B13458, Semiannual Radioactive Effluents Release Rept for Jul-Dec 1989

Semiannual Radioactive Effluents Release Rept for Jul-Dec 1989

ML20012A182
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1989
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B13458, NUDOCS 9003080452
Download: ML20012A182 (14)

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March 1, 1990 Docket No. 50-213 B13458 Re:

10CFR50.36a a~

U.S.-Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC'20555

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1 Gentlemen:

Haddam Neck Plant Semiannual Radioactive Effluents Release Report

'In accordance with the requirements of 10CFR50.36a, the Technical Specifica-tions and the.".adiological Effluents Monitoring Manual,. a copy of the Semi-annual Radioactive Effluents Release Report is herewith submitted, t

This report includes'a ' summary of the quantities of solid radioactive waste and liquid and gaseous effluents'for the period of July through December 1989.

An-Annual Radioactive Effluents Dose Report ~ (to be submitted. in = Harch 1990) will include an assessment ' of. the radiation doses due to 'the radioactive l

. liquid ~and gaseous effluents during the calendar year (January-through

~

December 1989).

- The report has been prepared in accordance with the format - of Regulatory Guide 1.21, and copies of the report are being forwarded in' accordance with the provisions of 10CFR50.4(b)(1).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY-

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W Senr//Mro'cika [/

E.'~J or Vice President cc:

W. T. Russell, Region I Administrator A. B. Wang, NRC. Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant 90030B0452 891231 DR ADOCK-050 3

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March 1, 1990-4 Docket No. 50-213 B13458 l

Re:

10CFR50.36a U.S. Nuclear Regulatory Commission Attention:

Document' Control Desk J

Washington, DC 20555 Gentlemen:

Haddam Neck Plant Semiannual Radioactive Effluents Release Report

.In accordance with the requirements of 10CFR50.36a, the. Technical Specifica-tions and the Radiological Effluents Monitoring Manual, a copy of the Semi-annual _ Radioactive Effluents Release Report is herewith submitted.

This report includes a summary of the quantities of solid radioactive waste

- and liquid and gaseous effluents for the period of July through December 1989.

An Annual Radioactive Effluents Dose. Report (to be submitted in March 1990) will include.an assessment of the radiation doses due to the radioactive liquid and gaseous effluents during the calendar year (January ~through December 1989).

The report has been prepared in accordance with the formats of Regulatory Guide 1.21, and copies of the report _ are being forwarded in accordance with the provisions of 10CFR50.4(b)(1).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY' M '

E.7f41ro'cika //

Senror Vice Pr(sident cc:

W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident inspector, Haddam Neck Plant OS3422 REV 4 88

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TABLE OF CONTENTS h

Table of Conten ts...........................................................................................

I Introd uc ti on..................................................................................................

2 i

Radiological Effluents Information........................................................ 3-4 Gaseous Effluents - Summation of all Releases................................ 5 Oaseous Effluents - Mixed Mode Release............................................ 6 Lignid Effluents - Summation of all Releases................................... 7 Liquid Effluents - B atch and Continuous............................................

8 SolidWaste.......................................................................................................

9-10,

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Attachment....................................................................................................... I1-i E

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ey Introduction l

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l The report is submitted for the Connecticut Yankee Atomic Power Company's Haddam t

Neck Plant in accordance with the requirements of 10CFR50.36a, and the Radiological i

Effluent Technical Specifications, and in the fortrat outlined by the U. S. NRC Regulatory Guide 1.21.

During the period July December 1989, the Haddam Neck Plant operated with a 31.5%

capacity factc,r of the Design Electrical Rating (DER). The unit entered Cycle XV Refueling Outage on September 2,1989.

This re sort presents data on radioactive matedals in airborne and liquid effluents as well 1

as solic radioactive materials shipped offsite during that period.

l The noble gas releases for the 6 month period was about five (5) times higher than previous periods. The beta sk!n dose consequences for the 3rd quarter was 13.16 mrad which exceeded the regulatory quarterly limit of 10 mrad. The annual dose consequences are, however, within the annual regulatory limits. The detailed dose consequences to the public will be reported by March 30,1990 in the Annual Radioactive Effluent Dose Report, i

The cause of the higher than normal releases of noble gases was a result of fuel clad damage caused by c ebris left behind in the reactor coolant system from repair work on the thermal shie d in the 1987 outage. This type of damage was not previously experienced by CYAPCO. This was previously reported to NRC as LER 89 20.

At this time the plant is in an extended outage with reconstitution of the fuel to ensure fuel with failed clad is removed. A special debris clean up program for the reactor coolant system is being planned for this outage. In addition, a specia license (or.dition has been proposed to NRC to require an augmented primary coolant chemistry program that will help in the early detection of these types of fuel clad failures.

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RADIOLOGICAL EFFLUENTS INFORMATION l

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Third Ounrier Fourth Ouarter E Beta EGamm_a E Beta E Gamma l

I Average En (E) (in MeV)

ForFission n Activation Gates 1.15E 4.35E-02 2.22E-01 9.94E-03 I

11 Measurements and ApDfoximation of Total RnMonctivity i

a.

Fiction and Activation Games: Stack effluents are monitored by a scintillation detector in parallel with an in line G. M. Detector. Gas samples are collected on the stack and are analysed for low level fission and activation gases.

b.

lodines: Continuous in line charcoal sample filter en main stack effluent. Charcoal 5

filten are then analysed foriodines.

c.,

Partienintes: Continuous in line particulate sample filter on main stack effluent. Particulate sam >les are then ocunted for gamma a@'ity. A monthly composite is made from i

wee dy samples. The monthly composite is checked for gross alpha and 89Sr / 90Sr.

d.

Linuld Effluentet in-line scintillation detectors monitor waste liquid being released.

Prior to dischar ge a sample is taken. Principal gamma emitten, entrained gases j

and tritium ana'yses are A monthly composite is made from batch and weekly i

samples. Gross Alpha, 9Sr. 90Sr. and 55 Fe are determined.

I!!

Eadioactive Efhents Monitor Inonerability 6 30 days)

On June 16,1989, test tank monitor R 22 was declared out of service due to inability of the check source to be read. De cause was due to intemal background around the detector from plateout. A Plant Design Change Evaluation is g through CY Engineering to irrplement a pnmary water flush line through the detector, plementation is expected dunng the current refuehng outage.

The trip set point function is backed up by monitor R-18, thereby providing automatic termination of release should the trip set point be exceeded. All applicable precautions (double sampling of l

discharges) per RETS are b:ing observed until R 22 is returned to service.

t IV REMM/ODCM/PCP Chanpq The REMM/ODCM/PCP was revised effective September 30,1989. The revision deleted the.

requirement to have the NRC approve REMM changes prior to implementation.

The NRC ap;) roved this cht:nge when it approved a PTSCR to delete the requirement for NRC review of REMM changes. This change was recommended by the NRC in their Generic letter 89-01, and is attached.

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V Batch Releases a.

Liquid 1)

Numberof bnch Meases:

89 2)

Total time pedo 3 Ibr bite.h release:

513.7 Hours 3)

Maximum time pmiod fx a tatch release:

16.2 Hours 4)

Average time 3rd.od for batch release:

5.4 Hours 5)

Minimum time pedas for a batch release:

0.3 Hours 6)

Average streara Dow thring paiods of 15,800 cubic feet release of effluent bro a Dowing stream:

persecond b.

Gaseous 1)

Numberof hatch releas:a:

51 2)

Total time penc4 far tmtch.tleases:

547.8 Hours 3)

. Maximum time period fcr a batch release:

77.9 Hours 1

4)

Average time period for bmch releases:

17.7 Hours 5)

Minimum time period for a batch release:

1.5 Hours i

i VI Abnormal Releases

• None l '

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.-0 Releases that exceed Technical Specification Limits 4 of il

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EFFLUENT & WASTE DISPOSAL SEMI ANNUAL REPORT - 1989 G ASEOUS EFFL UENTS SUMM ATION OF ALL REI EASES 3rd 4th EST. TOTAL UNIT QUARTER QUARTER ERROR %

A.

FISSION & ACTIVATION GASES

1. Totalrelease Ci 1.23E@4 1.23E+03 1.40E+01

2. Average release rate for period pCi/sce 1.55E43 1.55E+02 H.

IODINES i

1. TotalIodine.131 Ci 1.29E-02 1.42E-03 1.30E+01

2. Average release rate for period pCi/sec 1.62E-03 1.79E-04 C.

PARTICULATES

1. Paruculates with half hves

> 8 days Ci 6.01E-04 6.10E 05 1.40E41

2. Average release rate for period pCi/sec 7.56E.05 7.67Er06

3. Gross alpha radioactivity Ci diDA diDA D.

TRITIUM J

1. Totalrelease Ci 9.12E+01 2.14E+01 8.00E40

2. Average release rate for period pCi/sec 1.15E+01 2.69E+00 i

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l EFFLUENT & WASTE DISPOSAL SEMI ANNUAL REPORT - 1989

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G ASEOUS EFFLUENTS - MIXED MODE RELEASES CONTINUOUS MODE BATCll MODE 3rd 4th 3rd 4th NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER FISSION GASES Argon-41 Ci diDA diDA 5.53E 02 diDA Krypton 85 O

7.34E+02 5.51E42 2.37E+02 4.44 E+02 Krypton 85m O

2.33E+00 dfDA 6.06E-01 d1DA Krypton-87 O

efDA diDA 1.04E-01 diDA Krypton 88 O

efDA diDA 2.61 E-01 diDA Xenon 131m O

1.41E+02 1.71E+00 3.39E+01 2.40E+01 Xenon 133 O

5.91E+03 1.17E+01 5.04E+03 1.98E42 Xenon 133m O

2.74E+01 diDA 4.85E+01 diDA Xtnon 135 O

6.32E+01 diDA 4.58E+01 diDA Xenon 135m Q

diDA diDA 4.94E-02 diDA Xenon-137 O

dOA dfDA 1.13E 02 dfDA Xenon 138 Q

ofDA diDA 3.98E-02 diDA TOTAL FOR PERIOD Q

6.88E+03 5.64 E+02 5.41E+03 6.66E+02 TRITIUM H-3 Q

7.05E+01 2.05 E+01 2.07E+01 9.45E-01 HALOGENS Iodine 131 Ci 1.29E-02 1.42E-03 lodine 133 0

6.02E-04 dfDA lodme 135 O

diDA ofDA TOTAL FOR PERIOD Q

l.35E 02 1.42E-03 PARTICULATES Alpha O

diDA diDA Chmmium-51 Q

efDA diDA Manganese-54 O

diDA diDA Cobalt 58 Ci diDA diDA Cobalt-60 Q

diDA diDA Strontium-89 O

diDA diDA Strontium 90 Q

l.37E-08 2.17E-05 Zirconium / Niobium-95 O

<MDA diDA Ruthenium-103 O

diDA dfDA Ruthenium-106 O

ofDA diDA Cesium 134 0

2.20E-04 5.00E-06 Cesium-137 O

3.81 E-(M 3<43E-05 Banum/ Lanthanum-140 Q

diDA diDA Cerium-141 Ci diDA diDA Cerium 144 O

dfDA diDA TOTAL FOR PERIOD Q

6. ole-04 6.10E-R5 V

• • Reported under continuous mode.

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i EFFLUENT & WASTE DISPOSAL SEMI. ANNUAL REPORT - 1989 LIOUID EFFLUENTS SUMMATION OF AI L RELEASES 3rd 4th EST. TOTAL UNIT QUARTER QUARTER ERROR %

A.

r!SSION & ACTIVATION PRODUCTS

1. Totalrelease(notincluding tritium, noble gases, alpha) 0 2.01E-01 3.92E-02 1.10E401

2. Averagedilutedconcentration during period pCi/ml 1.21E-06 8.25E-07 B.

TRITIUM I

1. Totalrelease O

9.81E+02 2.44E402 3.50E+00

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2. Averagedilutedconcentration during period pCi/ml 5.91E-03 5.14E-03 C.

DISSOLVED & ENTRAINED GASES l

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1. Totalrelease Q

3.54E+00 9.16E-02

'1.90E+01

2. Average diluted concentration during period pCi/ml 2.13E-05 1.93E-06 D.

GROSS ALPIIA RADIOACTIVITY

1. Totalrelease O

4.39E-02 6.25E-06 8.00E+00 E. Volume of waste released (prior to dilution)

Liters 3.59E+07 1.03E+06 3.00E+00 l Liters F. Volume of dilution water used i

1.66E+08 4.75E+07 2.50E+00 during period 7 of il

EFFLUENT & WASTE DISPOSAL SEMI ANNUAL REPORT 1989 LIOUID FFFLUENTS CONTINUOUS MODE HATCll MODE 3rd 4th 3rd 4th NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Alpha O

3.85 E-02 dIDA 5.37E-03 6.25E-06 Chromium-51 O

diDA dIDA 1.44E-03 2.38 E-04 Manganese-54 Q

diDA dfDA 2.71E-04 3.31 E-05 Iron 55 O

1.23 E-02 diDA 1.06E-01 2.76E-02 Cobalt 57 O

diDA diDA ofDA diDA Cobalt 58 O

dfDA diDA 3.86E-03 1.16E-03 Iron-59 O

efDA dOA 4.52E-04 1.07 E-04 Cobalt-60 Q

diDA efDA 2.19E-02 2.36E 03 Strontium 89 Q

2.46E-04 etDA 2.05E-05 1.07E 05 Strontium-90 0

7.87E-04 dfDA 5.99E-04 1.47 E-05 Zirconium-Niobium-95 Q

diDA diDA 1.48E-04 3.19E 05 I

Ruthenium-103 Q

diDA dOA 2.92E-04 2.25E-05 Ruthenium-106 O

dOA dOA dOA dOA Silver 110m Q

<MDA diDA 6.73E-05 d4DA Antimony 124 Q

<MDA diDA dOA diDA Antimony 125 O

diDA

<MDA 1.82E-05 3.00E-05 lodine-131 Q

3.07 E-04 dfDA 6.42E 03 6.50E-03 lodine 132 O

diDA ofDA diDA efDA lodine 133 O

diDA diDA

<MDA dOA lodine 134 Q

diDA d4DA

<MDA diDA Cesium-134 O

dfDA dfDA 6.50E-04 2.90E-04 lodine-135 Ci diDA dfDA

<MDA 44DA Cesium 137 O

dfDA

<MDA 1.52E 03 7.78E-04 13 anum-Lanthanum-140 Q

<MDA diDA 3.00E-05 41DA Cerium-144 O

d1DA dfDA dfDA diDA Total for Period (above)

Ci 5.21E 02 dfDA 1.49E-01 3.92E 02 Tritium O

4.81E 01 diDA 9.81 E+02 2.44E+02 Krypton 85 O

diDA diDA 9.45E-02 2.61 E-02 Xenon 131M Q

diDA diDA 1.19E-01 dfDA Xenon 133 O

diDA diDA 3.30E400 6.55E-02 l

Xenon 133M Ci d1DA dOA 2.64E-02 diDA Xenon 135 O

diDA diDA 5.09E-03 diDA S of 11

E 1

1 SOIJD WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOf m WASIE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIA' FED FUEI3 6-Month EST. TOTAL 1.

TYPE OF WASTE

.UNII Period ERROR %

a.

Spent resins, filter m3 17.034 i 1.0E41 lud es, evaporator O

595.361 tt m,etc.

b. Dry co ssible m3 99.81 i 1.0E@l

Waste, taminated 0

17.100 eqmp., etc.

c.

Irradiated components m3 N/A il.0E41 0

2. ESTIMATE OF MA.10R NUO InE WMPOSITION SY TYPE OF WASTEHn %

a.

Co60 20.667 b.

Co60 10.3 Cs137 22.681 Cs137 7.55 Cs134 18.869 CoS8 2.98 CoS7 0.006 Cs134 1.41 CoS8 2.966 H3

.325 Mn54 2.321 Cl4

.247 Cel44 0.074 Tc99 2.868E-02 H3 0.021 1129 0.151 04 0.081 Ni63 5.87 Tc99 2.93E-04 Fe55 61.8 1129' 6.29E-05 Sr90 9.056E-02 Ni63 3.804 Pu241 8.86 Fe55 26.536 Cm242 1.649E-02 Sr90 0.149 Pu238 0.189 Pu241 0.300 Pu239 2.237E-02 Pu238

.011 Pu240 2.237E-02 Pu239 1.66E-03 Am241 1.917E-02 Pu240 1.66E-03 Cm243 1.118E-02 Am241 4.57E-03 Cm244 1.118E-02 Cm242 2.68E-03 Np237 3.195E-03 Cm243 2.03E-03.

Cm244 2.03E-03 9 of 11

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SOLID WASTES DISPOSmON NUMBER OF SHIPMENTS MODE OP 'IRANSPORA*nON DESTINATION 10 Truck Barnwell, SC.

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10 Truck Richland, WA.

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IRRADIATED FUEL SHIPhENTS mISPOSmON)

None C.

ADDmONALINIORhMTION

1. Solidification agents utilized:

N/A

2. Containerinformation:

ft 3

a. High integrity Container 119

b. High Integrity Container 193

c. Steelliners 182

d. Steelboxes 96 10 0f il

9/3CiB9 R:v.1 1

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RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation, g

All changes and their rationale shall be documented in the Semiannual Radioactive Effluent Release Report.

It shall be the responsibility of the Station Superintendent to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the TecanicalSpecifications.

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