ML17037C269

Letter Enclosing a Corrected Semi-Annual Effluent and Waste Disposal Report for the Second Half of 1975

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 DOCKET NUMBER NRC roRM 195 50-220 FILE NUMBER NRC DISTRIBUTION FoB PART OO DOCI(ET MATERIA( ~yrrCe .

TO: FROM: DATE OF DOCUMENT Niagara Mohawk Power Corporation 12/2/76 Mr. James P. O'Reilly Syracuse, New York DATE RECEIVED R. R. Schneider 12/10/76

+(LETTER ONOTORIZEO PROP INPUT FORM NUI4 GER OF COPIES RECEIVED GOB IGINAL gUNC LASS IF I E D One signed copy 3fcopv DESCRIPTION ENCLOSURE 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.

gGE~0 (6-P) REMOVE 050T PLANT NAME:

Nine Mile Point Unit 81 SAFETY FOR ACTION/INFORMATION 12 10 76 RJL ASSXGNED AD: 'L'IXQHED ~

MILNE %,L~E:.. Lear " BANC Re RO~C'~@N I'LFFP; PROJECT MANAGER LIC ASST ~ Parrish LXC ASST Duncan INTERNAL D IST RI BUTION PJ7 SYSTEMS SAFETY PLANT SYSTEMS S TE SAFE NRC PDR HE XNEIIAN TEDESCO I

OELD

& E SCHROEDER ~M GOSSXCK & STAFF ENGINEERING XPPOLITO Elf'RNST IiXPC CASE KNIGHT BALLARD SIHMEIL OPERATING %ACTORS SPANGLER IIARLESS PAUL CK STELLO SITE TECH PROJECT IIANAGEMENT REACTOR SAFE OPERATXNG TECH GAMMXLL BOYD ROSS EXSENIIUT STEPP PE COLLINS NOVAK IIULIIAN HOUSTON ROSZTOCZY PETERSON 'CHECK SXTE ANALYSIS IKLTZ VOLLMER I IELTEIIES AT&X BUNCH 8KOVHOLT SALTZMPiN J ~ COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER NAT LAB ~ BIIMK1MVjiK3 TXC: REG V IE ULRIKS~ON ORNIQ NSXC: '~%~7/ gy-200 ASI.B:

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. ix EI'I'LUI!N'I'ND I>'ASTE DISI'OSAI, SEhil-ANNUAI, RI!I'Olk'I'{IJ75)

Su i lemcntal Information FACILITY: Nine hii le Point Uni t 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 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. Iodines:

c ~ Particulates, half-lives 8 da> s: 1.S uCi/scc

d. Liquid Efflucnts.: Ave MPC.(July-Sept) 6.3 Ii-06 uCi/ml Avc hiPC (Oct-Dcc) 8.1 Ii-06 uCi/mi

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 ~ 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 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

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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 A&k Not applicable

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'6. Abnormal Releases a Liquid ~ ~

None

b. 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 Est. Total 3 Error, 75 75 A. Fission f~ activation gases

1. Total release Ci 6.01 E+05 3.63 E+04 2.0 E+01

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

8. 'odines "4 W M ~ ~ ~ I

1. Total iodine-131 - Ci 1.45 E+00 5.15 E-01'. 1. 4 F+0]

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 C. Particulates

1. Particulates with half-lives 5 8 days Ci 2.91 E-Ol 1.21 E-01 1.5 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 DE Tritium 1.

2.

3.

Total release Average release rate Percent for period 'Ci/sec of technical specification limit Ci 8.02 E+00 1.54 E+00 1.01 E+00 1.93 E-01

• E 1.6 E+01

• None specified

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TABLI.' I]

rrrLUENT AND NASTr) DISI'OSAL SEMIANNUAL REPORT(1975)

GASEOUS EFFLUENTS-L'LEVATFD RELEASE CONTINUOUS DIODE IIATCII hfODE Nuclides Released Unit Quarter Quarter Quarter Quarter 3 4 75 75 1 ~ Fission gases krypton-85m Ci 3;41 E+04 1.20 E+03 r: E krypton-87 Ci 7. 84 r:+04 4.54 E+03 E E krypton-88 Ci 1.15 E+05 5.01 E+03 r: E xenon-133 Ci 5.88 E+04 8.35 E+02 E E xenon-]35 Ci ....l.. 79 .E+05 5.70 E+03 E E xenon-138 Ci - --8 05 r:+04 1 ~ 57 E+04 E E Others(specifiy) Ci E E r; E Ci E E E E Ci r: E E E unidentified Ci 5.53 E+04 3.30 E+03 E E Total for period Ci 6.01 E+05 3.66 6+04 E E

2. Lodines iodine-151 Ci 1.45 E+00 5. ]5 E-01 E iodine-133 Ci 2.18 E+00 2.36 E-01 r: E iodine-135 Ci 3.96 E-01 4.28 E-02 E E Total for period Ci 4.03 E+00 7.94 E-01 L' E

3. Particulates strontium-89 Ci 3. 64 E-0'2 5.3 E-0 I E r:

strontium-90 Ci 2.03 E-Oi <1.3 E-0 'I E E cesium-]34 Ci 8.46 r;-Oi 9.92 L-01 E cesium-137 Ci 4.37 E-03 I~ /3 I)-'03) E E barium-lanthanum- 140Ci 7 ~ 24 E-03 ].i}2 E-03 E E Others (speci f) ) Ci r:' E Ii E Ci E E E manganese-54 Ci 1 .il3 E-03 3..) 1 E-03 Ii E cobalt-60 Ci 3.99 I'.-03 1.23 I:.-02 r: E cobalt-SS Ci 2.20 E-0 I 6.76 I:.-0 I li E zirconium-Niobium 95Ci 2.S3 E-0 I ].2] E-03 E li iodine-131 Ci 2.66 E-03 E Ii ruthe>>]urn-]03 Ci ] .3'I E-03 68 (1.)

ruthenium-106 Ci 4,45 E-0 I ~ I3 I -03 cerium- l l4 Ci 2,54 E-0 I 25 E-03 cerium-]41 Ci 1,50 I'.-03 ~ I3 I)-03) I iron-59 2] E-0 I I Ci zinc-65 Ci 4,67 E-05 98 I',-0 I I; 9

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l!I:FI,UI!N'I' ND lVAS'I'E DISPOSAI. Slihll-ANNUAI. Rl:

'OR'I'OLID IVAS'I'1: AND'IRiVDIA'I'ED Fui:.I. Siilphli:.NIS A.

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Solid lVaste Sill)

TYPE OF IVASTE ed UN 3

I'I'IST.

Off site for Burial or Di.s)osal (Not Irradiated I)ucI)

TOTAL EIU<OR, '-o

a. Spent Resin m 1.39 E+01 Ci 2.35 E<02 1.5 E+01 Evaporator Bottoms 111 3 1.40 E+02 Ci 3.44 L+02 1.8 E+01 3

Resin or Filter Sludgcs m 1.23 E+01 Ci 8.43 E+02 2.1 E+Ol 3

Liquid IVaste m NOXF Ci

b. Dry Compressible IVastc ..m3 9.59 E+01 or. Contaminated L'quip. Ci- . 3.48 E+00 2.7 E+Ol

c. Irradiated Components m3 Ci NONE

2. ESTlhiATE OF hfAJOR NUCLIDE COhIPOSITION (BY TYPE OF IVASTE)

a. Evaporator Bottoms Cobalt-60 4.90'o Cesium-137 47.70~o hlangancse-54 1. 57~o Cesium-134 40:20~o Iodine-131 1. 50io Cobalt-58 0.41 o l,anthanum-140 0. 24~o Strontium-S9 0. 37."o Stro>>tium-90 0. OS~o Iron-59 0. 25'o Sodium-24 1. 90'-o Tungsten-1S7 0.22o Cerium-Iill 0. 05'-o Gill om1um-5 1 0. 29'o Zirco>>gaum-95 0. 16 "o Niobium-95 0. 20'-o Ant i lllony- 1 24 0.11 o Filter Sludge not determined Dry Gomprcssibl c'Vastc Vill.lCS C. I rrad 1 '1 tcd Colllponcnts none 9-7

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