ML19261C592
| ML19261C592 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/15/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19261C585 | List: |
| References | |
| NUDOCS 7903230313 | |
| Download: ML19261C592 (60) | |
Text
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UNITED STATES
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S
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'b NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20556 CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. DPR-61 The Nuclear Regulatory Commission (the Commission) has found that:
1, The application by Connecticut Yankee Atomic Power Company A.
(the licensee) dated June 4,1976, as supplemented by letters dated May 6, 1977 and November 28, 1977, and applications dated 16, 1978 and August 15, 1978, comply with tne standards February and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the applications, 8.
the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized C.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) tha+, such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the D.
common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR E.
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
79032303(3
. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license 2.
amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:
(2). Technical Specifications The Tei.nnical Specifications contained in Appendices A and B, as revised through Amendment No. 32, are hereby incorporated The licensee shall operate the facility in in the license.
accordance with the Technical Specifications.
This license amendment is effective as of the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION l
'hwn~
k]2auwi_
Dennis L. Ziemann, hief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 15,1979
ATTACHMENT TO LI_CjNSE AMENDMEllT N0. 32 FACILITY OPERA]ING LI_ CENSE N0. DPR-61 opCKET N0. 50-213 by deleting the following Revise the Appendix B Technical Specificatiore:The revised pages contain the pages and inserting the enclosed pages. captioned anendment num Overleaf pages (*) are included for document completeness.
change.
INSERT REMJVE i**
i ii **
11 iv**
iv 1.2 **
1.2 2.1-1 **
2.1-1 2.1 -2 *
- 2.1-2 2.1-3 **
2.1-3 2.1-6 **
2.1-6 2.1 ' **
2.1-7 2.2-1 2.2-1 **
2.3-1 2.3-1 **
2.3-2 **
2.3-2 2.3-3 2.3-3 2.3-3A 2.3-4 2.3-4 2.3-5 2.3-5 2.4-1 2.4-1 **
2.4-2 **
2.4-2 2.4-7 **
2.4-7 2.4-8 **
2.4-8 2.4-10**
2.4-10 2.4-12**
2.4-12 2.4-13**
2.4-13 2.4-14**
2.4-14 2.4-15**
2.4-15 2.4-17**
2.4-17 2.4-18**
2.4 18
. REMOVE INSERT 3.1-1 3.1-1 3.1-2 3.1-2 3.1-3 3.1-3 3.1-4 3.1 -4 *
- 3.1-1 3.1-1 **
3.2-2 3.2-2 **
3.2-3 3.2-3 **
3.2-4
- 3. 2-4 *
- 3.2-6 3.2-6 **
3.2-7 3.2-7 **
3.2-8 3.2-8 **
3.2-9 3.2-9 **
3.2-10 3.2-10**
4.1-1 4.1-1 4.1-2 4.2-1 4.2-1 4.3-1 4.3-1 4.3-2 4.3-3 5.1-1 5.1-1 **
5.1-2 5.1-2 5.1-3 5.1-3 5.2-2 5.2-2 5.3-1 5.3-1 5.5-1 5.5-1 5.6-1 5.6-1 5.6-la 5.6-2 5.6-2 **
5.6-3 5.6-3 **
5.6-4 5.6-4 5.6-5 5.6-5 5.7-1 5.7-1 **
- iii, 1.1, 2.1-4',2 X F,-'2'.4~-~9, 2.4-11, 2.4-16, 3.2-5, 4.1-2, 5.2-1
~
- These pages contain editorial and clarifying changes only.
TADLE OF CONTENTS Page 1.1 1.0 Definitions and Abbrevictions 1.1 1.1 Definitions 1.2 1.2 Abbreviations 2.1-1 2.0 Limitine Conditions for Oncration 2.1-1 2.1 Ther=al 2.1.1 Max 1=u= AT Across the Condenser and Maxi =u=
2.1-1 Discharge Temperature 2.1-6' 2.1.2 Itate of Change of Discharge Te=perature 2.1-7 2.1.3 Deicing Operations 2.2-1 2.2 Hydraulic 2.2.1 Intake Velocity 2.2-1 2.3-1 2.3 Chc=ical 2.3.1 Biocidcs 2, g_>1 2-2.3.2 pH
-2.3-4 2.3.3 Diosolved Oxygen 2.4 Radioactive Effluents 2.4-1 2.4.1 Specifications for Liquid Waste Effluents 2.4-2 2.4.2 Specifications for Liquid Waste Sc=pling and 1:enitorinS 2.4-2 2.4.3 Specif1gations for Caseous Waste Effluents 2.4-5 2.4.4 Specifications for Gaseous Waste Sa=pli=g and Monitoring 2,4 8 2.4.5 Specifications for Solid Waste Sa=pling and Disposal 2.4-12 3.0 Environmental Surveillance 3.1-1 3.1 Nonradiological Surycillance 3,1_1 3.1.1 Fich Impinge cnt 3,1_1 3.1.2 Meccorological Monitoring 3,1-3 3.2 Radiological Environ =cntal MonitorinS 3.2-1 i
knendment ta. 32
i TABLE OF CCC ESTS (continued)
Paqc 4.1-1
_Special Surveillance, Research or Studv Activitics 4.0
- 1~1 h.1 Shad Monitorinc ProcrN3 5.1-1 5.0 Adminintrative Centr:1s 5.1-1 5.1 Respcasibility 5.1-1 5.1.1 Corporate officers 5.1-1 5.1.2 Plant Superintendent 5.1.3 Environ = ental Progra:s Branch 5.1-1 5.1.4 Technical Personnel 5.1-1
$ 1.5 Environ = ental Review Board 5.1-1
$,1.6 Plant Operations Review Cc=sittee 5.1-3 5.2-1
$.1 Organization 5.3-1
$.3 Review and Audit
$.3.1 Environ =cntal Review Board 5.3-1
$.3.2 Environ =cntal Technical specifications 5.3-1
$.4 Acticn to be Taken if a Limiting conditien for 5.4-1 Operation is Exceeded
$.4.1 Recedial Action 5.4-1
$.4.2 Investigation 5.4-1 5.4-1 5.4.3 Report 5.S-1 5.3 Procedures 5.5.1 Written Procedures 5.5-1
$.5.2 standard operating Procedures 5.5-1
$.5.3 Review 5,5-1 5.6-1
$.6 Plant Reporting Require =ents 5.6.1 Routine Reports 5.6-1 5.6.2 Sonroutine Reports 3.6-2 S.6-;
5.6.3 Chances 5.7-1
$. 7 Records Retention 5.8-1
$.8 Special Require =ents 11 k endnent.io. 32
LIST OF TABLES Pace Number Title Table Nu=ber Radioactive Liquid Sanpling 2.4-13 2.4-1 and Analysis Radioactive Caseous Waste 2.4-15 2.4-2 Sampling and Analysis 2.4-17 PWR Liquid Waste System 2.4-3 2.4-18 PWR Gaseous Wasts System 2.4-4 Average Energy per Disinte-2,4-19 2.4-5 gration Fish Impingement Report 3.1-2 3.1-1 Levcis Connecticut Yankee Radiological 3.2-7 3.2-1 Environmental Menitoring Progra A"~ er 9ent t;o. 32 iv
HPC is the maximum permissible concentration of a rcdio-nuclide according to 10 CFR 20, Appendix B, Table II, in air (MPCa) or water CfPCw).
Normal Power Oneration is operation with the reactur critical and above 5 percent of rated power in ccnformance with the requirerents of the Safety Technical Specifications.
Non-Routine Operation is that which occurs when all the four condenser cooling water pumps are not used because of pump f a ilure, pump inspection and/or maintenance.
Phytoplankton refers to those planktonic plants (au to t rophn )
which are capable of photosynthesis and may be classified is primary producers.
Routine Operation occurs when all four condenser coeling water pumps are utiliced.
Standard Methods refers to those methods as specified in the Federal Register, Title 40, Part 136, Volume J3, Ne. 199, pages 28758 - 28760, October 16, 1973.
Total residual chlorine is chlorine present in water as free avail-able chlorine in the form of hypochlorous acid and/c; hypochlorite 4.on or as combined available chlorine such as monochloramine, dichloramine or trichloramine (nitrogen trichloride).
Unreviewed Envi ronment al Impact-A ch ange in plant dcsign, in plant operation, or in procedures related to these Environ-mental Technical Specifications shall constitute an unreviewed environmental impact if both:
1.
The change could result in an increase in the environmental effects of station operation, and 2.
The increased effect is significant enough such that it exceeds the effect previously reviewed and evaluated by the NRC for the particular system or type of operation involved.
Zooplankton refers to those planktonic elements which are not primary producers, most of which may be classified as herbivorous.
1.2 Abbreviat*ons CONVEX - Connecticut Valley Electric Exchange CYAPC - Connecticut fankee Atonic Power Cernans C' - Cennecticut.:.
ce T'
- '.levation
,h<-
can
..a 1cvel
- Nviren "t- '
cic.
xir d acilit-
_ M t i n.
ma 3n ;t-u;
~
s.1 - r ID - Inner Diameter MPC - Maximum Permissible Concentration N ',B - N u c l e a r Rev _
9eard W 3CO - W rhte n t. t i li tie-5ervice Cerpany PORC - Plant Onorat. na Revtcu Connittee
_.2 Anend ent No. 32
LIMITING C0!mITIONS_ FOP OPERATIO![
3 2.0 2.1 Thermal _
Maximum AT Across the Condenser and Maximun Discharge Te=cerature 2.1.1 Obj ec t ive_
releases ef heat The purpose of this specification is to assure thatd in a manner consistent w to the Connecticut River are acconplishe m
the well-being of the Connecticut River ecosyste.
Specifications h ll The maximum dif f erential te=perature across the condenser s a during routine not exceed 260F for a period greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.1.1.1 ration.
operation with all four circulating water pumps in ope ll not The maximum dif f erential temperature across the condenser sha during non-routine exceed 330F for a period greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.1.1.2 in operation.
operation with less than four circulating water pumps d d by not The limits specified in 2.1.1.1 and 2.1.1.2 may be excee e deicing systes more than 10 percent during cold weather when the-2.1.1.3 is in service.
h ll The taximum discharge te=perature of condenser coeling water s a exceed 1190F f or a period greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.1.1.4 not 1.4 2.1.1.1, 2.1.1.2, 2.1.1.3, or 2.1.
If the limits specified in d taken are exceeded, an investigation of the cause shall be un er 2.1.1.5 liance with and plant operations shall be codified to restore co:p the specifications.
Monitoring Specifications 2.1.1.1 The primary system f or ensuring co=pliance with specifications 2.1.1.6 through 2.1.1.4 is as f ollows:
nsor the intake water te=perature shall be ceasured by a seo (a) t rs positioned just at a depth below the influence of heated recirculating wa e (greater than or equal to 3 feet below Mean Low Water).
d by a sensor the oischarge water temperature shall be =easure (b) located in the discharge canal.
during nor=al power operation the outputs of these sensors (c) shall be recorded continucusly.
the AT cf these senscrs, i.e.
(d) the dif f erence in the cu ;utshcli be recorded durin; nor:21 pcwcr across the cendenst operation.
2.1-1 Amendnent No. 32
an alarm shall be actuated if the discharge water tenperature or the AT across the condenser exceeds the limits specified (e) in 2.1.1.1 through 2.1.1.4 The backup system for ensuring cc=pliance with Specifications 2.1.1.7 2.1.1.1 through 2.1.1.4 is as follows:
the intake water temperature shall be =casured by temperature sensors located in the piping to each condenser water box.
(a) the discharge water temperature shall be measured by a sen-sor located at the outlet of the cendenser water boxes.
(b)-
readings shall be taken during nor=al power operation these hourly either by the cceputer or =anually if the cenputer is (c) once a year the correlation factor between the readings of out of service.
the sensors in 2.1.1.6 (a) and 2.1.1.7 (a) shall be deter-(d) mined.
of the once a year the correlation f actor betweer. the output sensors in 2.1.1.6 (b) and the arithmetic =ean of the out-(e) puts of the sensors in 2.1.1.6 (b) shall be determined.
if the primary system specified in 2.1.1. 6 is inoperative during normal power operation, the dif f erence in the cor-(f)
(d) and (e), of rected readings as determined in 2.1.1.7shall be computed the sensors specified in 2.1.1.6 (a) hourly to determine the AT across the condensers.
Temporary malfunction of temperature monitoring systems shall not restrictive on plant operations providing one inlet and one 2.1.1.8 be outlet sensor system if functional.
The range of the sensors described in Specifications 2.1.1.6 and The total uncertainty (due to 2.1.1.9 0
C 2.1.1.7 shall be 30 F to 150 F.
11 F, 0
accuracy and instrument drif t) of the sensor syste=s shall be There shall be an annual Channel Calibration of the sensor syste=s.
2.1.1.10 There shall be a monthly Channel Functional Test of the sensor 2.1.1.11 systems.
Recorting Recuirenent_
in Section 5.5.2 a. (1) sna;1 be cade A prenpt report as described 2.1._._,
2.1.1.2, 2.~.1.3, 2.1.1.12 when liciting conditiens specifiel in or 2.1.1.4 are exceeded as a result of plant operations.
i 2.1 -2 Amendment flo. 32
Bases The Specification 2.1.1.1 covers the case of routine operation. about design AT across the condensers during routine operation at 600 MWe is 22.4*F.
During operation at about 600 MWe the actual AT across the condenser as documcated in the staticn's daily log books over the past 7 years always exceeded the design aT of 22.4*F.
The range of AT observed is from 23*F to 25.5*F.
The higher AT occurs during the cooler seasons because of deviations in the plant operating cycle tied to circulating water inlet te=perature.
The limit of 26*F specified in 2.1.1.1 is the upper limit of the range of temperatures that are normally observed during routine opera-tion at the peah station output. The extensive biological studies discussed below were done during the plant operation period from 1968 through 1972. They were of sufficient sampling frequency and intensity to essentially reflect the impacts, #f any, of the plant operation at peak load with a ST in the range of 23*F to 26*F.
four Specification 2.1.1.2 covers the case when only three of the condenser cooling water pumps are operatf ag.
For this conditicn the maximum observed AT across the condre.ser is 33*F.
Reduced pump capacity can occur tecause of a pi p failure, pucp maintenance or inspection.
could occur Specification 2.1.1.3 is based on a AT of 33 F that when the intake water temperature is 86 F (maximut observed).
Specification 2.1.1.4 indicates that corrective action shall be taken to restore operation that would be in compliance with the limiting conditions of operation.
The intake water te=perature shall be monitored by the sensor (Specification positioned just outside of the intake structure 2.1.1. 6 a). This sensor shall be at a depth below the influence of heated recirculating waters (about 3 feet below.Mean Low Water). This sensor will not be affected by the deicing opera-The sensors located in the piping to each condenser water tion.
box (Specification 2.1.1.7 a) will provide the redundancy require-This sensor will ment for monitoring the intake water temperature.
be affected by the heated recirculating water and the deicing op-readings shall be correlated as specified.
eration. These two sensor The temperature of the discharge water shall be monitored by the sensor in the discharge canal (Specifica tion 2.1.1. 5b).
The redundancy requirement for monitoring will be provided by the sensor system on the outlet of the condenser water boxes (Specifi-cation 2.1.'.6b).
The readings of these two senser systers shall be correlated as specified.
1: has bet well der ' a t rac t -
.. ten -
-t f
ere-system of the lower connecticut areer b; <re an; ;;r in g the tize 2.1-2 Anendment No. 32
2.1.2 Rate of Change of Discharge Temperature Objective The purpose is to limit thermal stress to the aquatic ecosyster.
Specification exceed The rate of change of discharge temperature shall not 2.1.2.1 8'F/ hour.
The limit specifico in 2.1.2.1 may be exceeded f or brief periods 2.1.2.2 as necessary to protect plant equipment and f or certain safeguard l
be limited or negated by plant operations.
operations which cannot These safetuard operations include automatic plant trips and ccc-pliance with safety related technical specifications.
the limit specified in If, as a result of changes in plant operations, 2.1.2.3 2.1.2.1 is exceeded, plant operations will be modified to restore com-pliance with the specification.
Monitoring Specification The output of the sensor located in the discharge canal and described in specification 2.1.1 shall be differentiated to provide the rate of 2.1.2.4 This information shall be recorded during change of temperature.
An alarm shall be actuated if the limit normal power operation.
specified is exceeded.
Temporary malfunction of this monitoring system shall not be 2.1.2.5 operations provided that inlet te=perature, restrictive on plant outlet temperature, oT and AT/hr are =anually logged on an hourly basis during power operation.
2.1.2.6 Reporting Require =ent as described in Section 5.6.2 a (1) shall be A prompt report made when the limits and requirements specified in Section 2.1.2.1 are exceeded as a result of plant operations, "except when Section 2.1.2.2 applies".
Bases Observation of the behavior of the fish residing in the discharge canal during plant shutdowns in the winter ti=e indicated that after of the ccnal an initial period of so=e lethargy the fish moved out No fish kills were observed. This is the ti=e and into the river.
of maxi =um expected stress on the ecesyste= and no effects have been observed.
Normal plant lead pickup and shed are i: cut 1.5 MVe"cin and 2.:
The stress on :ne ecos:s:e= durin: ::.e s ;
SNe/ min respect' rely.
normal rates of r.hanges of temperature (a =ax;;;m of 5;F/ hour) will be less than that described belev.
2.1-6 Arendrent ';0.
32
the rate of change of temperature across the l It is estimated that condenser can decrease by a f actor of 2 across the discharge cana
's probably i.e., the specified 80F/ hour across the condensethe point whe i
River.
This rate of change will further decrease with distance and within 40F/ hour at about 8000 feet, the maximum extent of the 40F isotherm, it could be as low as 0.50F/ hour.
2.1.3 Deicing operations Objective _
aquatic ecosystem.
To limit the thermal stress to the Specification 2.1.3.1 Refer to Section 2.1.1.3.
Monitoring Recuirement The sensor systens described in 2.1.1 will fulfill the monitoring 2.1.3.2 requirement.
Reporting Requirement Refer to Section 2.1.1.12.
2.1.3.3 Bases _
the intake in the event In order to provide a means of melting ice at of exceptionally cold weather, a 44-inch diameter pipe is provided to permit heated discharge water to be directed back to the intake baysThe several elevations.
by gravity flow at 10 percent of the condenser cooling water for this purpose is about flow.
plant records on the maximu= AT's across the condenser specified in 2.1.1 and using the sensor described in 2.1.1.7 are Present based on intake water ceasurements whose response was influenced by In view of the installation cf the sensor spec-the deicing operation.
river ified in 2.1.1.6, which will more closely measure the ambient be affected by the deicing operation, it is nec-temperature and not wculd permit a 13 per:ent essary to allow for a specification that 2.
increase in the thermal limits specified in 2.1.1.1 and 2.1.1.
Deicing operations can commence in early December and extend to as long as the middle of March.
Amendment fb. 32 2.1-7
2.2 pydraulic 1
Intake _ Velocity 2.2.1 There are no hydraulic limits on intake velocitics.
Amendment tio. 32 2.2-1
2.3 Chemical _
2.3.1 Biocides Objective releases The purpose of this specification is to assure chac plant lled manner of total residual chlorine are accomplished in a contro h River.
and will not add measureably to concentrations in t e
_ Specification i
The average increase in total reald:ial chlorine (free chlor ne in cooling water and mono, di-and trichloramine) concentration 2.3.1.1 hall discharged into the Connecticut River due to pl l
i tion.
exceed 120 minutes a day.
Chlorination times shall not in Sequential chlorination of condensers shall be undertak 2.3.1.2 order to limit as practicable.
specified in 2.3.1.1 above are exceeded If levels exceeding that hlorine corrective action shall consist of reducing the c 2.3.1.3 injection rate.
Monitoring Specification of the shall be ca.'lected in front Once a week a grab sample duritt the chlorination period 2.3.1.4 intake and in the discharge ca,'
idual chlorine and analyzed using standard methods for cotal res 16, 1973).
(Federal Register, Title 40, October
_Recorting Recuirement_
(1) shall be A prompt report as described in Section 5.6.2 a2.3.1.1 and 2.3.1.2 made when any of the limits described in 2.3.1.5 are exceeded.
Amend ent fio. 32 2.3-1
Bases Sodium hypochlorite is injected into the condenser cooling water to minimize bio-fouling of the condenser heat transfer surfaces.
/
The control of the chlorination rate and the sequential chlorination of condensers will assure that the total residual chlorine discharge specifications are not exceeded.
Operating experience has shown that a differential chlorine residual across the plant below 0.1 milligram per liter is realized at suitable dosages and chlorina-tion times that can average about 120 minutes a day when needed.
Further dilution of the periodically chlorinated water with unchlorinated cooling water and the ultimate dilution of the dis-charge concentration by the Connecticut River water (subsequent to discharge) will render residual chlorinc concentrations in the river due to plant discharge that are inacasurcable.
Monitoring total residual chlorine in the discharge water will assure that differential concentrations across the plant are 0.1 milligram per liter or less, and will be used to reestablish the proper dosage rate should this limiting value be exceeded.
The weekly grab sample will be adequate to determine if the injection rate setting or the biological uptake has changed.
Interest in ILniting the differential total residual chlorine concentrations to as low as possible evolve f rem economic as well as ecological considerations.
High differential total residual chlorine concentrations will indicate that more scaium hypochlorite is being applied than that initially determined as being required to retard fouling of condenser tubes.
As part of the studies done to determine the effects of plant operation on the Connecti t River ecosystem, observations were made on entrained.ish larvae and other zooplankton under various operational conditions in order to evaluate the con-tribution of various stress factors to entrainment mortality i.e., heat, mechanics and biocide treatment.
The results indicated that the effect of sodium hypochlorite was not measurable when compared to mechanical and heat stress (March, 1973).
Further, chlerination was not found to inhibit M:ctosynthetic production ir the dischar:;e canal 'rher stir nes of dali.
prinary pr i :ticn in 9 Cenac::: cut m_zer
.5 _c the uischarge canal 'ere m:de frcr die-reasurcrents f aissoited ox nen.
These and other studies demonstrate that 'trief exposure to total residual chlorine conccatrations below 0.1 g/l are not, in general, injurious to aquatic lift Amendment No. 32 2.3-2
2.3.2 311 Objective on the pH of the discharge The objective of this specification plant operaticas do not signi-cooling water is to assure that ficantly alter pH to a level incocpatible with aquatic lif e.
Specif ica t ion The pH of the condenser cooling water ef fluent as =easured in the discharge canal shall be between 6.8 and 8.5 er within 2.3.2.1 except during periods when natural super-1 pH Unit of the intake, saturation of the river water causes extre=e pH conditions.
If the limits specified in 2.3.2.1 are exceeded, action vil.
be taken to determine if the cause is due to plant cperations and 2.3.2.2 if so, corrective ceasures uhall be adopted to bring the pH back to specification.
Monitoring Specification I
the intake shall be positioned cutside cf the intake
- ischarge canal.
2.3.2.3 The sensor atAnother sensor shall be placed in the The sensor signals shall be continuously read out on analog record-structure.
An alarm shall be actuated if the limits specified are exceed-ers.
ed.
The senior calibration shall be checked using weekly grab samples.
2.3.2.4 If the sensor systc=s are inoperative, weekly grab sa:ples shall 2.3.2.5 be taken during periods of discharge.
2.3.2.6 Reporting Requirement report as described in Section 5.6.2. a (1) shall be made A prompt when a limiting condition as specified in Section 2.3.2.1 is ex-ceeded as a result of plant operation.
Bases Connecticut River Ecological Studies have indicated no significant coolinF wa:er pH.
Chem-dif ferences between intake and discharge ical discharges are neutralized prior to discha: ge into the canal.
Water Quality S:and:rds nain:ain that a
The State of Connecticut of 6.5 to S.5 will be sufficien: so as n.t :: affec: the well-being of Connecticut River bieta.
Sevecer
- s: riser data pH range ind ica t e that on many occasic s :he rivc: ;H is c;: side thi: ::nge.
For this reasen the al: 2rnate prevision :h2: :..e :h be
'e_d wi:hin to avo:d penali:ing the plant one unit of the intake is included for conditions Seyond its control.
'. endment f'o. 32 2.3-3
Recent observations at the plant have sho-T. that phytcple.nkten (blooms) are capable of causing river vater dicsolved c,xygen increases cencentrations in excess of saturation with resultant During these periods the passage of river vater thrcugh in pH.
the plant has reculted in large decreases in dissolve:i exygen and pH (greater than 2.0 pH unit).
2.3-3A anendment No. 32
2.3.3 Dissolved oxygen DELETED 2.3-4 Amendment l10. 32
DELETED I
i 2.3-5 Arendren: No. 32
2.4 RADIOACTIVE EFFLUENTS Limits and conditions for the centrolled release of Radioactive Liquids and Cases shall be as specified below.
Obiective:
To define the li=its and conditions for the controlled release of radioactive =aterials in liquid and gaseous effluents to the these releases are as lov as practicable.
envirocs to ensure that in radiation exposures in These releases should not result of natur:1 back-unrestricted areas greater than a few percent discharges of The concentration of effluent Eround exposures. radioactivities shall be within the 1Laits specified in Part 20.
To ensure that the releases of radioactive =aterial abov ground to unrestricted areas be as icv as practicable as defined in Appendix I to 10 Cra Part 50, the folleving design cbjectives apply:
For liquid vastes:
The annual dose above background to the total body or any organ of an individual frem all reactors at a site should a.
not exceed 5 mrem in an unrestricted area.
The annual total quantity of radioactive caterials in liquid vaste, excluding tritium and dissolved gases, dis-b.
charged should not exceed 5 C1.
For gaseous vastes:
The annual total quantity of noble gases above background in an air dose due
'c.
discharged fro = the site should result to gn==a radiation of less than 10 = rad, and an air doce any loca-due to beta radiation of less than 20 crad, at tion near ground level which could be occupied by indi-viduals at or bey ad the boundary of the site.
The annual total quantity of all radioicdines and radio-active =aterial in particulate for:s above background d.
in an annual dose to any crgan of an should not result all path ays of individual in an unrestricted area f r :
in excess of 15 =rc=.
The annual total quanti:y of iciine-131 discharged at a exposure c.
site should not exceed 1 C1.
2.4-1
%rendment Nc. 32
2.4.1 Specifications for Licuid vaste Effluents 2.4.1.1 The concentration of radior._tive =aterials released in liqu:.d vaste effluents at the site shall not exceed the values specified in 10 CFR Par t 20, Appendix B, Table II, Column 2, for unrestricted areas.
2.4.1.2 The cu=ulative reicase of radioactive =aterials in liquid vaste effluents, excluding tritiu= and dissolved gases, shall not exceed 10 Ci/ calendar quarter.
2.4.1.3 The cu=ulative release of radioactive =aterials in liquid vaste effluents, excluding tritiu= and dissolved gases, shall not exceed 20 C1 in any 12 consecutive =onths.
2.4.1.4 During release of radioactive vastes, the effluent control =onitor shall be tat to alarm and to initiate the autc=atic closure of
~
each vaste isolation v.alve prior to exceeding the 11=its specified in 2.4.1.1.
2.4.1.5 The operability of each auto =atic isolatica valve in the liquid radvaste discharge lines shall be de=onstrated quarterly.
2.4.1.6 The equip =ent installed in the liquid radioactive vaste system shall be caintained and shall be operated to process radioactive liquid vastes prior to their discharge when the projected cu=ula-tive release could exceed 1.25 C1/ calendar quarter, excluding tritiu= and dissolved gases.
2.4.1.7 The =axi=e= radioactivity to be centained in any liquid radvaste tank that can be discharged directly to the envirens shall not exceed 10 C1, excluding tritium and dissolved gases.
2.4.1.8 Reoor t ins Requirement:
If the ce=ulative release of radioactive =aterials in liquid effluents, excluding tritium and dissolved gases, exceeds 2.5 Ci/ calendar quarter, the licensee shall =ake an investigation to identify the causes for such releases, define and initiate a progrs= of action to reduce such releases to the desigu objective IcVels listed in Section 2.4, and report these actions to the Co=nission within 30 days fro = the end of the quarter during which the release occurred.
2.4.2 Specifications for Licuid Waste Sa=oline and~ Menitoring 2,4.2.1
?lant records shall bc =aintained of the radioac:iva concentration and volute befera dilutien of lic.uid wac:e in:enecc f:: discharge and the average dilatica flew a.cd length of ti=a ver which each 2.4-2 A-end ent 'io 32
The average release rate of all iodines and radicactive materials in particulate form per site with half-lives (3) greater than eight days during any calendar quarter shall be:
0 1.5 x 10 Q 1 1 y
The average release rate of all iodines and radicactive materials per site in particulate for: with half-lives (4) greater than eight days during any period of 12 consecutive months shall be:
8 3.0 x 10 q, 1 The acount of iodine-131 released during any calendar quarter
~
(5) shall not exceed 2 Ci/ reactor.
The a=ount of iodine-131 released during any period of 12 consecutive conths shall not exceed 4 C1/ reactor.
(6) a Reporting Recuirementsi 2.4.3.3 (1), (2) or (3) listed 2.4.3.3 Should any of the conditions ofthe licensee shall take an investiga f
the causes of the release races, define and initiate a program o below exist, action to reduce the release rates to design objective levelsth listed in Section 2.4 and report l
within 30 days from the end of the quarter during which the re ease occurred.
If the average release rate of nobic gases frc= the site during (1) any calendar quarter is:
1 II 5800 Qiv iS
.w g
or.
iI 2400 Q 1
iv iY i
If the average release rate of all icdir.es and ::dicactive for: per site with 5.alf-lives greater
- 2)
=cterials in par:1culate is:
days durir.; aay calendar quar: :
than eight 0
5.9 x 10 Q
>1 y
2.4-7 A end ent No. 32
(3)
If the amount of iodine-131 released during any calendar quarter is greater then 0.5 C1/ reactor.
2.4.3.4 During the release of ganeous wastes from the primary system vaste gas holdup system the effluent monitors listed in Table 2.4-4 shall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.4.3.1 above. The operability of each automatic isolation valve shall be demonstrated quarterly.
2.4.3.5 The maximum activity to be contained in one waste gas storage tank shall : t exceed 29,000 curies (considered as Xe-133).
2.4.4 Specifications for Gaseous Waste Sampling and monitoring 2.4.4.1 Plant records shall be maintained and reports of the sampling and analyses results shall be submitted in accordance with Section 3.6.1 of these Sp-cifications.
Estimates of the sacpling and analytical error associated with each reported value should be included.
2.4.4.2 Gaseous releases to the environment, except from the turbine building ventilat ion exhaust and as noted in Specification 2.4.4.3, shall be continuously monitored for gross radioactivity and the flow continuously measured and recorded.
Whenever these Radia: on monitors are inoperable, grab sacples shall be taken and analyzed daily for gross radioactivity.
Whenever the Radiation or Flow monitors are inoperable for more than seven days, these releases shall be terminated.
2.4.4.3 During the release of gaseous wastes from the prirary system vaste gas holdup system, the gross activity monitor, the iodine col-lection device, and the particulate collection device shall be operating.
2.4.4.4 All waste gas effluent monitors shall be channel calibrated at least source which has been quarterly by means of a known radioactive calibrated to a National Bureau of Standards source.
Each monitor shall have a channel functional test at least monthly and channel instrument check at least daily.
2.4.4.5 Sampling and analysis of radioactive material in gaseous waste, particulate form, and radiciodine shall be performed in accordance with Table 2.4-2.
Bases e ial<
- asec1, a t.-
-t ta ca o i m
- h is c on c.
_t
- _i-<
,co t nn.
.. :.c.
T n.
3n c e
, ti.
,:i U
,t
- '"~'
Amendment No. 32
The beta dose contribution was deter =ined using Equation 7.21, as nnd Atorie Enerre -
described in Section 7-4.1 of !!cteorolomThe bet 1968.
a an infinite cloud passage sich s1=1-infinite geo:etry 1
~
The beta and g:n-a ec=-
ground level release (submersien dose).
ponents of the gross radioactivity in gasecus ef fluents were combined to determine the allovable continuous release rate.
Based on these calculations, a continueus release rate of gross radioactivity per site in the a=ount specified in 2.4.3.l(1) vill not result in of fsite annual deses above background in ex-cess of the li=its specified in 10 CFR Part 20.
1 The value Qiv used in the equation of Specification 2.4.3.1(1) vill be based on the average cocposition of gases determined f rem the plant The average energy per beta or ventilation exhausts.
gn==a disintegration for those radioisotopes determined to be present from the isotopic analyses are given in Table 2.4-5.
are not listed in Table Where isotopes are identified thatenergies are deter =ined frc= gable C; M. Lederer, J. M. Hollander, and I. Perl=an, Sixth Editien, 2.4-5, the gn-mn 1967 and the beta energy shall be as given in USSEff-tR-802, Spectra of Individual Necatron E=itters_ '(Seta Spectra),
II.
O. Hogan, P. E. Zigran, and J. L. Mackin.
For S' pacification 2.4.3.l(2), dose calculatiens have been =ade for the critical sectors an/ critical pathways f or all radio-fodines and radioactive care.ial in particulate fer=, withIhc calculatte half-lives greater than eight days.
der site meteorology for these releases.
For radiciodines and radioactive materials in p 5
(X/Q = 3.2 x 10 WNW sector at a distance of 520 meters The nearest tilk-sec/m ) for the dose due to inhalation.
3 goat is located in the WSW sector at a distance of 8050 is 1.6 the nearest tilk goat The applicable X/Q atThe grass-goat-milk-child thyroid chain meters.
3
~7 sec/m.
x 10 controlling.
(1) onsite The assu=ptions used for these calculations are:
meteorological data for the most critical 22.5 degre of 1220 and a gracing f actor of 0.6 was applied for pessible (2) credit ecolcgical chain ef f ects fro = radioactive iodine and particu-late releases.
2.4-10 caendrant No. 32
Specification 2.4.4.2 cxcludes =cnitoring the turbine luilding since this release is expected t: be a ventilation exhaust rave turbine negligibic relcace peint.
Many PWR reactors do not To be consistent in this requirement for building enclosures.
all PWR reactors, the monitoring of gascous releases f rom tur-bine buildings is not required.
andline and Disocsal u
2.4.5 Specifications for Solid uaste Measurc=ents shall bc =ade to deter =ine or esti= ate the total 2.4.5.1 curie quantity and principle radionuclide ce= position of all radioactive solid vaste shipped cffsite.
Solid vastes in storage and preparatory to ship =ent shall be 2.4.5.2 monitored and packaged to assure cc=pliance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-173.
J' Reporting Reeuire=ents_:_
2.4.5.3 Repotts of the radioactive solid waste ship =ents, volu=es, prin-ciple radionuclides, and total curie quantity, shall be submitted in accordance witu Section 5.6.1.
Bases:
The require =ents for solid radioactive vaste handling and dis-posal given under Specification 2.4.5 provide assurance that solid radioactive =aterials stored at the plant and shipped offsite are packaged in confor:auce with 10 CFR Part 20,10 CFR Part 71, and 49 CFR Parts 171-178. These require =ents provide the data for the licensee and the Co= mission to evalusta the handling and storage facilities for solid radwaste, and to eval-unte the environ = ental i= pact of offsite ship =ent and storage.
Reports on the quantities, principle isotopes and volu=es of the ship =ents, are furnished to the Co==ission according to On the basis Section 5.6.1 of these Technical Specifications.
of such reports and any additional infor=ation the C==ission may obtain frc= the licensee or others, the Cc=sission may from
. time to ti=e require the licensee to take action as the Co= mis-sion dee=s appropriate.
-~:nc er 32 2.4-12
~.
Table 2.4-1 LING AND ANALYSIS _
_TijDIOACTIVE LIQUID SAMP Detectable Type of Liquid Activity Analysis Concentratgs Sampling Frequency (uCi/ml)
Source 5 x 10~
(}
Principal Camma Ecittters Each Batch A.
Tent Tank Releases 10~
Dissolved Cases One Batch /Honth 10' B a-l.a-140, I-131 Weekly Composite S x 10' Sr-89
-5 10 Monthly Composite (1) p
!!-3 7
10~
g Cross a 5 x 10~
Sr-90 Quarterly Componite
-6 10 Weekly (4)
I-131., I-133
-1 (2)
H.
Pr!mnry Coolant 5 x 10 Principal Camma Emittera f
9tenn Cencrator Blowdown U)
-6 C.
10 Weekly Composite Ba-La_140, I-131
-5 10 Dissolved Cases One Sample / Month
- i
_a ro 5 x 10 a
Sr-89
- 3
,o
~5
/
10 3
Hoathly Composite'(f) 11-3 P
10' Gross a
~
3 : Ju Quarterly Composite'II)
St-90
Table 2.4-1 (continued)
NOTES:
i A composite sample is cne in which the quantity of each fraction of liquid added to the sample is proportional to l
(1) the quantity of liquid ef fluent represented by the sample.
j Prior to conpositing all samples taken for the cocposite the cocposite sample j
should be throughly mixed in order for release.
to be representative of the average ef fluent it say not be possible For certain mixtures of ga==a emitters, to ecasure radionuclides in ccncentratiens near their sensitivity (2) in the sa=pl'e in cuch limits when other nuclides are present it vill be Under these circunstances, greater concentraticas.
more appropriate to calculate the concentrations of such radio-nuclides using =casured ratios with those radienuclides which are routinely identified and ceasured.
The detectability li=its for activity analysis are based en the technical f easibility and on the potential significance in the (3)
For so=e nuclides, environment of the quantities released.
icver detection li=its =ay be readily achievable and when nu-they should also clides are measured below the stated li=1ts, be reported.
the The power level and cleanup or purificatica flow rate at (4) sample time shall also be reported.
Amendme't Nc. 32 2.4
'_4
Table 2.4-2 RADI0 ACTIVE CASEOUS VASTE SAMPLING AND ANALYSIS Detectable Type of Concentrations Sampling Gaseous
~
Activity Analysis (uci/ml)(1)
Frequency Source
(}
10' Principal Camma Emitters Each Tank
-6 A.
Vaste Gas Decay 10 Tank Relenaea
-3
-4 (21 (3) 10 Principal Gamma Emitters B.
Containn.ent Purge Releases Each Purge
-6 10 11 - 3
~4 (2} (3) 10 Principal Camma Emittero C.
Condenuer Alr Ejector Monthly
-6 10 II-3
(
10 Principal Cacua Frittern Monthly
-6 D.
Environmental Release (Gas Samples) 10 Points 1 -3 10' Weekly (Charcoal Sampic)
-10 10 (Charconi Sample) I-133, I-135 Monthly Princ1; al Camma Dnitters
,17 Weekly (Particulatca) for Ba-La-140, I-131 10 s
(at 1 cast 10~
Monthly Compoolte(')
Sr-89
_31 (Particulates) 10 ET Grosn a 10~
)
$l $ gd{3gggooite
o Table 2.4-3 L10tilD WASTE SYSTEM LOCATION OF FROCESS AND FITI.tJENT MONITORS AND SAMPt.FRS i
Grab H td Iladiation Auto Control to Continuous Samde Grone Dinnolved isoty lc level Process Stream or Pel m e Fofnt Alare:,
Isolation Valve Monitor Station Activity i
Cases Alpha If-3 Analysis Alarm X
X X
LASTE TEST TANKS X
X X
X RECYCLtT) WATE R TEST TGVS X
X X
X X
X X
II)
XI2)
X X
X X
FRIMANY t'EMIANT II)
X g Jiti H/DwAsst. Di'..IU M.t St.kV ILF, _WAl t H D IS{llo t.E _,,
X(3)
X X
smM crue Anm nin i nn I
X x(4) x(l) x X
X x
X COMPuMM 4 out.ING X
X X
X otitdoor s torage t imlO -
X X
x Dikes or Retentlyn Ponds (1)
Continuous montria.le t t a minc u gross activity only.
(2)
Grab sample numa nc.I f or tudine.
(3)
Service w.it r d ischarge monitor gives high radiation alarm and closes liqtiid radwaste discharge valve.
(4)
Grab sampi,.inalvzed for Iodine, dissolved gases, Alpha,11-3 and isotpic analysis.
( "s )
t i l y,li : ;ni l.i t i..n
. i l. i i ni closes the component cooling surge vent.
Amendment flo. 32 2.4,-17
Table 2.4-4 YST D1
_CASFOUS_VASTE S 1.OCAT10t( OF PROCESS AND EFFLUENT MONITORS AND SAMPLES I
Crab (4)
~
Measurement Sa ple Noble H-1 Alpha Part Continuous I
Auto Control to Stattoia ca,es Radiation Monitor isolation valve Alaria Process Streavn or Pelcage Point X(J)
X X
X X
X X
Xll)
WASTE CAS STCKA(.E TANe s X(2) O)
X X
X X
X X
j X
i l
CONDENSER AIK EJECTUtt X(3)
X X
X X
X X
X(2)
X X
X VL*.I lif Aut !!
XO)
X X
X X
O)
X X
X X
X X
X
. TANK Vt.'iT STtX1 GLNLRAlod glar.p -
X WAST E LVANP ATOR ti?;r U)
X X
X X
X X
X X
X 0)
X X
X X
X X
l't f lu.E PLACTok Ort 1 AltatENT 1
I'H! % Y AtlXILIARY BUf!bfN O)
X X
X X
X X
X VI::if tI AlinN X
X X
X X
X Vt til it A s tid U)
X X
PTEL liu ll ts i t.t.
X i
X VI';l If ArloN R AI4'AS1]. bill t tilt {t; f oss of diltation air flow or high radiation.
also sonitored l>y the It is air ejector and the dilution air fans.
(1) valve clos.- on le niunitored Jn the line between the (2)
Con.ini.c r.e f s e t.. t os ettluent routed to a ulngle release point, having a wingle c ont ineu>ue monit o r.
- .t.u k r.a s m.in itor.
prim.n y vent
...l s e lv.n e potute are
.t s e
( 1)
All ps**$ erne stack monitor.
he collected at the primary vent (4)
Gr ab s.nnple te c.m Amendment flo. 32 2.4-1s
.3.0 E!NIR0mfENTAL SITRVEILIANCE 3.1 Nonradiolecical Surveillance 3.1.1 Fich Iepince=ent Objective Fish inpinge=ent will be =enitored to assure that urpinsc=ent losses rc=ain at acceptable levels.
Specificatien Once cach week, fish vashed fro = the traveling screens and collected 3.1.1.1 in the trash baskets over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period shall be icentified, counted and separated into three length categories
(<3",
3-6", >6").
The numbers i= pinged per =enth shall be esti=4ted by averaging the four weekly counts in any one conth and cultiplying the average by the nu=ber of days in the =enth.
Observatiens of fish vashed f ro= the traveling screens shall bc ende 3.1.1.2 daily by plant personnel in order to qualitatively conitor any obviously large increase in i=pinge=ent levels.
3.1.1.3 The specificatiens above shall be required only when condenser cec 1.-
ing water pu=ps are operating.
Reportine Reouirements The nu=bers of fish i= pinged shall be reported en a reutine basis.
Data shall be separated by species and length categories.
Bases Since historical fish i=pinge=ent levels at Connecticut Yankee have not been found to constitute a significant adverse i= pact based upon extensive studies of resident and =igratory fish species, it was felt that report icvels reficcting those observed would assure centinued protection of fish populations.
3.1-1
'lenc an:
o.
32
Table 3.1-1 DELETED i
3.1-2 A,endnent no. 32 l
3.1.2 Meteorolocical Monitoring Objective The objective of =cteorological conitoring is to cdequately measure and docu=ent ceteorological conditions at the site.
Specif ication The meteorological conitoring system shall conform to the recommendations in Regulatory Guide 1.23, Onsite Meteorological Prcerams_.
Reporting Requirements consistent Meteorological data shall be sirr-nri=ed in a for=at with the reco==endations of Regulatory Guide 1.23, and observa-tions in a form consistent with National 'w'enther Service pro-Su=saries of data and observations shall be available cedures.
If the out-U.S. Nuclear Regulatory Co= mission.upon re:uest.
to thL time of any of the ceteorological instru:ents exceeds seven Arendren t '.o. 32 3.1-3
consecutive days, the total outage time and dates of cutage, the cause of the outage, and the instrument (s) involved shall be reported within 30 days of the initial time of the outage to the appropriate Regional Office (a copy to Director Nuclear Reactor Regulation).
Bases The collection of meteorological data at the plant site provid es information which may be used to develop atmospheric dif fusion parameters to estimate potential radiation doses to the public resutling from actual routine or accidental-releases of radioactive materials to the atmosphere.
A meteorological data collection program as described above is necessary to meet the requirements of sub-paragraph 50.36 a (a) (2) of 10 CFR Part 50 and Appendices D and E to 10 CFR Part 50.
3.1 -4 Amendment No. 32
3.2 Radiological Environmental Monitoring Objectives The overall objectives of the radiological environmental moniter-ing program are:
(1) to establish a sampling schedtle which,ill recognize changes in radioactivity in the envirenrent in the near vicinity of the plant, (2) to assure that effluent releases are kept as low as reasonably achievable and within allcrable limits, l
and (3) to provide information on the type and quantity of radiation in certain indicator organists or critica1' pathways which can be used as a basis for evaluating radiation exposures resulting from plant operation.
Specifications 3.2.1 Except as specified below, environmental samples shall be collected and analyzed according to Table 3.2-1 at the locaticas shown in Figures 3.2-1 through 3.2-3.
The minimum pratical detectable con-centrations and sample sizes for the radioactivity detection procesures shall be those presented in Table 3.2-2.
The annual doses correspond-ing to these detection limits are also indicated where applicable.
3.2.2 During the seasons that animals producing milk for human consumption are on pasture, samples of fresh milk shall be obtained f rom these animals at locations and frequencies shown in Table 3.2-1, and analyzed for their radiciodine content calculated as iodine-;31.
Analysis shall be carried out within eight days (one 1-131 half life) of sampling.
Suitable analytical procedures shall be used to determine the radiciodine concentration to a sensitivity cf 0.5 picocuries per liter of milk at the time of samrling.
For activity levels at or above 0.5 picccuries per liter, the overall (one sigma confidence level) of the analysis shall be eithin error
+ 25%.
Results shall be reported, with associated calculated error, as picoeuries of 1-131 per liter of milk at the time of sampling.
If milk cannot be obtained, samples of pasture grass shall be ob-tained from the locations where the animals are pastured as identi-ied in Tab le 3.2-1.
Suitable analytical procedures shall be used to determine the radiciodine concentration of grass to c sensitivity of 0.050 pCi/gn (wet) at the tire of sar;1ing.
For activity levels at or above 0.050 pCi/gm, the overal; error (one sigma confidence level) of the analysis shall be within 3 50E.
3.2.3 An annual census of anical:
7-juciv mil; - r br r c > u.n c
shall m mducted st t
~ o r r i,-
e t
th :
' w !, a n<.
.' tL 5
11 w,,m :nc mJ mm m
3.2-1 knencnent No. 32
1.
Within a 1 mile radius f rom the plant or the calculated 13 mrem / year thyroid isodose line whichever is larger: A door l
to door or equivalent counting technique shall be utilized.
2.
Within a 5 mile radius for cows and a 15 mile radius for Enumeration by using referenced information fror goats:
sources such as county agricultural agents or other reliable Sources.
A change in sampling locations shall occur if, after census takings, a new milk animal is f ound to be in a more critical l
location f rom the s tandpoint of deposition of radiciodine than one of those specified.
A suitable substitution shall be made if samples from a locatien of milk animals are no longer available due to removal of the animals from the location.
3.2.4 Edible vegetable and fruit samples shall be collected at the middle and the end of the harvest seasons from commercial farms in the vicinity of the station.
There shall be two locations, an indicator station within 10 miles of the station and a control station about 10 cc 20 miles or acre from the station.
3.2.5 If commercially availabic and if the animal feed is grown wi:hin 10 miles of the station, samples of meat, poultry and eggs shall be sampled annually from an indicator (within 10 miles) and a control station (greater than 10 miles) and given a ga==a isotop;c analysis.
3.2.6 Deviations are permitted f rom the required sampling schedule if seasrnal specimens are unobtainable due to hazardous cenditicas, unavailability or malfunction of automatic sampling equipment.
If the latter, corrective actions shall be completed prior to the end of the next sampling period.
All deviations from the sampling schedule shall be described in the annual reports.
Reporting Recuirements Routine Reports 3.2.7 Routine reports for the radiological environmental surveillance program will be made in accordance with Section 3.6.
Non-Routine Reports 3.2.8 Non-Reutine reports for the radiological environmental survcillance pregran ill oe na6, in a:cordance with Sect i -
4 3.2-2 Anendment No. 32
Bones l
I-131 concentration of 2.4 picoeuries per liter of cou r. ilk and 3.4 Anpicocuries per liter of goat = ilk vill result in a dose to the thyroid of an infant (2 gram thyroid) of 15 =re= per year, based upon the consumption of one liter or 0.7 liter per day, respectively, of fresh milk for the year.
Reporting recuire:ents for the radiciodine pathways give allowance for six conths grazing.
The specifications and effluent monitoring requirements in Section 2.4 ensure that releases of radionuclides in liquid The and gaseous effluents are properly controlled and tonitored.
data obtained as a result of these requirements will per=it an evaluation of the perfor=ance of the station in ter=s of radio-nuclides released to the environ =ent.
The environmental conitoring progra: requires sufficient saepling locations, types of samples and sensitivity of analyses which, with preoperational and background data., will provide verification of the effectiveness of station effluent control, an indication of measurable change in radiation and radioactivity levels in the environment, and provide reasonable assurance that the design objective doses (specified in Section 2.4) are r.ot exceeded.
Amendment No. 32 3.2-3
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3.2-4 Amendner:t No. 32
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27 l
l Higgenom 0 17 O C.Y Site soeecm 0 15 26 S
D v'
l t
18 s
Ol6 28 o Ecst Haddem L
ti,,t,,,t pl scale of miles J
[
C Uell Water Sampling Stations I
e Aquatic Sampling Statiens FIGL';.E 3.2-3 Aquatic and Lell L'a:er S W 'r-Stati:n:
hadd= b2:
C'.
Anend ent No. 32 3.2-6 n
9 TABLE 3.2-1 CONNECTICUT YAt:KEF RADIOLOGICA1. ENVIRONMENTAL MONITORING PROGRAM (b)
(
592f _P. T11'".t_F r,e_Ti e n c y and Analysis'c)
I Distance Camma Air
)
g) 1.o c.i t i on 6 Direct ion (3)
Dose P.i r t ic ul a t e Sail Vegetation Water Milk
!ctrestrial Statte 1.
on site fence n.o r ' or on wa ste stor.we tanks 0.5 miles, N H
2 On site fence o 'i ete gas surge where 0.5 miles, N M
3.
On r i t s-fence twa i its-harge an il 0.5 miles, SSE M
4.
a )n ette fence i,i c i. i t.1 house 0,5 miles, WNW M
I'I i.
sin
.t r e - Ia) i :lo ! I:
i..i.nl 0.5 miles, NW M
Wl-M2-QS
- 3.,5 w
r.,
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- sah i.
t-1.0 mile, ENE Wl-M1-0 (c )
A2.5 Wl-M2-QS '"}
a.', 5
- i. i i. ui. l...i 2.0 mile, SE M
R.
i.r H i.hla,
- 1. 0 m i l e, ESE M
Wl-M2-qs A.$, s 9.
Hio:inom 3.3 mile, WNW M
Wl-N2-Q5 A2,5 1,
lin t 1f
'a i r Roa !
, i.t IInapton 3.0 mile, NSW M
Wl-M2-Q5 A2,5
- 11. Mt.tdl. town
- 10.0 mile, NW Wl-M2-95 A2,5
~
- 12. Deep River
- 8.0 mile, S F,E M
Wi-M2-Q5 A2,5
- 11. h.rth Ma<lison
- l2.0 mile, SW M
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A2,5 14 t.l.L. ster
- 10. 0 m ile, ENE M
W i - m'-Q S A2,5 15 on 11:<-
- Wri t -
0.5 mile, SE M1,2,4,5 I e., WelI
- . t.u. '. -i, i i. i. t.
I.e.t
!!a.l.l.n.
- 3.0 mile ';
g l,1, c., s 1; Urli - I n j..n a 11 1:,.. t 1.0 mile, NW yt,7,4,s lx. Well - Ila.t.l.e.
1.0 mile, S 41
.), '..
p 19 i..w l... i t 1..n il
.7 mile, N I:
ti l 33 i o.
t4.w 1.. atlon 2.2 mile, ESE fil (D
3
?). Cow li iation v' 2.8 mile. E MI
}
iw I, i a t 1.. n
- 1 J,0 m il e, l.NI.
Mi to
't.
- c... i t i.. i s i..n i
. 7.o mi l., s M3 U
2.
i ist locatfon r+
1.0 mile, FNr II)
=
^2,3(h) innai. :. v,7,.i.
O N
TABLE 3.2-1 (continued)_
Sample Type, Frequency (b) and Analy Bottom Fish (1)
Shellfish _,
Distancega)
Sediment Water Direction Location Aquatic Stations Q2,3 0.5 milet, SSW Conn. River - Vicinity of intake Q2,3 26.
- 3 mile, NW Q2,5 Conn. River - IIIgganum L'ight 27.
- 2 mile, SE Q2,5 II}
Conn. Elver - E. IIaddam Bridge Q1,2,4,5 Q2,3 28.
mile, ESE Q2,5 Q1,2,4,5, Q2,3(1) 29.
Connect icut u nct. v icinity of, tue 0.75 t,.,
Plant Distliarge Canal
- 9 mile,im 30.
Conn. River - ltiddlecova Q2,3 to 1.5 mile, SE 31.
Itouth of the Salmon River Control Stations t o nentest half mile (a) Distance l
W - Week ly, !! - Ifonthly, Q - Quar terly, SA - Seml-Annual, A - Annua 37, 4 - E-3; 5,,- Sr-89, St-90, co-137 (b) 1 - Groos Beta, 2 - Camma Spectrum, 3 - I-131, Sr-89, Sr-90, Ca-1 mg (c) period April through October and once in February Mg (d) During tin-Includen n charcoal filter that is to be analyzed weekly for I-131 5
(c)
Analyaco are done on the month'ly and quarterly composites (f) if the former is available A similar annlysia vill be 'done on milk instead of grass (g) l farms During the harvest season, when avcilable from commercia (h)
TABLE 3.2-2 HINIMDf DETFCTAPLE LEVEL.S IN_EffVIR0j.104 AL_SAMPl.ES_AND RESULTING DOSES 7
Hinimum Detectable Annual Dose I.evels' Assoc!ated l
Analysis Sample Size Jm3.)
with_tpt' (mrem)
Critical _0 g Annual Intake E rf e Typt Well and River Water Gross beta 1 liter I pCf/t Carea spectrum 3 liter 20 pC1/1 2
Sr-89 2 liter 2.0 pct /1 0.2' bene 440 1 Sr-90 2 liter 1.0 pC1/1 1.0' bone 440 1 Cs-137 2 11ter 6.0 pct /l 0.078' whole b>ly 440 1 I
H-3 2 liter 60 pC1/1 0.005' body tissue 440 1 e
0.05 pct /g' Bottom Se,ltw nt an 1 ' il Camma spectrum 1 kg Sr-89 1 kg 0.072 pct /g Sr-90 1 kg 0.036 pC1/g Cs-137 1 kg 0.064 pC t /g 0.05 pCi/g#
Sr-89 100 g 0.018 pCi/g 0.08 bone 18.1 kg Fish and Sh.tiftsh Gamma spectrum 1 kg 0.0*
pCf/g 0.4 liene IR. 3 kg Cs-137 100 g 0.056 001/g 0.03) whole body
- 18. 3 In g Sr-90 100 g Ti ll 1 month I mi em whole bmty 12 month cuposure G.wr 3 D.
exposure p
Child's thyantd 183 1
.3 1-131 4 liter 0.5 pCi/I 1.6 Sr-89 1 liter 2.0 pCl/l 0.08 bonc 1A) 1 li t ik Sr-90 1 liter 1.0 pCl/l O.40 bone 181 1 Cs-lj7 1 liter 6.0 pC1/1 0.0 16 whole body 181 1 (D
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4.0 SPECIAL SURVEILLANCE. RESEARCH OF STUDY ACTIVITIES 4.1 Fish Deterrent Studies (DELETED) 4.1-1 Ame & ent No. 32
42 Shad Monitoring Program Description The objective of the shad =onitoring progran is to determine the size and population dyna =ics of American Shad co=prising the annual spawning run in the Connecticut River.
Approxi=ately 4000 Accrican Shad will be tagged and released at the couth of the Connecticut River during each year of an anti-cipated 8-year study program which began in early 1974.
In this tag and recovery =cthod of esti=ating population size, co==cr-cial fisher =en act as the recovery eechanism.
Representative fish samples will be taken for age, size and sex analysis.
This study program design has been followed since 1965.
Reporting Recuire=ent Reports vill be trans=itted to the Co==ission upon the co=ple-tion of each annual study ef fort in accordance with Section 5.6.
Basis The Licensee has sponsored nu=crous shad populatien studies since 1965.
Although much has been learned as a result of these study ef forts, the Licensee believes that the co==ercial importance of the Connecticut River shad fishery warrants addi-tional study.
In keeping with this policy, the Licensee is co-sponsoring ongoing shad population studies with the State of Connecticut.
It is presently anticipated that shad studies will be continued for at least seven more years.
- 4. 2 d en: e
- o. 32
4.3 Phytoolankton Studies (DELETED) 4.3-1 endnert No. 32
5.0 ADMINISTPATIVE CONTROI.S Objective Ad=inistrative and manaccrent controls are established to pro-vide continuing protection to the enviror.nent and to 1:pic ent the enviror: ental technical specifications.
Specifications 5.1 Recnonsibility 5.1.1 The ulticate responsibility for i=ple=entation of the Enviren-cental Technical Specifications shall reside with the corocrate officers of The Connecticut Yankee Ato ic Power Cc pany.
The corporate and station level organizatica chart is shewr in Figure 5.2 1.
5.1.2 The Plant Suocrintendert shall have direct responsibility for assuring that the operation of The Connecticut' Yankce Ato:1c Powcr Co pany, liadda: Neck Plant. is ceniucted in such a canner as to provide continuing protection to the envircr ent.
During periods when the Plant Superintendent is unavailabic. he 227 delegate his responsibility to the Assistant Plant Superintendent l
or qualified plant supervisory personnel as designated in the plant ad=inistrative procedurcs.
Operation of the plant to insure adherence to the limiting con-ditions for uperation is the responisbility of the Plant Super-intendent with the assistance of the plant staff ergani:stion.
5.1.3 The environ = ental surveillance prograns and the special ecolo-gical studies will be perforced through contractual arrangc ent either by personnel of the Northeast Utilitics Cc parv G;U500) or by various outside environmental contractors appointed by the company.
The coordination of and technical direction for all the progra:s will come from the Envircemental Precra s Branch reporting through the administrative chain of ccc:and l
in Figure 5.11.
5.1.4 The 12:cdiate responsibility for the review and updatirt of each progran lies with the grcup perf orning the activity.
They can receive assistance in the review from the varicus scientific and technical cersonnel trployed by SU5^0 or frc: cuts-le environ: ental cenauttarz.
5.1.3 The Fri ciren~n al
,< x
+ '- " r.
m., - -.. - - -..c., t.....
chall.nciuae :.e
- e v i..-
- r. a auc t o f e n c i r c n < n t a, r_a t.c r s a s described in Section 5.3.
5.1-1 Arer.drent f.'o.
32
The Environmental Review Board shall be constituted as fcilows:
5.1.5.1 Membershio The ERB shall consist of a minimum of five persons (with alternates) none of whom shall be directly employed by the Connecticut Yankee Atomic Power Company.
As a group thef will collectively provide expertise in the environmental disciplines and engineering. The collective competence of this group will be maintained as changes to membership are made.
The members and alternates shall be appointed by the NUSCO Vice President Nuclear Engineering and Operations.
The ERB will obtain advice and counsel of scientific and techni-cal personnel employed by the Company or other organizations whenever necessary to carry out its responsibilities..
5.1.5.2 Meeting Frequency The ERB shall meet at least semiannually on cal.1 by the chair-man or as requested by individual members.
5.1.5.3 Quorum A quorum will consist of the majority of the designated board members or their alternates.
The majority shall include the chairman or the vice-chairman or their designated alternate.
5.l.5.4 Authority The ERB shall be advisory to the NUSCO Vice President Nuclear Engineering and Operations, the Plant Superintendent, the NUSCO System Superintendent Nuclear Operations and the NUSCO Director Nuclear and Environmental Engineering as indicated in Figure 5.2-1 5.1.5.5 Records 5.1.5.5.1 Minutes shall be recorded for all ERB meetings. Meetings shall be numbered in sequence and distribution shall be to the NUSCO Vice President Nuclear Engineering and Operations, the Plant Superintendent, the NUSCO System Superintendent Nuclear Operations, the NUSCO Director Nuclear and Environmental Engineering and the Chairman of the Nuclear Review Board.
5.1-2 A.-end en Mc. 32
5.1.5.5.2 Reports of all audits including recommendations of the 5:ard shall be made in writing to the NUSCO Vice President Nuclear Engineering and Operations, the NUSCO System Superintencer.:
Nuclear Operations and the NUSCO Director Nuclear and Erviror.-
mental Engineering with copies to the Plant Superintendent.
5.1.5.5.3 The findings of all reviews of Environmental Technical Soe:ifi-cation violations and recom.mendations to prevent re:urrer.ce shall be reported in writing to the NUSCO Vice Presiden: hJClear Engineering and Operations, the NUSCO System Superintencer.t Nuclear Operations, the NUSCO Director Nuclear and Environmental Engineering and the Plant Superintendent.
5.1.5.6 Procedures Written administrative procedures for Board operation shall be prepared and maintained.
5.1. 6 The Plant Ooerations Review Committee (PORC) shall be constituted as specified in Section 5.2, and shall assume the same scope of responsibility in onsite environmental matters which it holds in other operational matters. The PORC shall make recommendations to the Plant Superintendent.
Amer.d-c-: ':o. 32 5.1-3
PRESIDENT CYAPC0 VICE PRESIDENT
___________-l CYAPCO*
I I
i 1
NUSCO DIRECTOR ENVIRONMENTAL l SYSTEM SUPERINTENDENT NUCLEAR NUCLEAR AND REVIEW BOARD REVIEW BOARD NUCLEAR OPERATIONS ENVIRONMENTAL ENGINEERING l
F l
I l
ENVIRONMENTAL PROGRAMS BRANCH l
g 1
l l
L______________7 l
w 7
i N
PLANT
_________________y SUPERINTENDENT I
I l
l l
PtANT OPERATIONS REVIEW COMMITTEE l
STAFF
- Also NUSCO Vice President Nuclear Engineering and Operations p
- A hnintstration NUSCO 1
k
-- - - AJministration and Line responsibility CYAPC0
-Conrunications, advisory reporting g
n
[
FIGURE 5.2-1 Chirt of Organizational Responsibilities for Northeast Utilities and the Connecticut Yankee Atomic Power Company.
E.i
5.3 Review and Audit the f ;11ow in g:
The Environmental Review Board shall review 5.3.1 Environmental Te chr.ic al Specifica tions 5.3.1.1 Proposed changes to these and the evaluation of the impact of the change.
Proposed changes or modifications to plar.: syster.s or ecuipment 5.3.1.2 which are determined to have an "unreviewec environmental i= pact 3.3.2 The Environrental Review Board shall make or cause to be rade seciannual reviews or audits of the fellowin;:
at least Investigations of all reported instances of violations of 5.3.2.1 Where investigati:>n Environnental Technical Specifications.
indicates, evaluate and formulate recoceendatiens to prevent recurrence.
Surveillance records, written procedures and reperts recuired for 5.3.2.2 compliance with these Environmental Technical Specificaricas.
5.3.3 The Environnental Review Board shall make or cause te be ade an annual reviev or audit of the results of the ' tirenr2n a. nenitor-ing program.
described in the Envirenrental An annual review of the prograre the Encirer, ental 5.3.4 Technical Specifications shall be perforced be Programs Branch with the objective af proposin; chanas or of the preprars. Tha modifications of the scope or content ER3 bef:re sub-proposed changes will be reviewed by POEC ani the mittal to the SRC.
Amer d erc No. 32
5.5 Procedures including applicable check li. s and Detailed written procedures, instructions, shall be prepared and followed f or all acti. ;:ies 5.5.1 the environmental technical specif t:a:icns.
involved in carrying out data recording and s tcra t e, Procedures shall include sampling, and ac:icas calibration, measurements and analysis.
Testin: fre-instrument to be taken when limits are approached er exceeded.
included. These f rec uenc ie s s.;a;i quency of any alarms shall be in similar be determined f rom experience with similar instrunents technical manuals.
environments and from manufacturers' Precedures shall be prepared for assuring the quality of progrca the including analytical measurements, which documen:
progran in policy directives, designate a responsible organi-
- results, zation or individuals, include purchased services, (e. g., cc a-l include audits and tractual lab or other contract services),
investigate include systems to identify and correct deficiencies,and review and evaluate anomalous or suspect results, and reports.
in standard operating procedures shall include previsi:ns,
Plant addition to the procedures specified in Section 5.5.1, t e er.su:e 5.5.2 systems and components are operated in cc :1_ar-that all plant cs. r:
with the limiting conditions for operations cstablishec of the Environmental Technical Specifications.
thereto shall :e reciewe; All p rocedures described above and changes 5.5.3 prior to implementation as follows:
By PORC f or procedures which are perforred by er under the direct responsibility of plant personnel, crocedu es v".ich nay a.
related tc nuc ear i
effect plant operation, or procedures 1
sarety.
By a qualified individual of the Envirocrental Frograms Eranch, for procedures performed by cr under b.
other than the author, of the Environmental Progr:ms Branch, the direct responsibility the environmental monitorini program.
or procedures related to Temporary changes to procedures nay be made pro;idec:
c.
altered 4
of the o-iginal procedure is not
- 1) The intent the change is a? proved 2)
For procedures reviewcd by PORC, managenent staff, at least l
by two members of the plant one of whom holds a senior reactor operater's license is reviewed by PORC and approled by the,lant and then superintendent wi thin 14 davn of irl.c entatien.
')
Per promdures review b.-
t '. c
" clu m)), lite Cl :n Z e 19
'It'~-'
tt' 3 3F J1;*
^ ?cr cf the Q rg,
e *
-~
7-I DI
< f;ia t.
5. ;~
ATendrent ib. 32
5.6 plant Reporting Recuirement_s_
- 5. 6.1 Routine Reports Annual Environmental Operating Report a.
Part A: Nonradiological Report.
A report on the environ-mental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the appropriate Regional Of fice (with copy to the Director of Nuclear Reacter Regulation) as a separate document within 90 days af ter January 1 of each year.
The period of the first report shall The report shall include su=maries, begin on January 1, 1975.
interpretations, and statistical evaluation of the results of the nonradiological environmental surveillance activities (Sectien 3.0) and the environmental monitoring programs required for the by limiting conditions for operation (Section 2.0) report period, including a comparison with pre-operational studies, operational controls (as appropriate),
and previous of the environmental,orveillance reports and an assessment operation on the environment.
observed impacts of the plant If harmful effects of evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the the problem and a proposed course of action to alleviate problem.
Radiological Report.
A report,on the radiological Part B:
environmental surveillance programs for the previous 12 months of operation shall be pebmitted to the Director of the appropriate Regional Office (with copy to the Director of Nuclear Reactor Regulation) as a separate dccument within The period of the first 90 days after January 1,of each year.
The reports shall l
report shall begin on January 1, 1975.
interpretations, and statistical evaluation j
include summaries, of the results of the radiological enviromental surveillance activities f or the report period, including a comparison l
with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation If harmful effects or evidence of on the environment.
irreversible damage are detected by the monitoring, the i
licensee shall provide an analysis of the problem and a j
proposed course of action to alleviate the problem.
shall include a sunmary table of all The annual report rad iological environmental 97mnles chich shd 1 inci n f ollowing inf or-at ion.- 2ach,ath nv m aH e ' r.J c d
. m vf analysi:
indicator locations 1.
Total number of analyses performed at control locatiens 2.
Total number of analyses performed at 3.
Minimun detectable level 5.6-1 Amendnent No. 32 i
4.
Mean and range o*~
all indicator Ic'
- .cnn terether 5.
Mean and ranar all control locati ns torerner 6.
':a r..e, d i s t a n c e et direction fron <i. -ha r ae, n an ar.d ranne for t he-loc.i t is with the highest r ;ual
.ar ( i r.
. ator or centrol).
ents u deriw d in 7.
?;urber of nonroutine e por te d nea':'.
Section 5.6.2b.
' ' t ' - l '>
Arendnent No. 32
In the event that some results are not available within the 90 day per i od, the report shall be subnitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
b.
Radioactive Ef fluents Release Report A report on the radioactive discharges released form the site during the previous 6 months of cperation shall be submitted to the Director of the appropriate Regional Office (with copy to the Director of Nuclear Reactor Regulation within 60 days after January 1 and July 1 or each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, measuring evaluating, an reporting readioactivity in solid wastes and releases f radioactive materials in liquid and gaseous effluents form light-water-cooled nuclear power plants with data su=marized on a quarterly basis following the format of Appendix B thereof.
The report shall include a summary of the neteorolegical conditions concurrent with the release of gaseous ef fluents during each quarter as outlined in Reculatx, Gu ld: 1.21, with data summarized on a quarterly baais fellowing the format of Appendix B thereof.
Calculated offsite dose to humans resulting f rom the release of effluents and their uubsequent dispersien in the atmosphere shall be reported as recommended in Regulatory Guide 1.21.
5.6.2 Nonroutine Reports Nonroutine Environmental Operating Reports a.
A prompt report shall be submitted in the event that l
(a) a limiting condition for operation is exceeded (as specified in Section 2.0, " Limiting Ccnditions for Operation"), (b) a 30 day report shall be s ubmi t t ed in the event that a report level is reached (as speci-fied in Section 3.0 " Environmental Surveillance"),
or an unusual or inportant event occurs that causes a significant environmental impact, that affects pot ential environmental inpact from plant operatica, or that has high public or potential public interest concernin~ cnvironmental impact f r c~ c l.
- marati
".> ports Aa ! ' be u5 i:t, undcr enc
~
r, ne schedu l.. t i < r i?
c_
u.
(l)
Prompt Leport. T'aose events raquirir.; promp. t ap :rts within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the Director of the appropriate Regional 5.6-2 Amendment No. 32
Of fice and with 10 days by a written report to the Director of the appropriate office (with copy to the Director of Nuclear Reactor Regulation.)
(2) 30-Day Report.
Those events not requiring prompt report shall be reported within 30 days by a written report to the Director of the appropriate Office (with copy to the Director of Nuclear P.eactor Reg-ulation.
The reporting schedule for reports concerning limiting conditions for operation and report levels shall be specified in the licensee's technical specifications.
Reports concerning unusual or important events shall be reported on the prompt s ched u le.
Written 10-day and 30-day reports and, to the e:. tent possible, the preliminary tclephone, telegraph,.or facsimile reports shall (a) describe, anlayre, and evaluate the occurrence, including extent and magni-tude of the impac t, (b) describc the cause of the occurrence, and (c) indicate the corrective action (including any significant changes nade in re :edures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar cenpo-nents or systems.
The significance of an unusual or apparentl:. important event with regard to environne tal impact may not be obvious or fully appreciated at the tire of occurrence.
In such cases, the NRC shall
_a informed prcmp:1:, of l
changes in the licensee's assessment of the signifi-cance of the event and a corrected report shall be schmitted as expeditiously aJ possible.
5.
Nonroutine Radiological Environmental Operating Report (1)
Anomalous Measurement Report.
If a confirmed measured level of radioactivity in any of f-site environmental medium exceeds ten times the control station value and can be attributed to an increase in plant related activity, a wrltten report shall be submitted to the Directcr of the appropriate Regional rf' ice (t ith copy to the 71rac tor cf Nucl ear Reac t or Me:, :1t
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Amendment No. 32
(2) Milk Pathwav Measurcments (a)
If cow or goat milk samples collected over a, calendar quarter show average plant related concentrations I
of I-131 of 4.8 or 6.8 picocuries per liter or greater, respectively, a plan shall be submitted within 30 days advising the appropriate Regional Office (with a copy to the Director, Suclear Reactor Regulation) of the proposed action to ensure the plant related annual doses will be within the design objective of 15 area /yr to the thyroid of any individual.
(b) When pasture grass is sampled rather than goat milk, if individual pasture grass samples show plant related I-131 concentrations of 0.072 picoeuries per gram wet weight or greater, a plan shall be submitted witl in 30 days form confirmation of results advising I
appropriate Regional Office (with a copy to the Director of Nucle'r Reactor Regulation) of the proposed action to ensure that plant related annual doses will be within the design objective of 15 mrem /yr to tne thyroid of any individual.
c.
Nonroutine Radioactive Effluent Report The reporting requiremen ts for rad ioac tive discharge are specified in Section 2.4 of these specificatior>.
5.6.3 Channes in Environmental Technical Specifications a.
A report shall be made to the NRC prior to irplanentation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change constitutes an unreviewed environmental impact.
The report shall include a description and evaluation of the changes and a supporting benefit-cost analysis.
b.
Request for changes in environmental technical specifications shall be submitted to the Director of Nuclear Reactor Regulation.
NRC for review and authorization.
The submittal will include an evaluation of the environmental impact of the change.
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e TABLE 5.6-1 DELETED 9
i Ar.er.drent No. 32 5.6-5
5.7 Records Retention 5.7.1 Records and logs relative to the following arean shcil 5.-
at; a r. 3 retained for the life of the,lant:
a, Records and drawin.x detailing plant desen chanu anc taodi fications nade to system and equi
.nt as..icribe; in Section 5.,.l.
b.
Records o f all orocesse<! data from envir.'n ental menit: ring, surveillance, and special surveillance and sttJy activities required by these environmental technical specifications.
5.7.2 All other reocrds ind loga relating to the environecnta; te:.i-cal specifications shall be retained for five years f o ll e'.ti r '
logging or recording.
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erendr=n: I:3. 32