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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases B13555, Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-06-25025 June 1990 Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation B13380, Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal1989-09-29029 September 1989 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal ML20245J1451989-08-0404 August 1989 Proposed Tech Specs Re Containment Air Recirculation Sys, Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys ML20248D7711989-08-0202 August 1989 Proposed Tech Spec 3/4.5.1 Revising ECCS to Reflect Component Configurations Following 1989 Refueling Outage Mods to ECCS to Resolve Single Failure Concerns Identified on Three Separate Occassions B13327, Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests1989-08-0101 August 1989 Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests ML20248B2771989-07-31031 July 1989 Proposed Tech Specs Re Fire Detection & Spray &/Or Sprinkler Sys B13284, Proposed Tech Spec 3.6 Re ECCS1989-07-31031 July 1989 Proposed Tech Spec 3.6 Re ECCS B13314, Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys1989-07-28028 July 1989 Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys B13295, Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage1989-07-28028 July 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage B13292, Proposed Tech Specs,Supporting Cycle 161989-07-28028 July 1989 Proposed Tech Specs,Supporting Cycle 16 B13181, Proposed Tech Spec Sections 3/4.4,3/4.6 & 3/4.7 Re RCS1989-06-30030 June 1989 Proposed Tech Spec Sections 3/4.4,3/4.6 & 3/4.7 Re RCS B13221, Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes1989-06-29029 June 1989 Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes B13269, Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation1989-06-23023 June 1989 Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation ML20245D2281989-06-15015 June 1989 Proposed Tech Specs Re Cycle 15 Operation Coastdown Analysis & Operation A07433, Proposed Tech Specs Re Leakage Detection Sys1989-05-30030 May 1989 Proposed Tech Specs Re Leakage Detection Sys B13256, Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual1989-05-25025 May 1989 Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual B13169, Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs1989-04-30030 April 1989 Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs B13208, Proposed Tech Specs Supporting Operation of Cycle 151989-04-30030 April 1989 Proposed Tech Specs Supporting Operation of Cycle 15 ML20245F2581989-04-25025 April 1989 Proposed Tech Specs Re Administrative Controls in High Radiation Area B13201, Proposed Tech Specs Re Containment Integrity,Internal Pressure & Air Recirculation Sys to Allow Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power1989-03-31031 March 1989 Proposed Tech Specs Re Containment Integrity,Internal Pressure & Air Recirculation Sys to Allow Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power B13098, Proposed Tech Specs Re Administrative Controls & Organizational Charts1989-03-13013 March 1989 Proposed Tech Specs Re Administrative Controls & Organizational Charts B13151, Proposed Tech Specs 3/4.1, Reactivity Control Sys1989-03-0606 March 1989 Proposed Tech Specs 3/4.1, Reactivity Control Sys B13127, Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-371989-03-0101 March 1989 Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37 1999-08-24
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14627, Reactor Containment Bldg ILRT Rept. W/1993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept. W/ B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria ML20127E2901993-01-11011 January 1993 Rev 43 to Corporate Organization for Nuclear Incidents (Coni) Procedure Coni 1.02,page 7.2-2 of 2,Figure 7.2, Cero Staff-Managers Annual On-Call Schedule B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20217A6311990-11-14014 November 1990 Rev 0 to Haddam Neck Plant Reactor Containment Bldg Integrated Leak Rate Test ML20058H0611990-10-31031 October 1990 Core Xvi Startup Physics Test Rept ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases 1999-08-24
[Table view] |
Text
-, - -- .. ,_
., . .> .s
.s Attachment 1 Corrections to the Haddam Neck Proposed Radiological Technical Specifications I
i' l
l l-l-
l hDj71f0376850702 P M 05000213 PDR
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Change-Out Instructions REMOVE INSERT
- 1. Remove existing " Definition" Insert 3 correctly revised " Definition" section pages (3) included in pages 1-Sa, b and c.
the beginning of Attachment 5.
- 2. N/A After pages B3/411-1 of the Haddam Neck Plant RETS (Attachment 5),
insert Figure 5.1-1.
- 3. N/A After the Attachment 6 title page, insert the title page for the Haddam Neck Plant Radiological Effluent Monitoring Manual.
- 4. Remove existing page C-3 of Insert the corrected page C-3.
the Haddam Neck Radiological Effluent Monitoring Manual.
- 5. Remove existing page D-3 of Insert the corrected page D-3.
the Haddam Neck Radiological Effluent Monitoring Manual.
- 6. Remove existing page E-9 of Insert the corrected page E-9.
the Haddam Neck Radiological Effluent Monitoring Manual.
t f
i
, - - . .w
1.0 DEFINITIONS -
The defined terms below appear in capitalized type and are applicable to l Sections 7 and 8 of these Technical Specifications.
ACTION 1.26 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.--
CHANNEL CALIBR ATION j 1.27 A CHANNEL CALIBRATION shall be the adjustment,.as necessary, of the channel
- such that it responds with the required range and accuracy to known values of x- = input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip runctions, and may be
, performed by any series of sequential, overlapping or total channel steps such that
. the entire channelis calibrated.
CHANNEL CHECK 1.28 A CHANNEL CHECK shall be the qualitative assessment of channel behavior -
during operation by observation. This determination shallinclude, where possible,-
comparison of the channelindication and/or status with other indications and/or _
. status derived from independent-instrument channels measuring the same . . _ -
parameter.
i CHANNEL FUNCTIONAL TEST i
1.29' A CHANNEL F NCTION AL TEST shall be:
o
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable.to verify OPERABILITY including alarm .
and/or trip functions.
- b. Bistable chan els - the injection of a simulated signalinto the sensor to -
verify OPERABILITY. including alarm interlock and/or trip functions. . ... .
DOSE EQUIVALENT I-131.
1.30 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce.the same thyroid dose as the quantity and isotopic ~ r_.
- mixture of I-131, I-132, I-133,J-134, and-I-135 actually present. The thyroid-dose- ~
conversion factors used for this calculation shall be those listed in Table E-7 of U. S. Regulatory Guide 1.109,'" Calculation of Ahnual Doses to Man from Routine - .
Releases of Reactor Effluent for the Purpose of Evaluating Compliance with-10CFR50, Appendix I," Revision 1, October 1977.
4
~
MEMBER (S) OF THE PUBLIC 1.31 MEMBER (S) OF THE PUBLIC shallinclude all persons who are not occupationally associated with the plant. This category does'not include employees of the ~
utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or'to make deliveries. This category does include persons ~who use portions of the site for recreational,
- occupational or other purposes not associated withthe plant. -
1-Sa T -
w- - ' " -- * -- - - - = '- - = - - + ' '= +-F a-
. OPERABLE - OPER ABILITY 1.32 A system, subsystem, train, component or device shall be OPER ABLE or
.have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary
^
equipment that are requi. red for the system, subsystem, train, component
~
or device to perform ~ifsTunction(s) are also capable of performing their related support function (s).
PURGE-PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RADIOACTIVE WASTE TREATMENT SYSTEMS
~ 1.34 RADIOACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over
~
radioactive materialin order to meet the LCO's set forth in these specifications.
RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION M ANUAL 1.35 A RADIOLOGICAL EFFLUENT MONITORING MANUAL shallbe a manual containing the site and environmental s'afnpling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An OFFSITE DOSE CALCULATION MANUAL shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous end liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the REMODCM are provided in Specification 6.15.
SITE BOUNDARY 1.36 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.
Source Check '
^
l.3 7 - A SOURCE CHECK shall be the qualitative assessment.'of channel response when the channel sensor is exposed to a source of radioactivity.
UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the site boundary' to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive ,
materials or any area within the site boundary used for residential quarters
- or for industrial, commercial, institutional, and/or recreational purposes.
1-5b
,--y. --
VENTING 1.39 VENTING is the controlled process of discharging air or gas from a " '
confinement to maintain temperature, pressure, humidity, concentration or .
other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names,' does.
not imply a VENTING process.
G G
e 1-5c
Figure S M t Exclusion Area Boundary, Site Boundary for Liquid arul_ Gaseous Effluents -
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$staan
site soundary (Exclusion Area) )
Scale: 1 inch equals approx. 850 ft. -
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525 + ACRES '.,$
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! EDUCATION AND MAIN STACK (175 f ht) '
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,! INFORMhT10ll REACTOR ITAINHENT
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%. ronq i.; (*j 1 e #- Release Point i- , j . connecticut atver for Liquid i s.-*= 'or 11 f r h,T- .4 . .a " Effluents i 4 -- -
INTA UCTURE I
Section I Radiological Effluent Monitoring Manual For The Haddam Neck Plant Docket No. 50-213 r
4 ,
t
- TABLE C-1 (Continued)
TABLE NOTATIONS
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may' include radiochemical separation):
LLD = 4.66 Sh i E V 2.72 . Y . exp ( ,\ar) '
I where -
LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
Sb si the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) i 2.22 is the number of transformations per minutes per picocurie l
Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide
.at is the elapsed time between midpoint of sample collection and l midpoint of counting time-It should be recognized that the LLD is defined as an a_ priori (before the fact) limit representing the capability of a measurement system and not as a_ posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and recorded on the analysis sheet for that particular sample.
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
C-3 1
1 L:
TABLE D-1 (Continued)
TABLE NOTATION
- a. The lower limit of detection (LLD) is defined in Table Notation a. of Table C-1.
- b. Samples shall be changed at least once per 7 days and analyses shall be
. completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing. Special sampling and analysis of -
iodine and particulate filters shall also be performed whenever reactor coolant I-131 samples taken 2-6 hours following a THERMAL POWER -
change exceeding 15 percent of RATED THERMAL POWER in one hour show an increase of greater than a factor of 5. These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until the reactor coolant I-131 levels are less than a -
factor of 5 greater than the original coolant levels or until seven days have passed, whichever is shorter. Sample analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. The LLD's may be increased by a factor of 10 for these samples. .
- c. Sampling and ana_ lysis shall also be performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not
' increased more _than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
- d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications.
- e. _ The principal gamma emitters for which the LLD specification will apply are exclusively the following radionucaldes: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, i Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate ;
emissions. The list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the 'above nuclides, shall be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.
- f. When the refueling cavity is flooded, samples shall be taken at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the charging floor-(refueling floor) and analyzed for tritium. The results shall be used along with containment purge flow rates to determine tritium releases.
D-3
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L _ _ _ _ _
m i p_ L . g [j e ;
.e TABLE E-3 (Continued)
TABLE NOTATION ~
3
. a. - The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system'(which may include radiochemical separation): -
LLD = 4.66 56 l
- E
- exp(-M) i where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counter per transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide !
l at is the elapsed time between sample collection'(or end of the i sample collection period) and time of counting '
It should be recognized that the LLD is defined as a_ priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample ~ sizes,' the presence of interfering nuclides, or other uncontrollable circumstances may render these ' a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report,
- b. LLD for leafy vegetables.
- c. Background and onsite well water will not contain the short-lived I-131 isotope. River water is not used as offsite potable water supply and need not be analyzed for I-131.
- d. From end of sample period. E-9