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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] |
Text
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t Pl. ANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations are based NDT P us 600F and are sufficient to prevent l
on a steam generator initial RT brittle fracture.
3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM (Deleted) 3/4.7.4 SERVICE WATER SYSTEM (Deleted) 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANING SYSTEM The operability of the Control Room Emergency Air Cleaning System ensures that occupancy of the Control Room under design basis accident conditions will not result in Control Room personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident (GDC 19, 10CFR50).
3/4.7.6 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10CFR70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
YANKEE-ROWE B 3/4 7-4 Amendment No. 52, 83, 8904210316 890414 PDR ADOCK 05000029 P
PDC
PLANT SYSTEMS l
3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANING LIMITING CONDITION FOR OPERATION 3.7.5 The Control Room Emergency Air Cleaning System shall be OPERABLE.
APPLICABILITY Modes 1, 2, 3, and 4 ACTION a.
With the Control Room Emergency Air Cleaning System inoperable, except as a result of one inoperable fan and motor set, restore the system to OPERABLE status within 3-1/2 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one inoperable fan and motor set, restore the inoperable fan and motor set to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.5.1 At least once per 31 days:
a.
Initiate from the Control Room and maintain for at least 15 minutes, for each fan and motor set, Control Room Emergency Air Cleaning System flow through the HEPA filter and charcoal absorber.
b.
Manually shut down the Control Room unit ventilator, UV-2, from the Control Room and verify closure of the Control Room Emergency Air Cleaning System Isolation Dampers A and B.
4.7.5.2 At least once per 18 months, manually close Control Room Fire Dampers B and E from the Control Room.
4.7.5.3 At least every 18 months and following painting, fire, or chemical release in any ventilation zone communicating with the system, while the system is operating, that could contaminate and impair the function of the HEPA filters or charcoal adsorbers, the Filter System shall be demonstrated OPERABLE by verifying that:
The results of the in-place cold D0P and halogenated hydrocarbon tests a.
at design flows on HEPA and charcoal filter banks shall show 199% DOP removal and 199% halogenated hydrocarbon removal.
b.
Within 31 days after removal that the results of laboratory carbon sample analysis performed at representative system flow rates shall show 199% radioactive methyl iodine removal.
YANKEE-ROWE 3/4 7-18 Amendment Number
PLANT SYSIEMS SURVEILLANCE REOUIREMENJS (continued) c.
Recirculation Filter System flow rate is 3,000 cfm i10% during system operation.
d.
The pressure drop across the combined prefilter and HEPA filter bank is 14 inches H O while operating at the system flows specified above.
2 4.7.5.4 Fal10 wing maintenance or replacement activities, only those components which may have been adversely affected by the activity need be tested. Specifically:
Cold D0P testing shall be performed after each complete or partial a.
replacement of the HEPA filter bank, b.
Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal filter bank.
c.
DOP and halogenated hydrocarbon test shall be performed following any significant modification to the filter housing that could have an adverse effect on the filter efficiency.
d.
An air distribution test demonstrating uniformity within 120%
across the HEPA filters and charcoal adsorbers shall be performed if the filter housing is modified such that air distribution could be adversely affected.
4.7.5.5 The sample analysis of Specification 4.7.5.3.b shall be performed after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.
YANKEE-ROWE 3/4 7-18a Amendment Number
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l Yankee Atomic Electric Company Proposed Change No. 209 ATTACHMENT A BACKGROUND Submitted as part of Reference (b), the proposed Technical Specification change for the Yankee Control Room Emergency Air Cleanup System (CREACS) was rejected by the USNRC in Reference (c). Reference (c) states, "The request reflected operation that was susceptible to single failure and needed to be re-evaluated by the licensee." The following discussion provides our re-evaluation.
DISCUSSION CREACS Re-Evaluation for Single Failure Susceptibility In submitting the CREACS single filter train conceptual design to the USNRC, References (d) and (e), additional provisions were provided to ensure the reliability of the Filter System. These provisions provided for both a quick filter change out capability as well as having on hand an entire filter media reload. Given these additional protisions, the USNRC found the design of Yankee's CREACS to be acceptable, heference (f). The side loading rack design of Yankee's as-built filter train does provide for quick change out of all filter media, particularly the carbon media trays which are used rather than bulk carbon loading. Yankee also maintains in stock one entire reload of certified carbon media trays, carbon test cells, and HEPA filters and prefilters.
However, in submitting the proposed CREACS Technical Specification, Reference (b), the letter could be interpreted to allow the inoperability of the CREACS filter train during normal operation. That is, under the limiting conditions for operation it is stated, "With the passive train (filter unit) of the Control Room Emergency Air Cleaning System inoperable, restore to OPERABLE status within 3-1/2 days or be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." The implied inoperability requires clarification.
The proposed surveillance requirements require that each refueling the filter train be testad to show greater than or equal to 99% DOP removal, greater than or equal to 99% halogenated hydrocarbon removal, and greater than or equal to 99% radioactive methyl iodine removal. Assuming a normal six-week refueling for Yankee, it is possible to remove a carbon test cell early on in the refaeling, and within 31 days perform the laboratory analysis to determine the rac.oactive methyl iodine removal efficiency of the carbon trays.
Following acceptance or replacement of the carbon trays, the DOP and hydrocarbon removal efficiency tests would be performed along with system flow and filter _ _ _ _ _ _ - _ - _ - _ _ - -
Yankee Atomic Electric Company Proposed Change No. 209 ATTACHMENT A (Continued) differential pressure measurements.
This would result in a fully tested.
I fully operable filter prior to the end of the refueling. While this is the desired sequence of events, Yankee recognized the difficulties associated with scheduling the carbon test cell removal at the beginning of each refueling.
During the 1987 Yankee refueling, significant Main Control Board (MCB) rework was performed which required the MCB to be repainted. Accordingly, the carbon test cell was not removed until this painting was complete so as to ensure that the' paint fumes did not degrade the carbon filter media. The carbon test cell was removed, and with the exception of the carbon test cell laboratory analysis, all testing was successfully performed during the last week of the refueling. The results of the carbon test cell analysis, which were received after the
-ant returned to normal operation, showed the methyl iodine removal efficiens, to be 99.4%.
The filter train was, therefore, still deemed operable.
Had the laboratory analysis for methyl iodine removal efficiency shown less than 99% efficiency, the filter train would have been declared inoperable and the action statement of the proposed Technical Specification would have applied. This does not constitute susceptibility to a single failure for the following reasons:
1.
Carbon filters do not degrade catastrophically.. Rather, they exhibit gradual degradations in their efficiency. At Yankee this degradation has been less than 0.2% per refueling interval. A passive filter train is not analogous to active components such as motors or switches which are assumed to either function or not function. The filter train, even though inoperable by definition (less than 99% methyl iodine removal efficiency), would still be a functional component.
2.
Even assuming a degradation of twice the current rate of 0.2% per refueling interval and assuming the worst case, the carbon had tested satisfactorily the previous refueling at the proposed Technical Specification limit of 99.0% methyl iodine removal efficiency, a minimum efficiency of 98.6% would exist. This continues to exceed the assigned activated charcoal decontamination efficiency of 95% and, thus, maintains the conservatism of the Control Room personnel radiation exposure analysis.
3.
Yankee maintains a certified carbon reload in stock. The carbon tray desigr. allows for replacement in less than one hour and would be performed as soon as test personnel who can perform DOP bypass leakage testing are on-site. Replacement would not be performed immediately due _ _ _ _ _ - _ _ _ _ _ _ _ - _ - _ - _ - _ _ _ _ _ _ _ - - - - _ - _ _ _ - _ _ _
I I
g Yankee Atomic Electric Company Proposed Change No. 209 ATTACHMENT A i
(Continued) to the possibility of creating a bypass leakage path. Continuing to operate with the assumed 98.6% efficient carbon media would maintain the conservatism of the Control Room exposure analysis. Changing out the carbon media without the abil# ty to verify bypass leakage could, on the other hand, significantly affect the Control Room exposure analysis.
Therefore, 3-1/2 days were provided for in the proposed change in order to allow for securing the services of testing personnel who would test j
for bypass leakage immediately after the carbon tray replacement.
The proposed change to the Yankee Technical Specification for the CREACS provides for reasonable flexibility in scheduling filter efficiency testing.
It does so while also maintaining the conservatism of the Control Room personnel radiation exposure analysis.
It was not Yankee's intention to infer continued full power operation without the availability of the CREACS filter train, but within the limited context of OPERABLE versus INOPERABLE that implication did result. With the proposed Technical Specification surveillance requirements, the filter train is declared INOPERABLE, and replaced while it can still perform its intended function; i.e.,
it is still a system capable of operating.
It is being. replaced in the time frame specified due to the conservatism built into the surveillance acceptance criteria. With the above clarification, Yankee continues to support the proposed change to the Technical Specification.
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