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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
,_
REACTIVITY. sst AOL' SYSTEMS p
BORATED WATER SOURCES - SHUTDOWN LigjTING CONDITION FOR OPERATION 3.1.2.10 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
The boric acid mix tank and associated heat tracing with:
4 1.
A minimum contained borated water volume of 1500 gallons, equivalent to a tank level 13.6 feet, 2.
12 to 12.5% by weight boric acid solution, and 3.
A minimum solution temperature of 150'F.
b.
The safety injection tank (SIT) with:
1.
A minimum contained borated water volume equivalent to a tank level of 225.5 feet, 2.
A minimum boron concentration of 2200 ppm, and 3.
A minimum solution temperature of 40*F.
APPLICABILITY: MODE 5.
ACTION:
With no borated water source OPERABLE, suspend all operations involving positive reactivity changes until at least one borated water source is restored to OPERABLE status.
SURVEILLANCE REOUIREMENTS
- 4.1.2.10 The above required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration of the safety injec-tion tank water or the boric acid concentration of the l
boric acid mix tank water.
2.
Verifying the contained borated water volume of the tank,-
and l
l
- YANKEE-ROWE 3/4 1-19 Amendment No. #9 9007060269 900623 PDR ADOCK 05000029 p
PDC
c, 1
p+
, REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING-LIMITING CONDITION FOR OPERATION 3.1.2.11 Each of the following borated water sources shall be OPERABLE:
a.
The boric acid mix tank and associated heat tracing with:
1.
A minimum contained borated water volume of 1500 gallons, equivalent to a tank level of 13.6 feet, 2.
12 to 12.5% by weight boric acid solution, 3.
A minimum solution tempel.ture of 150'F.
b.
The safety injection tank (SIT) with:
1.
A minimum contained borated water volume equivalent to a tank level of 125.5 feet, 2.
A minimum boron concentration of 2200 ppm, and 3.
A solution temperature of 120*F to 130'F.
I APPLICABILITY: MODES 1, 2, 3 and 4.
' ACTION:
With'either the boric acid mix tank or the safety injection tank inoperable, provided the other required source'is OPERABLE, restore the inoperable tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 borated to a SHUTDOWN MARGIN (all control rods inserted) equivalent to'at least-
.5% Ak/k at 200*F; restore the inoperable tank to OPERABLE status
,l' within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.-
SURVEILLANCE REQUIREMENTS 4.1.2.11 Each borated water source shall be demonstrated OPERABLE:
l 1
YANKEE-ROWE 3/4 1-21 Amendment No. 49, 92 l
l i
e
- .c
'o.
3'.
LyERGENCY CORE COOLING SYSTEMS SAFETY INJECTION TANK l
LIMITING CONDITION FOR OPERATION I
3.5.4 The safety injection tank (SIT) shall be OPERABLE with:
a.
A minimum contained borated water volume equivalent to a level of 125.5 feet.
b.
A minimum boron concentration of 2200 ppm, and c.
A water temperature of 120'F to 130'F.
.\\
APPLICABILITY: MODES 1, 2, 3, 4* and 5*
ACTION:
With the safety injection tank inoperable, restore the tank to OPERABLE
~
status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and'in 110T SHUTDOWN with main coolant pressure <300 psig within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t SURVEILLANCE REOUIREMENTS 4.5.4 The SIT shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the cor tained borated water-volume in the tank, and 2.
Verifying the boron concentration of the water, b.
At least'once pe'. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the SIT temperature.
1
.J
- Main coolant pressure 1300 psig.
l YANKEE-ROWE 3/4 5-12 Amendment No. #9, 59, 92
'e
g
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\\
t
- .1,
,_EMERCENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
With-the Main Coolant System temperature and pressure below 330'F, and 1000 psig, respectively, one OPERABLE ECCS safety injection subsystem, with the OPERABLE recirculation subsystem and the OPERABLE long term hot leg injection subsystem, is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor, the decreased probability of a LOCA and'the limited core cooling requirements because of the negligible energy stored in the primary coolant under these conditions.
i The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that, at a minimum, the assumptions used in-the safety anclyses are met and that subsystem OPERABILITY is maintained.
g Complete system tests cannot be performed when the reactor is operating because of their inter-relatioa with operating systems. The method of assuring operability of these systems is a combination of complete system tests performed during refueling shutdowns and monthly tests of active system components (pumps and valves) during reactor operation. The test interval is based on the judgement that more frequent testing would not significantly increase reliability.
Some subsystems power operated valves fail to meet single failure criteria and removal of power to these valves is required.
In order to eliminate potential for reactor vessel low temperature overpressurization by the inadvertent-operatJ~1 of ECCS pumps,-the pump circuit breakers are opened and locked in the racked-out position or removed from the breaker cubicles. Also selected SIS isolation valves are positioned to remove the possibility of an overpressurization event during that portion of MCS heatup and cooldown when an inadvertent injection could result in an overpressure event.
3/4.5.4 SAFETY INJECTION TANK The OPERABILITY of the Safety Injection Tank (SIT) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on SIT minimum level and l
boron concentration ensure that - 1) suf ficient water is available within L
containment to permit recirculation cooling flow to the core, and 2) the reactor will remain suberitical in the cold condition f ollowing mixing of the SIT and the Main Coolant System water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses, which is based on allowing a minimum I
of 77,000 gallons to be injected by the safety injection subsystems before
,the recirculation is manually established.
LOCA analyses show that an injection of 77,000 gallons is sufficient to limit core temperatures and containment pressure for the full spectrum of pipe ruptures This leaves up to 52,000 gallons in the SIT ss reserve.
The boron concentration of l
2200 ppm is the highest value assumed in any accident analysis.
The SIT i
water temperature of 120'F to 130'F ensures that the reactor vessel is not L
subjected to conditions that could exceed the NDT provisions of the ASME Code af ter a severe transient.
YANKEE-ROWE'
,B 3/4 5-2 Amendment No. 52, 59, 92, XXX
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