ML17037C269
| ML17037C269 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/02/1976 |
| From: | Schneider R Niagara Mohawk Power Corp |
| To: | O'Reilly J NRC Region 1 |
| References | |
| Download: ML17037C269 (14) | |
Text
U.S. NUCLEAR REGULATORY COMM <SION NRC roRM 195 NRC DISTRIBUTION FoB PART OO DOCI(ET MATERIA(
DOCKET NUMBER 50-220 FILE NUMBER
~yrrCe TO:
Mr. James P. O'Reilly FROM:
Niagara Mohawk Power Corporation
- Syracuse, New York R. R. Schneider DATE OF DOCUMENT 12/2/76 DATE RECEIVED 12/10/76
+(LETTER GOB IGINAL 3fcopv DESCRIPTION ONOTORIZEO gUNC LASS IF I E D PROP INPUT FORM ENCLOSURE NUI4 GER OF COPIES RECEIVED One signed copy Ltr. w/attached....re their 2/25/75 ltr.
...furnishing corrections to previously submitted Semi-Annual Effluent and Ilaste Disposal Report for the second half of 1975.
(6-P)
PLANT NAME:
Nine Mile Point Unit 81 gGE~0 050T REMOVE SAFETY ASSXGNED AD:
MILNE %,L~E:..
RO~C'~@N I'LFFP; LIC ASST
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Lear "
Parrish FOR ACTION/INFORMATION
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BANC PROJECT MANAGER LXC ASST 12 10 76 Re Duncan RJL PJ7 NRC PDR I & E OELD GOSSXCK & STAFF IiXPC CASE IIARLESS PROJECT IIANAGEMENT BOYD PE COLLINS HOUSTON PETERSON IKLTZ IIELTEIIES 8KOVHOLT TXC:
INTERNALD SYSTEMS SAFETY HEXNEIIAN SCHROEDER ENGINEERING KNIGHT SIHMEIL PAUL CK REACTOR SAFE ROSS NOVAK ROSZTOCZY
'CHECK AT&X SALTZMPiN RUTBERG EXTERNAL DISTRIBUTION NAT LAB ~
REG V IE ISTRI BUTION PLANT SYSTEMS TEDESCO
~M XPPOLITO OPERATING %ACTORS STELLO OPERATXNG TECH EXSENIIUT BIIMK1MVjiK3 ULRIKS~ON ORNIQ S TE SAFE Elf'RNST BALLARD SPANGLER SITE TECH GAMMXLL STEPP IIULIIAN SXTE ANALYSIS VOLLMER BUNCH J ~ COLLINS KREGER CONTROL NUMBER NSXC:
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. ix EI'I'LUI!N'I'NDI>'ASTE DISI'OSAI, SEhil-ANNUAI, RI!I'Olk'I'{IJ75)
Su i lemcntal Information FACILITY:
Nine hiile Point Unit il 1 LICI:NSI!E:
DPR-63 1.
Regulatory Limits a.
Fission and activation gases:
Q
=
O.S7/E Ci/scc b.
Iodincs:
c.
Particulates, half-li.vcs 8 days:
=
1.5 I:+0 I v hiPC;
(.i/sec
- d. 'iquid effluents:
Gross Beta Activity
=
IE - 07 u(:i/mi or controlled in accordance with Appendix II, Table ll, Column ?, nf IO CFR 20 and Note 1 thereto.
2.
hiaximum Permissible Concentrations Iodines:
Particulates, half-lives 8 da> s:
1.S Liquid Efflucnts.:
Ave MPC.(July-Sept)
Avc hiPC (Oct-Dcc) uCi/scc 6.3 Ii-06 uCi/ml 8.1 Ii-06 uCi/mi Provide the MPC's used in determining allowable release rates or concentration.
a.
Fission and activation gases:
Q(Juiy-Sept)
=
0.7l Ci/scc Q(Oct-Dcc)
=
0.56 Ci/scc b.
c
~
d.
3.
Average Energy (July-Sept: )
=
0.80 hiev E (Oct-Dcc)
=
I.OI Mev
=7 is the average energy of the radionuclidc mixture in releases oi
. iission and activation gases.
4.
hieasuremcnts and A ) roximations of Total Radi oactivitv Provide the methods used to measure or approximate t.hc tot.ai rad~oictivity in effluents and the, methods used to determine radionuclide co-.positton.
a
~
C.
Fission and activation gases:
Stack monitor calibrated to isotopic analysis (NaI) of Off Gas samples at SJAI Io4nes:
4'cekly analysis (NaI) of: stack s;i:aiilcr charcoal cartrid):c Particulates:
Isotopic anal> sis (Gci.i, by contractor) of standi sa;.pier filters Liquid cfflucnts:
Isotopic analysis (Nal or Gel.i) ot reprc'irntativc batches
0 I'
0 EPFLUl'.NT AND NAS'1'E DISPOSAL SEMI-ANNLJAL Ri!PORT (19",53 Cont'de 5,
Batch Rcloases Provide thc following information relating to batch releases of radio-active materials in liquid and gaseous efflucnts.
a y Liquid
- 1. 'umber of batch releases:
381 2.
'1'otal time period for batch relcas<<s:
111 l)o))rs 30 ai:).
3.
Maximum time period for a batch rcle;)sc:
15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 11 ain.
Average time perio<l for batch release:
1 ho>>r 10 n)n.
5.
Minimum time period for a batch relc;)s<<:
0 ln)))rs.'5 r:)n.
6.
Average stream flov, during pcllod 01 release of effluent into a fle)i'ing str<<;)m:
Not Al)1)lie:)l)le b.
Gaseous Not applicable A&k
~I
'6.
Abnormal Releases a
b.
Liquid None Gaseous None
~
~
EFI'I.VENT AND li'AS'I'E DISI'OSAL SEMIAK'NUAL Rl:I'ORT(1975)
GASEOUS EI:I'LUENTS-SUM~IATION OF ALL RELLASLS Unit Quarter Quarter 3
75 75 Est. Total
- Error, A.
Fission f~ activation gases 1.
Total release Ci 6.01 E+05 3.63 E+04 2.
Average release rate for period
)>Ci/sec 7.50 E+04 4.50 E+03 3.
Percent of Technical Specification Limit
'-o 1.05 E+01 8.03 E-01 2.0 E+01
- 8. 'odines "4
W M
~
~
~
I 1.
Total iodine-131
- Ci 1.45 E+00 5.15 E-01'.
Average release rate for per'od pCi/sec 1.82 E-01 6.48 E-02 3.
Percent of technical specification
~o 1.22 E+01 4.33 E+00
- 1. 4 F+0]
C.
Particulates 1.
Particulates with half-lives 5 8 days Ci 2.91 E-Ol 1.21 E-01 2.
Average release rate for period pCi/sec 3.66 E-02 1.52 E-02 3.
Percent of technical specification limit
'-o 2.44 E+00 9.40 E-01 4.
Gross alpha radioactivity Ci 3.72 E-05 8.98 E-05 1.5 E+01 DE Tritium 1.
Total release Ci 8.02 E+00 1.54 E+00 1.6 E+01 2.
Average release rate for period 'Ci/sec 1.01 E+00 1.93 E-01 3.
Percent of technical specification limit E
- None specified
r C'
~ ~
TABLI.'
I]
rrrLUENT AND NASTr) DISI'OSAL SEMIANNUAL REPORT(1975)
GASEOUS EFFLUENTS-L'LEVATFD RELEASE CONTINUOUS DIODE IIATCII hfODE Nuclides Released Unit Quarter 3
75 Quarter Quarter Quarter 4
75 1
~
Fission gases krypton-85m krypton-87 krypton-88 xenon-133 xenon-]35 xenon-138 Others(specifiy) unidentified Total for period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3;41
- 7. 84 1.15 5.88
....l.. 79
- --8 05 5.53 6.01 E+04 r:+04 E+05 E+04
.E+05 r:+04 E
E r:
E+04 E+05 1.20 4.54 5.01 8.35 5.70 1
~ 57 3.30 3.66 E+03 E+03 E+03 E+02 E+03 E+04 E
E E
E+03 6+04 r:
E r:
E E
E r;
E E
E E
E E
E E
E E
E E
E E
E 2.
Lodines iodine-151 iodine-133 iodine-135 Total for period Ci Ci Ci Ci 1.45 2.18 3.96 4.03 E+00
- 5. ]5 E+00 2.36 E-01 4.28 E+00 7.94 E-01 E-01 E-02 E-01 E
r:
E L'
E E
E 3.
Particulates strontium-89 strontium-90 cesium-]34 cesium-137 barium-lanthanum-Others (speci f) )
manganese-54 cobalt-60 cobalt-SS zirconium-Niobium iodine-131 ruthe>>]urn-]03 ruthenium-106 cerium-l l4 cerium-]41 iron-59 zinc-65 Ci Ci Ci Ci 140Ci Ci Ci Ci Ci Ci 95Ci Ci Ci Ci Ci Ci Ci Ci
- 3. 64 2.03 8.46 4.37 7 ~ 24 1.il3 3.99 2.20 2.S3 2.66
].3'I 4,45 2,54 1,50 2]
4,67 E-0'2 E-Oi r;-Oi E-03 E-03 r:'
E-03 I'.-03 E-0 I E-0 I E-03 E-03 E-0 I E-0 I I'.-03 E-0 I E-05 5.3
<1.3 9.92 I ~ /3
].i}2 3..) 1 1.23 6.76
].2]
68
~I3 E-0 I E-0 'I L-01 I)-'03)
E-03 E
E E-03 I:.-02 I:.-0 I E-03 (1.)
I -03 98 I',-0 I 25 E-03
~I3 I)-03)
E E
E E
Ii E
Ii r:
li E
E r:
E E
E E
E E
E E
E li Ii I
I I;
9
~1 g
L
( ~
~
~r
l!I:FI,UI!N'I' ND lVAS'I'E DISPOSAI. Slihll-ANNUAI. Rl:
'OR'I'OLID IVAS'I'1: AND'IRiVDIA'I'EDFui:.I. Siilphli:.NIS A.
Solid lVaste Sill) ed Off site for Burial or Di.s)osal (Not Irradiated I)ucI) l.
TYPE OF IVASTE UNI'I'IST.TOTAL EIU<OR,
'-o a.
Spent Resin Evaporator Bottoms 3
m Ci 111 3 Ci 1.39 E+01 2.35 E<02 1.40 E+02 3.44 L+02 1.5 E+01 1.8 E+01 Resin or Filter Sludgcs m3 Ci 1.23 E+01 8.43 E+02 2.1 E+Ol Liquid IVaste 3
m Ci NOXF b.
Dry Compressible IVastc
..m3 or. Contaminated L'quip.
Ci-.
c.
Irradiated Components m3 Ci 9.59 E+01 3.48 E+00 2.7 E+Ol NONE 2.
ESTlhiATE OF hfAJOR NUCLIDE COhIPOSITION (BY TYPE OF IVASTE) a.
Evaporator Bottoms Cobalt-60 Cesium-137 hlangancse-54 Cesium-134 Iodine-131 Cobalt-58 l,anthanum-140 Strontium-S9 Stro>>tium-90 Iron-59 Sodium-24 Tungsten-1S7 Cerium-Iill Gillom1um-5 1 Zirco>>gaum-95 Niobium-95 Antilllony-1 24 Filter Sludge not determined 4.90'o 47.70~o
- 1. 57~o 40:20~o
- 1. 50io 0.41 o
- 0. 24~o
- 0. 37."o
- 0. OS~o
- 0. 25'o
- 1. 90'-o 0.22o
- 0. 05'-o
- 0. 29'o
- 0. 16 "o
- 0. 20'-o 0.11 o
Dry Gomprcssibl c'Vastc Vill.lCS C.
Irrad 1 '1 tcd Colllponcnts none 9-7
4
\\, r~, ~
o