Text

Corrected Annual Radioactive Effluent Release Rept for DC Cook Nuclear Plant Units 1 & 2.
	ML17333A402
Person / Time
Site:	Cook
Issue date:	12/31/1995
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17333A400	List: ML17333A399; ML17333A402;
References
	NUDOCS 9604080302
	Download: ML17333A402 (17)
	v • d • e

22, and 28) and storm debris on traveling screens (December

~11 . 'On.","8Lovam)Iei,:;::f8':,',,'gt ep,:,mei:,n,t,urbintewagerneratcr5ewe&s". m'an1@f'1P Unit 2 entered the reporting period at 100X RTP. On February 23, a reactor trip occurred due to a failed closed main feedwater regulating valve. Mode 1 was entered on March 1.

Power was decreased to 55X on April 19 and April 29 for east main feed pump condenser cleaning and testing. Power was restored to 100X on May 2. On August 24, power was decreased to 80X to remove j/21 circulating water pump from service to support diving operations on unit 1. On August 25, power was returned to 1002 RTP. Qn',,:,:'Auauwaei'!@EPPa~~xijctcc'tdi"gttriPsdcccmurrceen

)~!...,i::,ii." ': m:,:,-;., !,:,,::.;,'- "'"-,':::',,:-:p':':::::,:,::::-:::i'i:::,::::,,"-";:i'!pro gems with reactor coolant'system solenoid valves and power operated relief valve limit switches. Power was returned to 100X on September 8. However, a reactor trip occurred on September 8 due to misoperation of reactor trip breaker A during surveillance testing. Power was returned to 100X on September 17 after clamtrol treatment of the service water systems on September 15. On October 18, power was decreased to 94X to meet technical specification 3.5.2 requirements for removal of 4 loop injection from the safety injection system.

On October 19, power was returned to 100X RTP. On November '17 and December 8, power was decreased to 95X to place moisture separator reheaters in service. Power was returned to 100X RTP on December 9. On December 10, power was decreased .to 55X to perform main feed pump condenser cleaning. Power was returned to 100X RTP on December 11. Note that the unusual events described above for unit 1 also affected unit 2.

II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT UPON MAN Since a number of release points are common to both units, the release data from both units are combined to form this two-unit, Annual Radioactive Effluent Release Report. Appendix 1 of this report presents the information in accordance with technical specification 6.9.1.9.

The "MIDAS System" by Pickard, Lowe and Garrick, Inc., is a computer code that ca1culates doses for all isotopes that were released by the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were well within technical specifications limits.

There were no abnormal liquid or gaseous releases during 1995.

Li uid Releases During the first quarter of 1995 there were 20 liquid batch releases. There were 23 during the second quarter, 34 in the third quarter, and 28 in the fourth quarter.

2 qiaeoS0S02 9a040S:I' PDR 'DOCK 05000315 R .." PDR LI"

There were no abnormal liquid releases during 1995.

For the, purpose of dose assessment, batch releases were treated as continuous releases. Estimated doses (in millirem) to maximally exposed individuals via the liquid release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Gaseous Releases t During the first quarter of 1995 there were 162 gaseous batch releases, 170 in the second quarter, 105 in the third quarter, and 189 in the fourth quarter.

Containment pressure reliefs (CPR) are listed as batch releases in accordance with NRC inspections 50-315/89016 (DRSS) and 50-316/89017 (DRSS). There were 606 CPRs during 1995.

There were 15 waste gas decay tank releases and 2 releases from CVCS HUTs during 1995.

In calculating the dose consequences for continuous and batch gaseous releases during 1995, the meteorological data measured at the time of release were used.

The estimated doses (in millirem) to maximally exposed individuals via the gaseous release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Solid Waste Dis osition There were 38 shipments of radioactive waste in 1995.

III. METEOROLOGICAL Appendices 2.1, 2.2, 2.3, and 2.4 of this report contain the cumulative joint frequency distributions of wind speed and wind direction, corresponding to the various atmospheric stability classes for the first, second, third and fourth quarters of 1995. Hourly meteorological data are available for review and/or inspection upon request.

IV. OFFSITE DOSE CALCULATION MANUAL ODCM CHANGES The Offsite Dose Calculation Manual, PMP 6010.0SD.001, was changed during the report period. The reasons for the changes and the PNSRC approval are documented on the procedure cover sheet. These changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Appendix 3.0 contains the revised ODCM with changes indicated by marginal bars.

V. TOTAL DOSE Section 4.2.5 of th'e ODCM requires that the dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to no more than twenty-five (25) millirem to the total body or any organ over a period of twelve (12) consecutive months to show conformance with the requirements of 40 CFR Part 190. The maximum cumulative dose to an individual from liquid and gaseous effluents during 1995 was well within the ODCM limits. Measurements using thermoluminescent 3

dosimeters at ten (10) offsite background stations indicate that the dose due to direct radiation is negligible.

An assessment showed that radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary are also negligible.

VI. CONCLUSION Based on the information presented in this report, it concluded that the Donald C. Cook Nuclear Plant Units 1 and 2 is performed their intended design function with no demonstrable adverse affect on the health and safety of the general public.

arid storm debris traveling screens (December s: '!i ~gg:,: met 22, and 28 on -

it tip'iiadi;::"::~ii!!ih ig'22ovemherigi28: ':Qt'h%'jiimcuaiin~ti'i'vb'ice~i:"..'etnetatc~rwa "o'ar'a1Ti1.'$i1j'i+i:,>>:thii~hi'iil',, T'e untitc exi'ted the rse'per%Mug per'r'o WaMOiOwX"RiTP"".""

Unit 2 entered the reporting period at 100X RTP. On February 23, a reactor trip occurred due to a failed closed main feedwater regulating valve. Mode 1 was entered on March 1.

Power was decreased to 55X on April 19 and April 29 for east main feed pump condenser cleaning and testing. , Power was restored to 100X on May 2. On August 24, power was decreased to 80X to remove fj21 circulating water pump from service to support diving operations on unit 1. Dn August 25, power was returned to 1002 RTP. Qn.':,.:,."Augii'iieq+8,:~ta:;,'isa'otocr,:::::tir,"iP;,"':~cccnxxeg dcuxejiitp:;,;a:;:::tcrhv On Septembe~r, coo down was commenced to resolve problems with reactor coolant system solenoid valves and power operated relief valve limit switches. Power was returned to 100X on September 8. However, a reactor trip occurred on September 8 due to misoperation of reactor trip breaker A during surveillance testing. Power was returned to 100X on September 17 after clamtrol treatment of the service water systems on September 15. On October 18, power was decreased to 94X to meet technical specification 3.5.2 requirements for removal of 4 loop injection from the safety injection system.

On October 19, power was returned to 100X RTP. On November 17 and December 8, power was decreased to 95X to place moisture separator reheaters in service. Power was returned to 100X RTP on December 9. On December 10, power was decreased .to 55X to perform main feed pump condenser cleaning. Power was returned to 100X RTP on December ll.

described above for unit 1 also affected unit 2.

Note that the unusual events II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT UPON MAN Since a number of release points are common to both units, the release data from both units are combined to, form this two-unit, Annual Radioactive Effluent Release Report. Appendix 1 of this report presents the information in accordance with technical specification 6.9.1.9 ~

The "MIDAS System" by Pickard, Lowe and Garrick, Inc., is a computer code that ca1culates doses for all isotopes that were released by the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were well within technical specifications limits.

There were no abnormal liquid or gaseous releases during 1995.

Li uid Releases During the first quarter of 1995 there were 20 liquid batch releases. There were 23 during the second quarter, 34 in the third quarter, and 28 in the fourth quarter.

2

There were no abnormal liquid releases during 1995.

For the purpose of dose assessment, batch releases were treated as'ontinuous releases. Estimated doses (in millirem) to maximally exposed individuals via the liquid release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Gaseous Re eases During the first quarter of 1995 there were 162 gaseous batch releases, 170 in the second quarter, 105 in the third quarter, and 189 in the fourth quarter.

Containment pressure reliefs (CPR) are listed as batch releases in accordance with NRC inspections 50-315/89016 (DRSS) and 50-316/89017 (DRSS). There were 606 CPRs during 1995.

There were 15 waste gas decay tank releases and 2 releases from CVCS HUTs during 1995.

In calculating the dose consequences for continuous and batch gaseous releases during 1995, the meteorological data measured at the time of release were used.

The estimated doses (in millirem) to maximally exposed individuals via the gaseous release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Solid Waste Dis osition There were 38 shipments of radioactive waste in 1995.

III. METEOROLOGICAL Appendices 2.1, 2.2, 2.3, and 2.4 of this report contain the cumulative joint frequency distributions of wind speed and wind direction, corresponding to the various atmospheric stability classes for the first, second, third and fourth quarters of 1995. Hourly meteorological data are available for review

'and/or inspection upon request.

r IV. OFFSITE DOSE CALCULATION MANUAL ODCM CHANGES The Offsite Dose Calculation Manual, PMP 6010.0SD.001, was changed during the report period=. The reasons for the changes and the PNSRC approval are documented on the procedure cover sheet. These changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Appendix 3,0 contains the revised ODCM with changes indicated by marginal bars.

V. TOTAL DOSE Section 4.2.5 of the ODCM requires that the dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to no more than twenty-five (25) millirem to the total body or any organ over a period of twelve (12) consecutive months to show conformance with the requirements of 40 CFR Part 190. The maximum cumulative dose to an individual from liquid and gaseous effluents during 1995 was well within the ODCM limits. Measurements using thermoluminescent 3

dosimeters at ten (10) offsite background stations indicate that the dose due to direct radiation is negligible.

An assessment showed that radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary are also negligible.

VI. CONCLUSION Based on the information presented in this report, it concluded that the Donald C. Cook Nuclear Plant Units 1 and' is performed their intended design function with no demonstrable adverse affect on the health and safety of the general public.

4

22, and 28) and storm debris on traveling screens December

11) . OpPS~veeSer~~&~tSe',+pin'-'>> evvgeePgemx,;atomic'waj>,.:ma~, X+

Ci~pysd:..~,.:~6'n$ ~8egemwbe, '."-l5@,",".

$'te~~i~~z3 ',, The unit ex't'e'c'i the reporting perio

-'ir'algid'id$

'at TOoOX RTP.

Unit 2 entered the reporting period at 100X RTP. On February 23, a reactor trip occurred due to a failed closed main feedwater regulating valve. Mode 1 was entered on March l.

Power was decreased to 55X on April 19 and April 29 for east main feed pump condenser cleaning and testing. Power was restored to 100X on May 2. On August 24, power was decreased to 80X to remove $ 21 circulating water pump from service to support diving operations on unit 1. On August 25, power was

,"~!,:. i!i'".,.:!i.: 's~j~:

returned to 1002 RTP. O~n!,.'Augusta'.,::25',:;,'@%~5iraaoto~rA;."std'>jgaa'tetrad orm;ngtankkexcreme";ha;gh53;eve3~.

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September X, coo'1 ctoown was c'o'mmenced to resolve problems with reactor coolant system solenoid valves and power operated relief valve limit switches. Power was returned to 100X on September 8. However, a reactor trip occurred on September 8 due to misoperation of reactor trip breaker A during surveillance testing. Power was returned to 100X on September 17 after clamtrol treatment of the service water systems on September 15. On October 18, power was decreased to 94/ to meet technical specification 3.5.2 requirements for removal of 4 loop injection from the safety injection s'stem.

On October 19, power was returned to 100X'RTP. On November 17 and December 8, power was decreased to 95X to place moisture separator reheaters in service. Power was returned to 100X RTP on December 9. On December 10, power was decreased .to 55X to perform main feed pump condenser cleaning. Power was returned to 100X RTP on December 11. Note that the unusual events described above for unit 1 also affected unit 2.

II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT UPON MAN Since a number of release points are 'common to both units, the release data from both units are combined to form this two-unit, Annual Radioactive Effluent Release Report. Appendix 1 of this report presents the information in accordance with technical specification 6.9.1.9.

The "MIDAS System" by Pickard, Lowe and Garrick, Inc., is a computer code that calculates doses for all isotopes that were released by the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were well within technical specifications limits.

There were no abnormal liquid or ga'seous releases during 1995.

Li uid Releases During the first quarter of 1995 there were 20 liquid batch releases. There were 23 during the second quarter, 34 in the third quarter, and 28 in the fourth quarter.

2

There were no abnormal liquid releases during 1995.

For the purpose of dose assessment, batch releases were treated as continuous releases. Estimated doses (in millirem) to maximally exposed individuals via the liquid release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Gaseous Releases During the first quarter of 1995 there were 162 gaseous batch releases, 170 in the second quarter, 105 in the third quarter, and 189 in the fourth quarter.

Containment pressure reliefs (CPR) are listed as batch releases in accordance with NRC inspections 50-315/89016 (DRSS) . and 50-316/89017 (DRSS). There were 606 CPRs during 1995.

There were 15 waste gas decay tank releases and 2 releases from CVCS HUTs during 1995.

In calculating the dose consequences for continuous and batch gaseous releases during 1995, the meteorological data measured at the time of release were used.

The estimated doses (in millirem) to maximally exposed individuals via the gaseous release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Solid Waste Dis osition There were 38 shipments of radioactive waste in 1995.

Appendices 2.1, 2.2, 2.3, and 2.4 of this report contain the cumulative joint frequency distributions of wind speed and wind direction, corresponding to the various atmospheric stability classes for the first, second, third and fourth quarters of 1995. Hourly meteorological data are available for review and/or inspection upon request.

OFFSITE DOSE CALCULATION MANUAL ODCM CHANGES The Offsite Dose Calculation Manual, PMP 6010.0SD.001, was changed during the report period. The reasons for the changes and- the PNSRC approval are documented on the procedure cover sheet. These changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Appendix 3.0 contains the revised ODCM with changes indicated by marginal bars.

TOTAL DOSE Section 4.2.5 of the ODCM requires that the dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to no more than twenty-five (25) millirem to the total body or any organ over a period of twelve (12) consecutive'onths to show conformance with the requirements of 40 CFR Part 190. The maximum cumulative dose to an individual from liquid and gaseous effluents during 1995 was well within the ODCM limits. Measurements using thermoluminescent 3

dosimeters at ten (10) offsite background stations indicate that the dose due to direct radiation is negligible.

An assessment showed that radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary are also negligible.

VI. CONCLUSION Based on the information presented in this report, it concluded that the Donald C. Cook Nuclear Plant Units 1 and 2 is performed their intended design function with no demonstrable adverse affect on the health and safety of the general public.

4

22, and 28) and storm debris on travelin screens December ll) . OA~~KovoN5@x':~+8'Sing.;;$ 8P~~N'~iAAPurSippjgc'0'8x'Shor,;;.';,,va'8~JR@ ',','Xp jg'Zajg'eile4$~ii'."',:e;"9$ dg'The unitr exudited the reporting period at'10'OX RTP.

Unit 2 entered the reporting period at 100X RTP. On February 23, a reactor trip occurred due to a failed closed main feedwater regulating valve. Mode 1 was entered on March 1.

Power was decreased to 55X on April 19 and April 29 for east main feed pump condenser cleaning and testing. Power was restored to 100X on May 2. On August 24, power was decreased to 80X to remove $ 21 circulating water pump from service to support diving operations on unit l. On August 25, power was retorted to 100X RTp. 0'! Rudue@FR uiireeo~tap~ tii'pie'oourred j

di,:".",'."i

'~iii."ilia '.;: ..."I,,,r,':,,:o!r* ",";,"-";4::::ih!jii!*,:-,"':, '"",: ';,:,"!:-":"",--';:;,"',":;p!:,'i';-":."

e'cps;., On 'Septem6er',' coo c own was commenced~to reso?ve pioblems with reactor coolant system solenoid valves and power operated relief valve 'limit switches. Power was returned to 100X on September 8. However, a reactor trip occurred on September 8 due to misoperation of reactor trip breaker A during surveillance testing. Power was returned to 100X on September 17 after clamtrol treatment of the service water systems on September 15. On October 18, power was decreased to 94X to meet technical specification 3.5.2 requirements for removal of 4 loop injection from the safety injection system.

On October 19, power was returned to 100X RTP. On. November 17 and December 8, power was decreased to 95X to place moisture separator reheaters in service. Power was returned to 100X RTP on December 9. On December 10, power was decreased .to 55X to perform main feed pump condenser cleaning. Power was returned to 100X RTP on December 11. Note that the unusual events described above for unit 1 also affected unit 2.

II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT UPON MAN Since a number of release points are common to both units, the release data from both units are combined to form this two-unit, Annual Radioa'ctive Effluent Release Report. Appendix 1 of this report presents the information in accordance with technical specification 6.9.1.9.

The "MIDAS System" by Pickard, Lowe and Garrick, Inc., is a computer code that calculates doses for all isotopes that were released by the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were'ell within technical specifications limits.

There were no abnormal liquid or gaseous releases during 1995.

Li uid Releases During the first quarter of 1995 there were 20 liquid batch releases. There were 23 during the second quarter, 34 in the third quarter, and 28 in the fourth quarter.

2

There were no abnormal liquid releases during 1995.

For the purpose of dose assessment, batch releases were treated as continuous releases. Estimated doses (in millirem) to maximally exposed individuals via the liquid release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.

Gaseous Releases During the first quarter of 1995 there were 162 gaseous batch releases, 170 in the second quarter, 105 in the third quarter, and 189 in the fourth quarter.

Containment pressure reliefs (CPR) are listed as batch releases in accordance with NRC inspections 50-315/89016 (DRSS) and 50-316/89017 (DRSS). There were 606 CPRs during 1995.

There were 15 waste gas decay tank releases and 2 releases from CVCS HUTs during 1995.

In calculating the dose consequences for continuous and batch gaseous releases during 1995, the meteorological data measured at the time of release were used.

The estimated doses (in millirem) to maximally exposed individuals via the gaseous release pathway are given in appendices 1.2, 1.3, 1 4, and 1.5 of this report.

~

Solid Waste Dis osition There were 38 shipments of radioactive waste in 1995.

III. METEOROLOGICAL Appendices 2.1,'.2, 2,3, and 2.4 "of this report contain the cumulative joint frequency distributions of wind speed and wind direction, corresponding to the various atmospheric stability classes for the first, second, third and fourth quarters of 1995. Hourly meteorological data are available for review and/or inspection upon request.

IV. OFFSITE DOSE CALCULATION MANUAL ODCM CHANGES The Offsite Dose Calculation Manual, PMP 6010.0SD.001, was changed during the report period. The reasons for the changes and the PNSRC approval are documented on the procedure cover sheet. These changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Appendix 3.0 contains the revised ODCM with changes indicated by marginal bars.

TOTAL DOSE Section 4.2.5 of the ODCM requires that the dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to no more than twenty-five (25) millirem to the total body or any organ over a period of twelve (12) consecutive months to show conformance with the requirements of 40 CFR Part 190. The maximum cumulative dose to an individual from liquid and gaseous effluents during 1995 was well within the ODCM limits. Measurements using thermoluminescent 3

dosimeters at ten (10) offsite background stations indicate that the dose due to direct radiation is negligible.

An assessment showed that radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary are also negligible.

VI. CONCLUSION Based on the information presented in this report, it concluded that the Donald C. Cook Nuclear Plant Units 1 and 2 is performed their intended design function with no demonstrable adverse affect on the health and safety of the general public.

4

22, and 28) and s'torm,debris on traveling screens (December

~11 O~IL" gowembox&g~ghe':"."msgnoturS'i~~s:-:$ 0tl@ratcmsmssr'ImantgggXp uirdppe 8:;!!ieIDIIOT'fi~lihnwembierP! PS':.":::,:'::.i."thiiVI~i%'an%!iturbtiie@~ffge'iIprgiVj~WÃd PhatiagIlei'eidbit~b": t4if~%"'~i:fS,. The'nit exi."ted 1'he repor'tiiig p'egioii at&'a'OX"RDT'P'".-

entered the reporting period at 100X RTP. On February

'nit 2

23, a reactor trip occurred due to a failed closed main feedwater regulating valve. Mode 1 was entered on March 1.

Power was decreased to 55X on April 19 and April 29 for east main feed pump condenser cleaning and testing. Power was restored to 100X on May 2. On August 24, power was decreased to 80X to remove f/21 circulating water pump from service to support diving operations on unit 1. On August 25, ~ower was returned to 1002 RTP. gn:::::,Au", g~%2bi~j~mXIrIga'crc/::; tn$ ppt occIIrrdadm "dnebi tne;a; e,".tu-up.r:

I", ato" is~o'1I'september 1 "c,'o'old o'wn'was commenced to resolve

~pro 'lems with reactor coolant system solenoid valves and power operated relief valve limit switches. Power was returned to 100X on September 8. However, a reactor trip occurred on September 8 due to misoperation of reactor trip breaker A during surveillance testing. Power was returned to 100X on September 17 after clamtrol treatment of the service water systems on September 15. On October 18, power was decreased to 94X to meet technical specification 3.5.2 requirements for removal of 4 loop injection from the safety injection system.

On October 19, power was returned to 100X RTP. On November 17 and December 8, power was decreased to 95X to place moisture separator reheaters in service. Power was returned to 100X RTP on December 9. On December 10, power was decreased .to 55X to perform main feed pump condenser cleaning. Power was returned to 100X RTP on December described above for unit 1 also affected unit 2.

ll. Note that the unusual events II. RADIOAC IVE RELEASES AND RADIOLOGICAL IMPACT UPON MAN Since a number of release points 'are common to both units, the release data from both units are combined to form this two-unit, Annual Radioactive Effluent Release Report. Appendix 1 of this report presents the information in accordance with technical specification 6.9.-1.9.

The "MIDAS System" by Pickard, Lowe and Garrick, Inc., is a computer code that ca1culates doses for all isotopes that were released by the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were well within technical specifications limits.

There were no abnormal liquid or gaseous r'eleases during 1995.

Li uid Releases During the first quarter of 1995 there were 20 liquid batch releases. There were 23 during the second quarter, 34 in the third quarter, and 28 in the fourth quarter.

2

There were no abnormal liquid releases during 1995.

For the purpose of dose assessment, batch releases were treated as continuous releases. Estimated doses (in millirem) to

'maximally exposed individuals via the liquid release pathway are given in appendices 1.2, 1.3, 1.4, and 1.5 of this report.