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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20043E6231990-05-31031 May 1990 Proposed Tech Specs 3.10.3 & 3.10.4 Re Limiting Conditions for Operation ML20034B3071990-04-19019 April 1990 Proposed Tech Specs Re HPSI & LPSI Pump Surveillance Frequency ML20042E2211990-04-12012 April 1990 Proposed Tech Specs,Addressing Administrative Changes ML20006A4651990-01-18018 January 1990 Proposed Tech Specs Re HPSI Throttle & Pressurizer Auxiliary Spray Mods & Surveillance Requirements for ECCS ML20005F1431990-01-0505 January 1990 Proposed Tech Specs Re Instrumentation Sys ML19332D1161989-11-22022 November 1989 Proposed Tech Specs Incorporating Wording from Generic Ltr 84-13 Which Removes Table 3.7.4 Re safety-related Mechanical Snubbers ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20210A5041987-01-29029 January 1987 Proposed Tech Specs Re Extension of Cycle 18 in-core Instrumentation Sys to Cycle 19 ML20213A4431987-01-22022 January 1987 Proposed Tech Specs,Providing Flexibility in Areas Governing Integrity Testing of Steam Generator Tubes ML20215N6281986-10-22022 October 1986 Proposed Tech Spec 4.5.2.b.4,increasing Allowable Open Time for LPSI Min Recirculation Line Valve CS-MOV-532 to 120 Minutes Per Wk ML20197A7611986-10-20020 October 1986 Proposed Tech Specs,Allowing for Performance of 10CFR50.59 Reviews for Future Core Reloads ML20211E8091986-10-0909 October 1986 Proposed Tech Spec Table 4.3-1, Reactor Protective Sys Instrumentation Surveillance Requirements ML20204F7191986-07-31031 July 1986 Proposed Changes to Tech Specs 3.3.3.2,4.2.1.2,4.2.2.1, 4.2.2.2 & 4.2.3.2 Re Operation of in-core Instrumentation Sys ML20211K7501986-06-24024 June 1986 Proposed Changes to Tech Specs to Allow Performance of 10CFR50.59 Reviews for Future Core Reloads ML20151U5571986-02-0505 February 1986 Proposed Tech Specs,Per Generic Ltr 84-43, Reporting Requirements of 10CFR50... & Generic Ltr 85-19, Reporting Requirements on Primary Coolant Iodine Spikes & Supporting LER Sys Mods ML20136J3981986-01-0808 January 1986 Proposed Changes to Tech Spec Table 3.6-1,replacing Manual Containment Isolation Valve W/Blank Flange ML20141G3461986-01-0606 January 1986 Proposed Tech Spec Changes,Permitting Filing of Supplemental Dose & Meteorological Summary Rept within 150 Days of Jan 1 Each Yr ML20138N3131985-10-31031 October 1985 Proposed Tech Spec Changes Per NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitors 1999-04-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20197D4341997-12-31031 December 1997 Rev 1 to Ynps License Termination Plan ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20141F6391997-05-15015 May 1997 License Termination Plan for Yankee Nuclear Power Station ML20198G6381997-02-0707 February 1997 Rev 12 to Ynps Off-Site Dose Calculation Manual ML20138Q5301996-10-31031 October 1996 Rev 11 to Off-Site Dose Calculation Manual ML20198S6131993-12-31031 December 1993 Partially Deleted Rev 9 to Edcr 93-303, Vessel Internals Segmentation Component Removal Program 1995 ML20198S5681993-08-0202 August 1993 Partially Deleted Rev 6 to Edcr 93-303, Reactor Vessel Internals Segmentation Component Removal Program 1993 ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20058D8451990-10-29029 October 1990 Separate Rept Re Local Leak Rate Test Results from Core 19/20 Refueling Outage ML20058D8421990-06-30030 June 1990 June 1990 Reactor Containment Bldg Integrated Leak Rate Test & Periodic Local Leak Rate Tests ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20043E6231990-05-31031 May 1990 Proposed Tech Specs 3.10.3 & 3.10.4 Re Limiting Conditions for Operation ML20034B3071990-04-19019 April 1990 Proposed Tech Specs Re HPSI & LPSI Pump Surveillance Frequency ML20042E2211990-04-12012 April 1990 Proposed Tech Specs,Addressing Administrative Changes ML20006A4651990-01-18018 January 1990 Proposed Tech Specs Re HPSI Throttle & Pressurizer Auxiliary Spray Mods & Surveillance Requirements for ECCS ML20005F1431990-01-0505 January 1990 Proposed Tech Specs Re Instrumentation Sys ML19332D1161989-11-22022 November 1989 Proposed Tech Specs Incorporating Wording from Generic Ltr 84-13 Which Removes Table 3.7.4 Re safety-related Mechanical Snubbers ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20244D3931989-04-11011 April 1989 Core 20 Startup Program for Yankee Nuclear Power Station ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20154L9791988-03-0606 March 1988 Rev 6 to Yankee Nuclear Power Station Offsite Dose Calculation Manual ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses 1999-04-23
[Table view] |
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PHR TECliNICAL SPECIFICATIONS
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS B.
Emergency Air Treatment Systems B.
Emergency Air Treatment Systems 1.
Except as specified in Specification 1.
At least once per operating cycle,.
Q 3.0.B.4 below, circuits of any the following conditions shall be-co emergency air treatment system and demons tra ted.
c the diesel generators required for p.a operation of such circuits shall a.
Pressure drop across the combined p' 94 be operable at all times when liEPA filters and charcoal adsorber C
the systems may be required.
banks is less than 6 inches of water 01 at system design flow rate.
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C b.
Air distribution is uniform within 20% across llEPA filters end Y
charcoal adsorbers.
2.
a.
The results of the in-place cold DOP 2.
a.
The tests and sample analysis of and halogenated hydrocarbon tests at Specification 3.0.B.2 for the post-design flows on HEPA filters and
. accident purge air treatment system charcoal adscrber banks shall show shall be performed initially and 0' :".
>99% 00P removal and >99% halogenated each refueling outage not to exceed hydrocarbon removal. ~
18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following b.
The results of laboratory carbon sample significant painting, fire or f) analysis from the post-accident purge chemical release in any ventilation system carbon shall show >90% radio-zone communicating with the system.
active methyl iodide remolial at a velocity within 20 percent of the b.
The tests and sample analysis of post-accident purge air treatment Specification 3.0.B.2 for the fue.1 system design, 0.15 to G.5 mg/m3 handling air treatment system shall inlet methyl iodide concentration, be performed initially and at least
->95% R. H. and >l90 F.
once per year for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, fire or chemical rele23e in any ventilation zone comunicating with the s'ystem.
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E PWR TECHNICAL SPECIFICATIONS
- 3.0 LIMITING CONDITIONS FOR OPERATION 4.0' SURVEILLANCE REQUIREMENTS c.
The results of laboratory carbon sample c.
The tests and sample analysis ~
analysis from the fuel handling system of Specification 3.0.B.2 for carbon shall show >90% radioactive the in-containment air treatment -
G methyl iodide removal at a velocity
~
system shall be perfomed V
within 20 percent of fuel handling air initially and each refueling treagment system design, 0.05 to 0.15 outage not to exceed 18 months inlet methyl iodide concentration, or af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of systep mg/m
>95% R.H. and >l25 F.
operation and following significa..
painting, fire or chemical release in any ventilation zone commuhicating with-the system.
d.
The results of laboratory carbon sample d.
Cold DOP testing shall be performed -
analysis from the in-containment system -
after each complete or partial carbon shall show >85% radioactive methyl replacement of a llEPA filter bank ~
iodide removal at a velocity within 20 or af ter any structural traintenance percent of in-containment system design, on the system housing.
3 inlet methyl iodide 5 to 15 mg/m concentration, >95% R.H. and >250*F.
O All emergency air treatment system fans e.
Halogenated hydrocarbon testing e.
shall be shown to operate within +10%
shall be performed after each of design flow.
complete or partial replacement g
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of a charcoal adsorber bank or after any structural maintenance on the system housing.
f.
Each circuit shall be operate.d at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
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PHR TECl!NICAL SPECIFTCATIONS r
. p 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLA!!CE itEQUIREMEitTS 3.
Tit otal fuel handling standby
~
3.
~ ' ally-and at least once treatmen tem bypass f, s 071 not-
- year, el handli,
andby exceed 1 percen
-<t e total system air treatment m shall be design flo-e under op dt W old DOP tal co ons.
em bypass of the filter ba Q
o At least once per ope' rating 4.
a.
1 and after the date that one circuit f'
4.
a.
an in-- ntainment air treatment sys is cycle automatic initiation of 6 made or fo to be inoperabl, f any each branch of the emergency "
e reason, reacto eration if permissible air treatment system shall-be ding seven days unless demonstra ted. -
only during the suc c(r sua e operable, such circuit is u'one provided t -
during such se days all b.
At least once per operating
.actijv omponents of the other i ontainment cycle manual operability of the bypass valve for filter
,aW treatment circuit shall be opera q
~
cooling-shall be-demonstrated.
b.
From and af ter the date that one circuit of the post-accident purge air treatment system c.
W.
one circuit of the'i is made or ~ found to be inoperable for any contal nt air trea. nt system.
reason, reactor operation is permissible becomes ino
-the other only during the succeeding thirty days unless circuit si be monstrated O-
such circuit is sooner made operable, provided to ba erable ime J ly and that during such thirty days all active y thereafter.
components of the other post-accident purge p_
air treatment circuit shall be operable.
d.
When one, circuit of the post-accident purge air treatment after the date that the fuel andMrg system becomes inoperable the 5.
a.
r..
i n to be active components in the other. ~
stenL s r3ade m air treatment inoperable for y-reasolr;-4u handling circuit shall be demonstrated o,pf_caMc.
shall be terminated ime - g to be operable immediately and daily thereafter.
b.
If the conditions for the in-containment or post-accident purge air treatment system cannot be met, operations shall be tenninated innadiately and the reactor shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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l PWR TECHNICAL SPECIFICATI0MS_
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Bases
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3.0.B Emergency Air Treatment System The in-containment air treatment system is designed to filter the contai:went building atmosphere during accident conditions.
Both in-containment air treatment systems are designed to automatically start upon
.Q accident signals.
Should one system fail to start, the redundant system is designed to start automatically.
j Each of the two systems has 100 percent capacity.
The fuel handling air treatment system is designed to filter the refueling building atmosphere to the facility vent during refueling conditions.
If the fuel handling air treatment system is on standby, the system is designed to filter the refueling building atmosphere to the facility veht during refueling accident conditions and is automatically started upon @
high radiation signal.
Upon initiation isolation valves in the ventilation system must close to allow air flow through the air treatment system.
If these valves do not close tightly, excessive bypass leakage could occur to negate the usefulness of the HEPA filters and~ charcoal adsorbers to.
reduce potential radiciodine releases to the atmosphere. Therefore, the bypass leakage for the total system has been limited to 1 percent.
High efficiency particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers for all emergency air treatment systems. The charcoal adsorbers are installed to reduce the potential release of radiciodine to the environment.
The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers ar.d a HEPA efficiency of at least 99 percent removal of D0P particulates.
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The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency.
of at least 90 percent on the fuel handling system sample and at least 85 percent on the in-contain-ment system samples for expected accident conditions.
If the efficiencies of the llEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10 CFR 100 guidelines C~
l for the accidents analyzed.
Operation of the fans significantly different from t.he design flow will l
change the removal efficiency of the HEPA filters and charcoal adsorbers.
i Only one of the two in-containment air treatment systems is needed to cleanup the containment building atmosphere during accident conditions.
If one system is found to be inoperable, there is not an immediate threat to the containment system performance and reactor operation may continue while repairs are being made.
If neither circuit is operable, the plant is brought to a condition where the in-containment air treatment system would not be required.
If the fuel handling air treatment system is found to be inoperable, all fuel handling and fuel movement operations will be teminated until the system is made operable.
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PWR TECHNICAL SPECIFICATIONS Bases 4.0.B Emeroency Air Treabnent Systen Pressure drop across the combined HEPA filters and charcoal adsorbers of less,than 6 inches of rater at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts.of foreign matter.
Pressure drop and air distribution should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated.
Tests of the charcoal adsorbers with halogenated hydrocarbon ANSI Ns10.
- Iodine removal efficiency refrigerant shall be performed in accordance withThe charcoal adsorber efficiency test procedures should tests shall follow RDT Standard M-16-lT.
allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtaining at least two samples.
Each sample should be at least two inches in diameter If test results are unacceptable, all adsorbent in and a length equal to the thickness of the bed.
the system shall be replaced with an adsorbent qualified according to Table-1 of Regulatory Guide 1.52.
The replacement tray for the adsorber tray removed for the test should meet the same adsorbent quality.
Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI-N510 Any llEPA filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.520 Operation of the emergency air treatment system cach month for at least ten (10) hours will demonstrate
~
operability of the filters and adsorber system and remove excessive moisture built up on the adsorber.
With the fuel handling standby air treatment system operating, DOP aerosol be adnitted at the refueling,'
Detection of more than 1 percent 00P at the inlet to the facility!
building ventilation system intake.
vent shall be considered an unacceptable test result and the isolation valves repaired to prevent
~
bypass leakage and test repeated.
painting, fire or chemical release occurs such that the HEPA filter or charcoa'l adsorber could become contaminated from the fumes, chemicals or foreign material, the same tests and sample If The determination shall analysis shall be' performed as required for operational use.
Knowledgeable staff members should be cade by the operator on duty at the time of the incident.
be consulted prior to making this determination.
Demonstration of the automatic initiation capability and operability of filter cooling is
~
assure system performance capability. system must be testad daily.
This substantiates the availability of the operable system and thus reactor operation can toatinue for a limited period of time.
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