ML20065T360
| ML20065T360 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/19/1990 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20065T357 | List: |
| References | |
| NUDOCS 9012280073 | |
| Download: ML20065T360 (20) | |
Text
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2.0 tlMITING COND1110NS FOR OPERATIONS 2.9 Radioactive Effluenti (Continued) 2.9.1 t.iouid and Gaseous Effluents (Continued) one or more of the equipment or subsystem (s) identified in the ODCM, a special report, pursuant to Specification 5.9.3, shall be prepared and submitted to the Commission within 30 days. This report shall include the following information:
(i) Identification of equipment or subsystem (s) not operable and reason for inoperability.
(ii) Action (s)takentorestoretheinoperableequipmentto operable status.
(iii) Summary description of action (s) taken to prevent a recurrence.
- d. The hydrogen and oxygen monitors shall be monitoring the in-service gas decay tank during the transfer of waste gases to tne gas decay tank and the concentration of hydrogen and oxygen shall be limited to below flammability concentrations. Whenever the monitors are inoperable, transfer of waste gases to a gas decay tank may continue provided grab samples are taken from the gas decay tank and (1)every8hoursduringdegassingoperations, I analy(szed:2Tdailyduringotheroperations, and
- e. (4) The stask-men 4ters-for Auxiliary Buildina Exhaust Stack gaseous, particulate, and iodine activit4esy monitors may be inoperable provided that 1) releases from a gas decay tank, containment pressure relief line, and the containment purge line are secured, and 2) whenever the vent 44at4en Aux 11iarv Buildinn Exhaust sltack gas or particulate activity be takenmonitor and analyzedis inoperable, once perap3 rop8)(riate eig1t hours.grab samples will L (44) During power operation, the condenser air ejector discharge l shall be monitored for gross radioactivity. If this monitor is inoperable, grab samples shall be taken and analyzed daily for principal gamma emitters.
f, E During release of gaseous radioactive wastes from the gaseous waste discharge header or during containment venting to the vent 44at4en Auxiliary Buildina Exhaust 51 tack, the l following conditions shall be met:
(i) The gas, iodine, and particulate monitors shall be monitoring the vent Auxiliary Buildina Exhaust sStack.
(ii) At least one exhaust fan shall be in operation.
(-lii) The effluent control radiation monitors shall be set in accordance with the ODCM to alarm and automatically terminate the releases prior to exceeding the limits specified in 2.9.1(2)a(i) above, l
gg22 g g g g 2-44 Amendment No. 127 -86 P PDR
(iv) The activity shall be monitored and recorded. The flow rate shall be monitored and recorded, or determined by calculation.
(v) During the release of gaseous wastes from the contain-ment purge line, a containment gas monitor and a particulate monitor shall monitor the containment, in addition to conforming with (i) through (iv) above.
- h. Durina releases from the Laboratory and Radioactive Waste Drocessina Buildina Exhaust Stack, the followina conditions shall be met:
(i) The laboratory and Radioactive Waste Processina Buildina (LRWPB) Exhaust Stack cas, iodine, and particulate monitors shall be monitorina the LRWPB Exhaust Stack. The effluent control radiation monitors shall be set in accordance with the ODCM to alarm prior to exceedina the limits specified in 2.9 l(2)a(i) above. The cas activity monitor may be inoperable provided that appropriate arab samples be taken and analyzed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The particulate and iodine activity monitors may be inoperable provided that samples are continuousiv collected as reauired in Table 3-12.
(ii) The effluent flow rate shall be monitored and recorded, or determined by calculation.
Basis Releases of radioactivity in liquid wastes within the design objective levels provide reasonable assurance that the resulting annual exposure from liquid effluents will not exceed the limits specified in Appendix I to 10 CFR Part 50. These specifications provide reasonable assurance that the resulting exposure will not exceed 3 mrem to total body or 10 mrem to any organ. At the same time, these specifications aermit the fiexibility of operation, compatible with considerations of lealth and safety, to assure that the public is provided a dependable source of power under unusual o)erating conditions which may temporarily result in releases ligher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience, calculation procedures based on models and data set forth in Regulatory Guide 1.109, and the evaluation of Fort Calhoun facility in accordance with Appendix 1 of 10 CFR Part 50 dose design objectives. The design objectives take into account a combination of variables including fuel failures, primary system leakage, primary-to-secondary system leakage and the performance of various radioactive waste treatment systems.
Specification 2.9.1(1)a requires the licensee to limit the concentration of radioactive materials in liquid effluents released from the site to levels specified in 10 CFR Part 20, Appendix B, for unrestricted areas. This specification provides assurance that no member of the general public will be exposed at any time to liquid 2-45 Amendment No. 12,86
l 2.0 LIMITING CONDITIONS FOR OPERATIONS
'2. 9 Radioactive Effluents (Continued) 2.9.1 LiauidandGaseousEffluents(Continued)
Basis (Continued) requirements in accordance with Section IV.A of Appendix I to 10 CFR Part 50, in addition to the requirements of Section 5.9 of these Tech-nical Specifications.
Specification 2.9.1(2)c requires the operation of equipment or subsystem (s) of the radioactive gaseous waste system, as identified in the ODCM, to reduce the release of radioactive materials in gaseous effluents to as 1)w as reasonably achievable, consistent with the requirements of 10 CFR Part 50.36a, and General Design Criterion 60 of Appendix A to 10 CFR Part 50. Normal use of the equipment or subsystem (s) in the radioactive gaseous waste system provides reasonable assurance that the quantity released will not exceed the design objectives.
Specification 2.9.1(2)d ensures that the concentration of potentially explosive gas mixtures entrained in the gas decay tank (s) will be main-tained below the flammability limits of hydrogen and oxygen.
Maintaining the concentration of hydrogen and oxygen below their flammability limits with a measurement program provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
Specification 2.9.1(2)e provides assurance that releases from gas decay tank, Auxiliary Buildina Fxhaust Stack. containment pressure l relief line, and containment purge line are not made whenever the vent 44atien stick caseous, particulate and iodine monitors are l inoperable.
Ik4s-s1pecifica*. ion aise 2.9.1(2)f assures that the gross l
-radioactivity, auring power operation, is monitored from the condenser air ejector dischar0e+
Specification 2.9.1(2)fa requires operation of suitable equi) ment to l dilute, control, and monitor in order to provide assurance tlat radioactive materials released in the gaseous effluents are properly controlled and monitored in accordance with the requirements of L General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A.
Specification 2.9.1(2)h provides provisions for releases from the Laboratory and Radioactive Waste Processina Buildina (LRWPB) whenever the LRWPB Exhaust Stack cas, particulate or iodine activity monitors l are inoperable.
2-47 Amendment No.86
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TRBIE 3-3 . _ !
Mnsm Fi<wouY3ES Em CHEXIS, CALTBRATIOG AND TESTRG ~
OF MISmrTNE00S DETRUMDTIATICN AND CNIROIS I
, surveillance .
Channel Descriptian Ibnction Frecuency Surveillance Method
- 1. Primary CEA Positian a. Check S a. Wri<aan of output data with secondary CEAPIS.
- Indication System l b. Test M b. Test of power depeiabd. insertim limits, devia-tian, and sequence manitoring sptems. ;
e c. Olibrate R c. HIysimlly w<=sred CEIM position used to verify
- spten accuracy. Calibrate CEA position inter- t i locks. !
{ 2. Secondary CEA Position a. Check S a. Ctmparison of output data with primary CEAPIS. !
Indication Sptem t
i
- b. Test M b. Test of power dependent insertim limit, devia- ,
tion, out-of-sequence, and overlap mmitoring {
syst e .
i Y c. Calibrate R c. Calibrate secondary CEA position indication
- systen and CEA interlock alarns.
- 3. Area, Pro ss, and a. Check D a. Normal readings observed and internal test I i > Post-Aondent signals used to verify instrument opstim.
Radiation Monitors [
R Decept Effluent b. Test M b. Detector exposed to remote operated radiation. 1 I Radiation Manitors(l) check sour or test signal. i
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$ r
- c. 61ihrate R c. PM-063L, M, and H and PM-064 - One time factory y calibratian is acceptable provided linearity -'
4 -
solid sources are used to check the integrity of i
- the detectors. PM-091A and B - In situ calibra-tion by electrmic signal substitution is ao pt-l able for all range h above 10 R/hr. In l
' situ calibration for at least one decade below g 10 R/hr shall be by means of calibrated radiation 3 source. All other monitors - Exposure to known *
$ . radiation source. ,
(1) The surveillance rvvstirvments for effluent radiation monitors are described under Specification 3.12.1.
Effluent radiation rxnitors are: RM-041, RM-042, RM-043, RM-054A, RM-054B, RMM)SS, RM-055A, RM-057, 'l ,
FM-060, FM-061, and RM-062. RM-050 and RM-051 are considered effluent radiation monitors when ronitoring I the votilatim Auxiliary Buildirrs Exhaust s_Stac_k.. l l t
- - . ~ . .
- 3.0 SURVEILLANCE REQUIREMENTS
'3.12 Radioloaical Waste Samplina and Monitorina (Continued) 3.12.1 Liauid and Gaseous Effluents (Continued)
(iii) Quarterly channel functional tests.
(iv) Channel calibration at refueling frequency.
]
- e. The steam generator blowdown effluent flow rate will be calibrated at refueling frequency and visually determined operable daily,
- f. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred.
Analytical results shall be submitted to the Commission in accordance with Section 5.9.4.a of these specifications.
(2) Gaseous Effluents
] a. Radioactive gaseous waste sampling and activity analyses shall be performed in accordance with Table 3-12. The results of these analyses shall be used with the calculational methods in the ODCM to assure that the concentration of radioactive materials in unrestricted areas is limited to the values in Specification 2.9.1(2)a.
- b. (i) A-vent 44ation-staek-Fadit4en An Auxiliary Buildina Exhaust Stack monitor shall have a source check prior to any release of radioactive materials from a gas decay tank or the containment. A monthly source check will be performed during refueling outages if a purge or gas decay tank release is not done during that month.
(ii) Eaek-vent 44at4en-stack The Auxiliary Buildina Exhaust Stack caseous, particulate, and iodine monitors and the Laboratory and Radioactive Waste Processina Buildina Exhaust Stack caseous, particulate.._and iodine monitors shall have a quarterly channel functional test.
(iii) Eaeh-vent 44atien-staek The Auxiliary Buildina Exhaust Stack caseous, particulate, and iodine monitors and the Lahoratory_and Radioactive Waste Processina Buildina Exhaust Stack caseous, particulate, and iodine monitors shall be calibrated at refueling frequency.
(iv) The vent 44atien Auxiliary Buildina Exhaust and the Laboratory and Radioactive Waste Processina Buildina Exhaust stack flow rate 3, will be calibrated and f unctionally tested at refueling frequency. The Auxiliary Buildina Exhaust and the Laboratory and Radioactive Waste Processina Buildina Exhaust stack radiation monitor 1_ flow 3-70 Amendment No. 86,122
4
. rates will be calibrated and functionally tested at refueling frequency. Beth The stack flow rates and radiation monitor flow rates will be determined operable by visual inspectio: daily.
(v) The Laboratory and Radioactive Waste Processina Buildina Exhaust Stack qaseous Darticulate, and iodine activity monitors shall have a daily channel check and a monthly source check,
- c. The condenser air ejector monitor shall have a:
(i) Daily channel check.
(ii) Monthly source check.
3-70a
TABLE 3-12 RADIOACTIVE GASE0US WASTE SAMPLING AND ANALYSIS Lower Limit of Sampling and Type of Activity Detection (LLD)
Gaseous Source Analysis Freauency Analysis (4) (uCi/ml)
A. Gas Decay Prior PrincipalGamma(5) 1.0E-04(1)
Tank Releases to each release Emitters B. Containment Prior PrincipalGamma(5) 1.0E-04(1)
Purge Releases to each release Emitters or Containment Prior Pressure Relief to each release H-3 1.0 E-06 Line Releases Monthlv (3) Tritium (H-3) 1.0 E-06 C. Condenser Air Monthly PrincipalGamma(5)
Eiector Releases Emitters 1.0 E-04(1)
D. Continuous (2)
Auxiliarv Weekly)(Charcoal Buildina and Sample I-131 1.0 E-12 Mboratory &
Radioactive Waste Weekly (2) PrincipalGamma(5) 1.0 E-ll Processina (Particulates) Emitters I-131 Fuildina Exhaust & Particulates Stack Releases with half-lives areater than 8 days Monthly Composite Grossa 1.0 E-ll Quarterly Composite Sr-89, Sr-90 1.0 E-ll (Particulates)
NOTES:
(1) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides at levels near their sensitivity limits when
-other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of.such radionuclides using observed ratios with those radionuclides which are measurable.
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3-74 Amendment No.86
2.0 LIMITING CONDITIONS FOR OPERATIONS
. 2.9 Radioactive Effluents (Continued) i 2.9.1 Liouid and Gaseous Effluents (Continued) one or more of the equipment or subsystem (s) identified in the ODCM, a special report, pursuant to Specification 5.9.3, shall be prepared and submitted to the Commission within 30 days. This report shall include the following information:
(i) Identification of equipment or subsystem (s) not operable and reason for inoperability.
(ii) Action (s) taken to restore the inoperable equipment to operable status.
(iii) Summary description of action (s) taken to prevent a recurrence,
- d. The hydrogen and oxygen monitors shall be monitoring the in-service gas decay tank during the transfer of waste gases to the gas decay tank and the concentration of hydrogen and oxygen shall be limited to below flammability concentrations. Whenever the monitors are inoperable, transfer of waste gases to a gas decay tank may continue provided grab samples are taken from the gas decay tank and (1)every8hoursduringdegassingoperations, I analy(zed:
and 2) daily during other operations,
- e. The Auxiliary Building Exhaust Stack gaseous, particulate, and iodine activity monitors may be inoperable provided that
- 1) releases from a gas decay tank, containment pressure relief line, and the containment purge line are secured, and
- 2) whenever the Auxiliary Building Exhaust Stack gas or particulate activity monitor is inoperable, appropriate grab samples will be taken and analyzed once per eight (8) hours.
- f. During power operation, the condenser air ejector discharge l shall be monitored for gross radioactivity. If this monitor is inoperable, grab samples shall be taken and analyzed daily for principal gamma emitters.
- g. During release of gaseous radioactive wastes from the I gaseous waste discharge header or during containment venting to the Auxiliary Building Exhaust Stack, the following l conditions shall be met:
(i) The gas, iodine, and particulate monitors shall be monitoring the Auxiliary Building Exhaust Stack. l (ii) At least one exhaust fan shall be in operation.
(iii) The effluent control radiation monitors shall be set in accordance with the ODCM to alarm and automatically terminate the releases prior to exceeding the limits specified in 2.9.1(2)a(i) above.
(iv) The activity shall be monitored and recorded. The flow rate shall be monitored and recorded, or 1 determined by calculation.
2-44 Amendment No. 12//86
2.0 LIMITING CONDIT:0NS FOR OPERATIONS l 2.9 Red oactive Eff M na (Continued) i 2.9.1 Liouid ant! Gaseous Iffluents (Continued) l (v) During the release of gaseous wastes from the contM n-ment purge line, a containment gas monitor and a particulate monitor shall monitor the cont
- ment, in 1 additiontoconformingwith(i)through(a, above,
- h. During releases from the Laboratory and Radioactive Waste Processing Building Exhaust Stack, the following conditions shall be mets (i) The Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack gas, iodine, and particulate monitors shall be monitoring the LRWPB Exhaust Stack. The effluent control radiation monitors shall be set in accordance with the ODCM to alarm 2.9.1(priortoexceedingthelimitsspecifiedin 2)a(i)above. The gas activity monitor may be inoperable provided that appropriato grab samples be taken and analyzed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The ) articulate and iodine activity monitors may be inopera)1e provided that samples are continuously collected as required in Table 3-12.
(ii) The effluent flow rate shall be monitored and recorded, or determined by calculation.
.B.U_!1 Releases of radioactivity in liquid wastes within the design object!n levels provide reasonable assurance that the resulting annual exposm from liquid effluents will not exceed the limits specified in Appendix
! to 10 CFR Part 50. These specifications provide reasonable assurance that the resulting exposure will n xceed 3 m" m to total body or 10 mrem to any organ. At the same t % 'hese specifications
)ermit the flexibility of operatica, com)atn " ath considerations of acalth and safety, to assure that the pu)lic n Jrovided a dependable source of power under unusual o>erating conditions which may temporarily result in releases ligher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience, calculation procedures based on models and data set forth in Regulatory GuNe 1.109, and the evaluation of Fort Calhoun facility in accordance with Appendix 1 of 10 CFR Part 50 dose design objectives. The design sbjectives take into accou.J a combination of variables including fuel failures, primar system leakage primary ~to-secondarysysiemleakageandteperformanceofvarious radioactive waste treatment systems.
Specification 2.9.1(1)a requires the licensee to limit the
- concentration of radioactive materials in liquid effluents released from the site to levels specified in 10 CFR Part 20, Appendix B, for unrestricted areas. . This specification provides assurance that no member of the general public will be exposed at any time to liquid 2-45 Amendment No. 12,86 i
2.0 t IMI1ING COND1T1 ONS FOR OPfRAT10NS 2.9 Radio.ar1.ive [f f luents (Continued) 2.9.1 liouidandGaseousEffluents(Continued) 3p n (Continued) containing radioactive materials in excess of limits considered permissible under the Commission's Regulations.
Specification 2.9.l(1)b establishes the frequency of dose calculations in accordance with the ODCM. This specification also establishes the reporting requirerwnts in accordance with Section IV.A of Appendix 1 to 10 CfR Part 50, in addition to the requirements of Section 5.9 of these Technical Specifications.
Specification 2.9.'(1)c requires the operation of the equipment or subsystem (s) of thc radioactive liquid waste system, as identified in the ODCM, to reduce the release of radioactive materials in liquid effluents to as low as reasonably achievable, consistent with the requirements of 10 CFR Part 50.36a, and General Design Criterion 60 of Ap)endix A to 10 CFR Part 50. Nonaal use of the equipment or suasystem(s) in the radioactive liquid waste system provides reasonable assurance that the quantity released will not exceed the design objectives.
2-45a
2.0 llM111NG CONDITIONS FOR OPERATIONS 2.9 Radioactive f f f luents (Continued) 2.9.1 Liouid and Gaseous Effluents (Continued)
Basis (Continued) requirements in accordance with Section IV.A of Appendix 1 to 10 CFR Part 50, in addition to the requirements of Section 5.9 of these Technical Specifications.
Specification 2.9.1(2)c requires the operation of equipment or subsystem (s) of the radioactive gaseous waste system, as identified in the ODCM, to reduce the release of radioactive materials in gaseous effluents to as low as reasonably achievable, consistent with the requirements of 10 CFR Part 50.36a, and Gantral Design Criterion 60 of Ap>endix A to 10 CFR Part 50. Normal use of the equipment or su) system (s) in the radioactive gaseous waste system provides reasonable assurance that the quantity released will not exceed the design objectives.
Specification 2.9.1(2)d ensures that the concentration of potentially explosive gas mixtures entrained in the gas decay tank (s) will be main-tained below the flammability limits of hydrogen and oxygen.
Maintaining the concentration of hydrogen and oxygen below their flammability limits with a measurement program provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
Specification 2.9.1(2)eprovidesassurancethatreleasesfromgas deca / tank, Auxiliary Building Exhaust Stack, containment pressure relief line, and containment purge line are not made whenever the stack gas, particulate and iodine monitors are inoperable.
Specification 2.9.1(2)f assures that the gross radioactivity, during l power operation, is monitored from the condenser air ejector discharge.
Specification 2.9.1(2)g requires operation of seitable equipment to l dilute, control, and monitor in order to provide assurance that radioactive materials released in the gaseous effluents are properly controlled and monitored in accordance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A.
Specification 2.9.1(2)h p-ovides for releases from the Laboratory and Radioactive Waste Proceuing Building (LRWPB) whenever the LRWPB Exhaust Stack gas, particulate or iodine activity monitors are inoperable.
2-47 Amendment No.86
P H E 3-3 ~
MBTIMQi EFSQUI2N FOR Cli! IFS, C74TWATIGG RND 'IESTEU OF MIWINTEOUS HGIHME2TIATIGT MO CDfTIPOIS Surveillance Omnnel D*Mdan Function Frecrx:r,r Surwillance Me*Jn1
- 1. Prinary CEA Positicn a. Check S a. C%rperison of ou$t data with secor23ary CEEIS.
Indicaticn Sys*wm
- b. Test M b. Test of power depeMent inserticn lirits, devia-ticn, ani segmnce ricnitoriry systers.
- c. mlihrate R c. R ysimlly reasurled CEM gsiticn useri to verify system acx:uracy. Calibrate GA positicn in*mr-locks.
- 2. Secorx3ary CEA Rsition a. Check S a. th9mrian of cLW data with primary CEAPIS.
Indication Sys+ws
- b. Test M b. Test of power dq;ta AmL inserticn limit, devia-tion, out-of-segaence, and creerlap ronitoriry sys+ m .
Y c. mlibrate R c. Calibrate secondary GA positicn inlicaticn C system aM CEA in*arlock alan:s.
- 3. Area, Process, aM a. Check D a. Ibrmal raviirgs ciserval and internal test g Post-Accident signals used. to verify instnmnt operaticn.
j Radiation Monitors
- E Except Effluent b. Test M b. Detector expcsed to rmote cperated radiaticn
) 3 Radiation Monitors (l) chei scurce or test signal.
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- c. Calibrate R c. Rf-063L, M, ani H ani 24-064 - One tire factory
[
calibraticn is acceptable prurided linearity solid scurces are used to check the in+agrity of
% the detectors. Rf-091A ani B - In situ calibra-ticn by electratic signal substituticn is accept-5
' able for all rarge W- abcve 10 F/hr. In situ calibraticn for at least one decade below
[ 10 R/hr shall be by reans of calibrated radiaticn source. All other ronitcrs - Exposure to kncun 3 radiaticn source.
(1) 'Ihe surveillan regaircuits for effluent radiation nonitors are described t.nler Specification 3.12.1.
Effluent radiaticn raonitors are: R4-041, R4-042,24-043, H4-05tA, R4-0548,21-055, R1-055A,24-057, [
R4-OCO, R4-061, and M4-062. Rf-050 ani R4-051 are considerei effluent radiaticn ronitcrs shen nonitoring the Auxiliary Buildirq Exhaust Stack. l
3.0 SURVEll. LANCE RE0VIREMENTS 3.12fLa.dioloaicalWasteSamplinaandMonitorina(Continued) 3.12.1 t iauid and Gaseous Effluents (Continued)
(iii) Quarterly channel functional tests.
(iv) Channel calibration at refueling frequency.
- e. The steam generator blowdown effluent flow rate will be calibrated at refueling frequency and visually determined operable daily,
- f. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred.
Analytical results shall be submitted to the Commission in accordance with Section 5.9.4.a of these specifications.
(2) Gaseous Effluents
- a. Radioactive gaseous waste sampling and activity analyses shall be performed in accordance with Table 3-12. The results of these analyses shall be used with the calculational methods in the GDCM to assure that the concentration of radioactive materials in unrestricted areas islimitedtothevaluesinSpecification2.9.1(2)a.
- b. (i) An Auxiliary Building Exhaust Stack monitor shall have l a source check prior to any release of radioactive materials from a gas decay tank or the containment. A monthly source check will be performed during refueling outages if a purge or gas decay tan'K release is not done curing that month.
(ii) The Auxiliary Building Exhaust Stack gaseous, particulate, and iodine monitors and the Laboratory and Radioactive Waste Processing Building Exhaust Stack gaseous, particulate, and iodine monitors shall have a quarterly channel functional test.
(iii) The Auxiliary Building Exhaust Stack gaseous, particulate, and iodine monitors and the Laboratory and Radioactive Waste Processing Building Exhaust Stack gaseous, particulate, and iodine monitors shall be calibrated at refueling frequency.
(iv) The t,uxiliary Building Exhaust and the Laboratory and Radioactive Waste Processing Building Exhaust stack flow rates will be calibrated and functionally tested at refueling frequency. The Auxiliary Building Exhaust and the Laboratory and Radioactive Waste Processing Building Exhaust stack radiation monitors flow 3-70 Amendment No.86,122
I rates will be calibrated and functionally tested at refueling frequency. The stcck flow rates and radiation nonitor flow rates will be determined operable by visual inspectinn daily.
(v) The Laboratory and Radioactive Waste Processing Building Exhaust Stack gaseous, particulate, and iodine activity monitors shall have a daily channel check and a monthly source check.
- c. The condenser air ejector monitor shall have at (i) Daily channel check.
(ii) Monthly source check.
I 3-70a Amendment No.86//122
TABLE 3-12 BJAD.LOACTIVE GASEOUS WASTE SAMPLING AND ANALYS!$
, Lower Limit of Sampling and Type of Activity Detection (LLD) i
$aseous Source Analysis Freouency Analysis (4) (uCi/ml) l A. Gas Decay Prior PrincipalGamma(6) 1.0E-04(1)
Tank Releases to each release Emitters B. Containment Prior PrincipalGamma(5) 1.0E-04(1)
Purge Releases to each release Emitters or Containment Prior Pressure Relief to each release H-3 1.0 E-06 line Releases Monthly (3) Tritium (H-3) 1.0 E-06 C. Condenser Air Monthly PrincipalGammc(5)
Eiector Releases Emitters 1.0 E 04(1)
D. Continuous (2)
Auxiliary Building and Weekly)(Charcoal Samole 1-1 31 1.0 E-12 Laboratory &
Radioactive Waste Weekly (2) PrincipalGamma(5) 1.0 E-11 Processing (Particulates) Emitters 1-131 Building Exhaust & Particulates Stack Releases with half-lives areater than 8 days Monthly Composite Gross a 1.0 E-Il Quarterly Composite Sr-89, Sr-90 1.0 E-Il
, (Particulates)
NOTES:
(1) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides which are measurable.
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I 3-74 Amendment No.S6
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DISCUSSION, JUSTIFICATION, AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTiflCATION The Omaha Public Power District proposes to revise fort Calhoun Station Jnit No. 1 Technical Specifications 2.9.1, 3.12.1 and Tables 3-3 and 3-12 (oncerning liquid and gaseous effluents to reflect the addition of the new fadioactive Waste Processing Building, dquiL3nd annus ef fluentLJections 2.9.1 and_L12.1. TableLJ-3. and h2 The reason for changes to pages 2 44 through 2 47, 3-13, 3-70, and 3-74 is to include provisions for the new Laboratory and Radioactive Waste Processing Building exhaust stack gaseous, particulate and iodine activity monitors. To differentiate the new exhaust stack from the existing stack, the title of the existing stack was changed to "The Auxiliary Building f.xhaust Stack." The design of the new building calls for a dedicated ventilation discharge. This discharge point will be monitored and will be used for exhaust of the laboratory section of the new chemical and radiation protection locker facility addition as well.
Changes to Table 3 3 adds the new gaseous, particulate, and iodine activity monitors (RM 041, 042, 043) ts existing plant effluent monitors. Changes to Sections 2.9.1 and 3.12.1 " Liquid and Gaseous Effluents" are made to include the new monitors with the existing stack monitors for grab sample provisions, functional test, calibration, and flow rate calibration and testing. The grab sample provisions requirt daily samples be taken and analyzed. This is consistent with the present specification concerning condenser air ejector discharge. Changes to Table 312 are made to include the new discharge point for radioactive gaseous waste sampling and analysis.
The new release peint is not expected to significantly increase the doses calculated for the routine gaseous effluent release. To ensure that an accidental release from the building is within the allowable range, a calculation was performed to determine the dose at the exclusion area boundary cue to iodine releases from the liquid Radwaste processing equipment. Radioactive sources used in the calculation were 1-131, 1 132, 1-133, 1 134 and 1-135. Concentration values used were from Updated Safety Analysis Report Section 11
" Radioactive Waste and Radiation Protection and Monitoring," Table 11.1 13 " fission and Corrosion Product Activity in Waste Treatment System at 70'f" for "As Received" nuclide. The calculation assumed a 70 gpm flow rate from the waste treatment system to the filtration and ion-exchange equipment in the Radioactive Waste Processing Building.
Based on the above assumptions, the maximum equilibrium radiciodine l
DISCUSSION, JUSTiflCATION, AND NO SIGNiflCAN1 ilAZARDS CONSIDERATIONS DISCUSSION AND JUSTiflCATION (CONTINUED) inventory was calculated. In the event of an ion-exchange equipment rupture it was assumed that 10% of the iodine collected on the resin bed will be released to the water, it was further conservatively assumed that 10% of the iodine in the water becomes airborne. These assumptions are in accordance with Standard Review Plan criteria contained in Section 15.6.5 Appendix B.
The results for two (2) hours thyroid dose calculations at the site boundary was determined as 3.8 rem or approximately 1% of the 10 CFR 100 limits. Thus these results remain within a small fraction of the bounds of 10 CFR 100.
Administrative Chances Specifications 2.9 l(2)e(i), 2.9.l(2)e(ii), and 2.9.1(2)f are being renumbered to 2.9.l(2)e, 2.9.l(2)f and 2.9.l(2)g respectively, in the present specifications, Specification 2.9.l(2)e(i) concerns monitoring releases from the gas decay tank or containment while Specification 2.9.l(2)e(ii) concerns monitoring the condenser air ejector discharge. This renumbaring provides separate specifications for monitoring releases from the different sources. The bases to this specification was revised to reflect this renumbering.
The word " analysed" in specification 2.9.l(2)d is misspelled and is being corrected to " analyzed."
I ,
BASIS FOR NO SIGNIflCANT HAZARDS CONSIDERATION:
The proposed change does not involve a significant hazards consideration because operation of the fort Calhoun Station in accordance with the proposed
. change would nots (1) Involve a significant increase in the probability or consequences of
, an accident previously evaluated.
Updated Safety Analysis Report Section 14.20 " Waste Liquid Incident" provides evaluation for a) . Release of liquid waste from components in the radwaste disposal system.
b) Release of liquid waste from one monitor tank, or one hotel waste tank to the circulating water discharge tunnel.
The pror: sed Radwaste Processing Building includes floor uains in
- with the possibility of-pipe break / leakage. Pipes liquid radweste will enter the new building in a coated
.onci ete a spe chase. The pipe chase extends to the processing comp:rtosnt which is seismically designed and includes floor drains:
and a lined sump. The entire floor of the compartment is covered with a steel l her for' additional protection. The proposed liquid processingsystem(filtrationand-ionexchanger)willbelocatedin this compartment. Therefore, in the event of a liquid radwaste pipe leak / break,.the contaminated liquid will be collected in the sumps and pumped back to the existing radwaste disposal system in the Auxiliary-Building. Also, in the event of a liquid )rocessing system (ion exchangers) rupture, liquid radwaste will )e contained in the seismic compartment.
Proposed revisions'to the technical. specifications include the addition of a new ventilation discharge from the Radioactive Waste- ,
Processing Building HVAC combined with the laboratory area of the chemical and radiation protection-locker facility.. The ventilation stackwillbeequippedwithathreechannel(Particulate, lodine,and NobleGas)effluentmonitorwithindicationinthemaincontrolroom.'
The releases from the new. discharge are anticipated to be insignificant compared with releases'from the existing plant discharge stack.
-Therefore, it can be concluded that the proposed amendment to the technical specifications does'not involve a-significant increase-in the probability or consequences of an accident previously evaluated.
L
o i
BASIS FOR MO SIGNiflCANT HAZARDS CONSIDERATION: (CONTINUED)
(2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
As described above, a liquid radwaste incident is evaluated under USAR Section 14.20. However, to determine off-site doses due to ion exchange system rupture in the Radioactive Waste Processing Building a calculation was performed. The results indicated 3.8 rem thyroid dose from iodines at the exclusion area boundary. This dose is approximately 1% of the 10 CFR 100 limit. The calculation used "As Received" iodine inventory from USAR Table 11.1-13. It was assumed a 70 gpm flow rate from the waste treatment system to the ion-exchange equipment located in the building. In the event of the ion-exchange equipment rupture it was assumed that 10% of the iodine collected on the resin bed will be released to the water, it was further conservatively assumed that 10% of the iodine in the water becomes airborne. Liquid radwaste processing and solidification / dewatering will be conducted in a seismically designed compartment and potential spills will be contained and routed back to the radwaste system.
Ventilation discharge will be monitored for any airborne releases.
The radioactive sources present in the Radioactive Waste Processing Building are identical to those currently in the Auxiliary Building.
Therefore, the possibility of a new or different kind of accident other than any evaluated previously in the Updated Safety Analysis Report would not be created.
(3) Involve a significant reduction in a margin of safety.
Due to close proximity of the Radioac'.ive Waste Processing Building and the Auxiliary Building (a 6" gap separates the two structures) the entire frame of the building was seismically designed. Analysis has indicated no interaction between the two buildings will occur in a design basis earthquake.
The liquid redwaste system extended to the Radioactive Waste Processing Building is an extension of the existing system and is non-safety related as defined in Omaha Public Power District's Critical Quality Equipment List.
Therefore, the proposed changes to Technical Specification will not reduce the margin of safety.
The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards consideration. Example (vi) relates to a change which either may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan.
The proposed change described above is similar to Exampla (vi) in that the addition of the Radioactive Waste Processing Building has been analyzed utilizing the Standard Review Plan criteria and the results are well within the acceptance criteria of both the Standard Review Plan and the fort Calhoun Station Unit No. 1 Updated Safety Analysis Report.
Thereiore based on the above considerations, OPPD does not believe that this proposed amendment involves a significant hazards consideration as defined by 10 CfF 50.92 c.nd the propm ed changes will not result in a condition which significantly alters the linpact of the Station on the environment. As discussed above, there is no significant change in the types or significant increase i the amounts of any effluents that may be released off-site, and there is no significant increase in individual or cumulative occupational radiation exposure. Thus, the pro)osed change meets the eligibility criteria for categorical exclusion set fort, in 10 CFR 51.22(c)(9) and pursuant to 10 CFR 51.22(b) no environmental assessment need by prepared.
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