge, TN for processing before burial, i
1:
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d 7 .e' TABLE 3A I j
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(Continued) ..N SEMI-ANNUAL.RADIDACTIC*dEFFLUENT RE1. EASE REPORT j g. NINE MILE POINT NUCLEAR SIATION #2 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS f 1
- 2. Iglimate.pf Maior Nuclide Cannoaltion (by Tyne of Waate) i
- a. Spent Resins,' filter sludges,: evaporator bottoms, etc. !
Est. Total Percent Error. 1 c Zine-65 3.18E+01 5.00E+01 - A Iron-55 2.77E+01 5.00E+01 !
. Cobalt-60 1.66E+01 5.00E+01 Mangantse-54 1.12E+01 5.00E+01 Cobal t.-58 6.50E+00 5.00E+01 Chromium-51 3.40E+00- 5.00E+01 Others 2.80E+00 5.00E+01 3
- b. Dry Compressible Waste, Contmainated Equips, Etc. 5
?
NONE
- c. Irradiated components, control rods, etc.
NONE
- d. Other (Noncompacted Est. Total commingled trach shipped to Percent Error. % -
Oakridge. TN for procecsing prior'to burial) f Cobalt-60 3.08E+01 5.00E+01 ! Manganese-54 2.91E+01 5.00E+01 ; Zine-65 2.37E+01 5.00E+01 i 4 Cobalt-58 1.33E+01 5.00E+01
- Iron-55 2.42E+00 5.00E+01 Others <1.00E+00 5.00E+01 i
- 3. Solid Waste Disposition Number of Shipmenta tiode of Transportation Destination 15 Truck Burial in 1 Barnwell SC 2 Truck Processing in Oakridge, TN B. IRRADIATED FUEL SHIPMENIS (DISPOSITION) -
Number of Shin.nent Mnde of.Trananortation Destination None - - i v m.
.am.
-13 --
_ . . _ _ __- _ _ - .. _ ._. ~ . . . , - N-- 6 % . - d4M W-4 W.* 4.*6 'a# - _ W. N-
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9
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TABLE 4 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT-y1 , NINE MILE POINT NUCLEAR STATION # 2 . [ RECF.NT CHANGES TO THE OFFSITE DOSE CALCUIATION MANUAL ' } Channe Reason . There have been no changes to the Offsite Dose Calculation , Manual during this, reporting period. -i i t.
.t 4%'
?
f n 6 5
?
9 h i 1 l l: l-lc l a taan. . . T WM
- _$p ..
. . _ _ _ _ _ _ . . ._ .. ~.- .. _ ._
- NW%fMONIN ' M N .
_- - - - - , , , - ., .vy* -v.e ew e r ,, w~. ,~a_ t - w
y '.
.,He 1.: l .
TABLE 5 1 ..- 4 3. t SEMI-Ah?!UAL RADIOACTIVE EFFLUENT RELEASE REPORT
' NINE MILE POINT NUCLEAR STATION #2 l - - RECENT CHANGES TO PROCESS CONTROL PROGRAM !
a ;
+
Change Raason ! To reflect other changes being made. Table of Contents [ Page 1 The Tech Spec section was broken down from 3/4-11.3 to sub-sections which were applicable. ; Page 10 ' bection 8.4 Reference to 10CFR50.59 was deleted as it t.as no longer needed af ter Start-up. ! Page 11 1 Naction 10 the words "The' Supervisor of Radwaste f Operations" were - added to provide a - contact to y ensure requirements are satisfied. . Page 12 In Section 11.1 the sub-section deahng with QA $ verifying each batch sample was deleted so as to ! conform with QA review of their program. Page 14 Section 11.2.2. This section was changed to - reflect the latest training schedule and to provide flexibility for future schedules to meet
- training needs. .
t Pages-70 and 21 This was changed to reflect the latest i Radioactive Chipping . Manifest revisions from Chem-Nuclear and U.S. Ecology. ;
]
?
9 h F
't s
by -Ww E.4W%+%W_ t : l -13 ~. _ . _ _ . . _ L
.e . . m ma. og. ww. ee. .en- sw..,w .ce
= wv +
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'.V P TABLE 6.
s SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (1989) NINE MILE POINT NUCLEAR STATION #2 ' EXPLANATION OF INSTRUMENTATION INOPERABILITY L ! k . DATE OUT DATE RET"RNED INSTR 11 MENT OF SERVICE TOSDitE ]QQ MNATION l g .0ffgas Noble Gas October 1988 April 1 W9 Offgas system was not in ~{ H, , ;. Ar.' d.vity service due to Plant '; i Outage. t r i j 9.. !- Offges Systew 710w August 1987 April-1989 Design Problems i resolved. . ; p ; i Offgas Sampler Flow- October 1988 ' April 1989 Ofigas system was not in. !
- service due to Plant' Outage Ofigas H 2-Train August 1987 -- Design Prob 1mes. .
A (Returned to service i 8/23/89.) ; Offgas H2 -Train August 1987 -- Design Problems 3 B (Returned to service : 8/23/89.) l 0figas h -Conuron 2 August 1987 -- - Desigu Problems. : Train (Returned to service-8/23/89.)
. i
. Reactor /Radweste -January 10 Not Returned Difficulty in j Vent Noble Gas. 19651 to Service trouble-shooting and >
obtaining parts. Reactor /Radwaste .Tanuary 10 Not Returned . Difficulty in i Vent System Flow 1989 to Service trouble-shooting and ; obtaining parts. 7 Reactor /Radwaste January 10, Not Returned Difficulty in Vent Effluent Flow 1989 to Service trouble-shooting and obtaining parts. Liquid Radwaste November 1987 Not Returned High background in Effluent Radiation to Service monitor. Modification is underway. Estimated completion October 1989. Tank Level Indicating - - None on site Devices
-16
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r^ ba alut. ptJ.t apDNS y h.N6 6hMNi*$$-p-A K6gige2$a " gy dp a
r ;p ll -
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4 ,
.s ,
gg TABLE 6 (Cont'd) SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (1980) l NINE MILE POINT NUCLEAR STATION #2 ) [ EXPLANATION OF INSTRUMENTATION INOPERABILITY p DATE OUT. DATE RETURNED INSTRUjLII 0F SERVICE TO SERVICE EXPIANATION a Cooling Tower October 1988 February 1989 Cooling Tower Blowdown Elowdown Radiatice secured. Returned to Service Febre.ary 1989. ; Cooling Tower Or.tober 1988 February 1989 Cooling Tower Blowdown Blowdown Flow i secured and monitor was ; inoperable. Service Watrr A e ' June 1988 Not Returned to Replacement part is not-Fadiation Service available. Expected repair is January 1990. Liquid Radwaste January 9, Februar3 16, Annunciator problems Effluent Flow 1989 1989 in the radwa:lte control room. t 4 (
)
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