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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210J1751999-07-30030 July 1999
Marked-up TS Pages for Proposed Changes Re Upper Temp Limit for UHS
ML20209B7411999-06-30030 June 1999
Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20204H9781999-03-23023 March 1999
Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations
ML20204H4291999-03-22022 March 1999
Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6
ML20202G9361999-01-30030 January 1999
Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex
ML20198N3471998-12-29029 December 1998
Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values
ML20198N2041998-12-29029 December 1998
Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements
ML20198K5841998-12-23023 December 1998
Revised Tech Spec Pages 3/4 3-53,3/4 3-53a,6-27 & 6-27a,for Rv LI Sys
ML20198A0811998-12-14014 December 1998
Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys
ML20196G6611998-11-30030 November 1998
Proposed Rev to Improved Tech Specs Section 3.1
ML20196B4101998-11-25025 November 1998
Proposed Tech Specs Facilitating Replacement of 125 Vdc At&T Batteries with New 125 Vdc C&D Batteries While in Mode 1-4
ML20155J2051998-11-0505 November 1998
Proposed TS Converting to Its,Rev R
ML20155J0041998-10-30030 October 1998
Proposed Tech Specs Section 5.6.2, Fuel Storage Drainage, to Identify Sf Pool Level Sufficient to Ensure SRP Acceptance Criteria
ML20154S5011998-10-18018 October 1998
Proposed Rev N to Improved TS Section 3.7
ML20154M5281998-10-15015 October 1998
Revisions K,O & P of 961213 ITS Submittal
ML20154A8881998-10-0202 October 1998
Proposed Rev L to Improved Tech Specs Section 3.8 Closeout
ML20153G4331998-09-25025 September 1998
Revs J & M to Tech Specs Sections 3.6 & 5.0,converting to Improved Tech Specs (Its),Final Closeout Package
ML20153C0351998-08-31031 August 1998
Revs to ODCM for Plant,Including Rev 2 to Chapters 10 & 11, Rev 4 to Chapter 12 and Rev 3 to App F
ML20238F8221998-08-25025 August 1998
Rev 2 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan
ML20236Y5481998-08-0303 August 1998
Rev 1 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan
ML20236W5851998-07-31031 July 1998
Proposed Rev G to Sections 3.1 & 3.2 of Improved Tech Specs
ML20237B6391998-07-30030 July 1998
Proposed Rev H to Section 3.5 of Improved Tech Specs
ML20237E9971998-07-21021 July 1998
Rev I to Proposed Improved Tss,Section 3.9 Re Final Closeout
ML20237B7021998-07-0909 July 1998
Proposed Improved TS (ITS) Section 3.3 Issued as Result of Removing Generic Change Traveler TSTF-135,Rev E from ITS Submittal
ML20236H6531998-07-0202 July 1998
Rev F to 961213 Improved TS Submittal,Containing Final Package Closeout for Improved TS Sections 1.0,2.0 & 3.0
ML20248M1491998-06-0101 June 1998
Proposed Tech Specs Bases Page B 3.8-58b,converting to Improved Tech Specs
ML20248K7361998-05-31031 May 1998
Commonwealth Edison Bnps Unit 1 Cycle 9 Startup Rept
ML20248C5511998-05-29029 May 1998
Proposed Tech Specs Bases Section 3/4.4.4, Relief Valves, Specifically Crediting Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS at Power Accident
ML20217Q8521998-05-0101 May 1998
Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments
ML20216D9431998-04-0909 April 1998
Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66
ML20216C1011998-03-26026 March 1998
Revs to ODCM for Braidwood,Including Rev 1.9 to Chapter 10 & Rev 3 to Chapter 12
ML20217E1891998-03-24024 March 1998
Proposed Tech Specs Surveillance Sections & Bases Allowing Util to Defer 10CFR50,App J,Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999
ML20217B2681998-02-14014 February 1998
Proposed Rev D to ITS
ML20217C3011998-01-31031 January 1998
Rev 0 to Inservice Testing Program Plan Pumps & Valves Braidwood Nuclear Generating Station,Units 1 & 2
ML20198L8131998-01-14014 January 1998
Proposed Tech Specs Pages Revising TS 3.4.8, Specific Activity, Figure 3.4-1,Table 4.4-4 & TS Bases 3.4.8
ML20198L8811998-01-14014 January 1998
Proposed Tech Specs Pages,Revising TS Section 3/4.8.2 & Bases,To Allow Replacement of 125 Volt Dc At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20199J7581997-12-31031 December 1997
Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2
ML20198C3181997-12-30030 December 1997
Proposed Tech Specs 3.7.1.3 Re Condensate Storage Tank
ML20203M5921997-12-17017 December 1997
Proposed Tech Specs,Rev C Changes Improved TSs 3.0,3.3,3.7, 3.8 & 5.0 as Result of Removing Generic Change Traveler TSTF-115 from Improved TS Submittal
ML20203D0361997-12-0909 December 1997
Proposed Tech Specs Pages Correcting Errors Discovered in Current TS W/Regards to Total RCS Volume & Correction to Increase in RCS Volume Associated W/Unit 1 Replacement SGs Accounting for Hot Conditions
ML20199A4751997-11-0707 November 1997
Proposed Tech Specs Pages Revising TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.c & Bases to Allow Performance of 10CFR50 App J,Type a Testing
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20198M2621997-10-31031 October 1997
Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12
ML20217K4461997-10-21021 October 1997
Proposed Tech Specs Re Boron Credit in SFP
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20202F4561997-10-10010 October 1997
Proposed Tech Specs,Deleting Lower Flow Rate Requirement Associated W/Nonaccessible Area Exhaust Filter Plenum & Fuel Handling Bldg Ventilation Sys
ML20211D9421997-09-24024 September 1997
Proposed Tech Specs Revising Allowable Time Interval for Performing Turbine Throttle Valve & Turbine Valve SRs Requirements from Monthly to Quarterly
ML20216H7011997-09-10010 September 1997
Revised Procedures,Including Rev 2 to Bwzp 2000-18, Post- Accident Sampling Sys (Primary Responsibility - Chemistry Director) & Rev 2 to Bwzp 2000-18A1, PASS Sample Collection Procedures
1999-07-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20202G9361999-01-30030 January 1999
Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex
ML20153C0351998-08-31031 August 1998
Revs to ODCM for Plant,Including Rev 2 to Chapters 10 & 11, Rev 4 to Chapter 12 and Rev 3 to App F
ML20238F8221998-08-25025 August 1998
Rev 2 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan
ML20236Y5481998-08-0303 August 1998
Rev 1 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan
ML20217Q8521998-05-0101 May 1998
Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments
ML20216C1011998-03-26026 March 1998
Revs to ODCM for Braidwood,Including Rev 1.9 to Chapter 10 & Rev 3 to Chapter 12
ML20217C3011998-01-31031 January 1998
Rev 0 to Inservice Testing Program Plan Pumps & Valves Braidwood Nuclear Generating Station,Units 1 & 2
ML20199J7581997-12-31031 December 1997
Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20198M2621997-10-31031 October 1997
Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20216H7011997-09-10010 September 1997
Revised Procedures,Including Rev 2 to Bwzp 2000-18, Post- Accident Sampling Sys (Primary Responsibility - Chemistry Director) & Rev 2 to Bwzp 2000-18A1, PASS Sample Collection Procedures
ML20137B9221997-02-28028 February 1997
Revs 1.3 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.4 to Chapter 11, Radiological Environ Monitoring Program & 1.4 to Chapter 12, Radioactive Effluent Technical Standards, Odcm,Byron Annex
ML20137A4961996-12-31031 December 1996
Rev 2 to Odcm,Braidwood Annex,Chapter 12 & App F
ML20116L4691996-08-12012 August 1996
Rev 1 to 1595-00305.30000, Byron Station Units 1 & 2 Second Interval Inservice Insp Program Plan-NRC Submittal
ML20116F3811996-06-30030 June 1996
Rev 1.9 to ODCM, Chapters 11,12 & App F
ML20100Q1761996-03-31031 March 1996
Rev 1.3 to Odcm
ML20134N3051996-03-25025 March 1996
Rev 1 to 10CFR50.59 Se
ML20095J6131995-12-31031 December 1995
Rev 0 of IST Plan Pumps & Valves Byron Nuclear Generating Station Units 1 & 2
ML20095A9071995-10-31031 October 1995
Rev 1.8 to Odcm
ML20129B7051995-09-22022 September 1995
Rev 0 to Byron/Braidwood Units 1 & 2 SG Eddy Current Analysis Guidelines
ML20092B1051995-09-0202 September 1995
Rev 0 to SG Structural Insp Plan in Support of Braidwood 1 & Byron 1 3.0 Volt Ipc
ML20091M8641995-08-25025 August 1995
Verification Analysis for Computer Program
ML20082L5451995-04-18018 April 1995
Rev 3 to ISI Plan for Braidwood Nuclear Generating Station Units 1 & 2 1st Insp Interval
ML20082C9481995-03-14014 March 1995
Rev 7 to IST Program Plan for Pumps & Valves
ML20072R4111994-09-0909 September 1994
Rev 13 to IST Program Plan for Pumps & Valves
ML20076L7461994-08-31031 August 1994
Rev 1.2 to Odcm,Chapters 10,11,12 & App F
ML20072Q1971994-08-29029 August 1994
Proposed Rev 0a to Section 7 of ISI Program Plan for Pressure Testing
ML20083N8701994-07-31031 July 1994
Rev 7 to Byron & Braidwood Stations Units 1 & 2 Eddy Current Analyis Guidelines
ML20064H9101994-03-11011 March 1994
Rev 12 to Section 4.0 of IST Program Plan for Valves
ML20064H9011994-03-11011 March 1994
Rev 10 to Section 3.0 of IST Program Plan for Pumps
ML20063F8721994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Byron Station
ML20063F8961994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Braidwood Station
ML20064N3281993-12-20020 December 1993
Rev 0 to Operating Parameter Uncertainties for Byron/ Braidwood Revised Thermal Design Procedure
ML20056C7441993-06-30030 June 1993
Rev 0.M to ODCM Chapters 10,11 & 12 for Braidwood Station
ML20046C7941993-06-25025 June 1993
Idns Map Monitoring Point Id for Braidwood Station, Tables H & I
ML20062N7851993-03-0101 March 1993
Rev 4.1 to Procedure Bwhp 4006-008, Repairing, Determinating,Terminating,Splicing,Taping,Cable Jacket Repair & Application of Ray Chem Kit on Cable
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20101M2191992-06-25025 June 1992
Rev 5 to Inservice Testing Program Plan for Pumps Braidwood Station Units 1 & 2
ML20098D7431992-05-31031 May 1992
Rev 0.G to ODCM Chapter 11,pages 11.i,11-5,11-6,11-7 & 11-7, Figure 11-3
ML20101B0301992-04-21021 April 1992
Corrected Rev 0.F to Page 11-19 of Chapter 11 of ODCM
ML20090A8541992-02-27027 February 1992
Rev 11 to Section 4.0 of Inservice Testing Program Plan for Valves
ML20090H7651992-02-27027 February 1992
Rev 0.D to Odcm
ML20092F2251992-02-0606 February 1992
Rev O.F to Chapter 11,Pages 11-i,11-7 & 11-17 of ODCM
ML20092J4091992-02-0303 February 1992
Rev 25 to Block Index Procedure Bwzp 600-3A1,App a, Federal Agency Emergency Support Phone List
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20082S8001991-09-0707 September 1991
Rev 54 to 1BWOA PRI-10, Loss of Residual Heat Cooling,Unit 1
1999-04-30
[Table view] |
Text
- - - _ . _ - - - _ . _ _ _. _ _.
't Tt Test Number: ST-1 Revision Number /Date: O. 04/04/89 ATTACHMENT 3 Frequency: _ Annual-A. PURPOSE
.p Q LThe purpose of~this procedure is to verify that the simulator's safety-related valves stroke with an. acceptable time period as required by. ANSI /ANS-3.5-1985.
B. REFERENCES
- 1. ANSI /ANS-3.5-1985: Nuclear Power Plant Simulators for Use in~0perator Training.
- 2. BwVP 200-2T1/3T1: Results of Stroke Timing Test (Braidwood Unit 1).
3.D Braidwood Simulator Initial Certification Report.
- 4. FWR Operations Guideline #12: Simulator Testing Program.
C. ' INITIAL CONDITIONS
- 1. Use the cold shutdown initial condition.
D. DATA COLLECTION
- 1. Attachment A, Velve Stroke Time Comparison Sheet, shall be used to document.
Braidwood Unit One and simulator valve stroke times.
E. TEST INSTRUCTIONS ,
- 1. Obtain the latest set of Braidwood Unit One valve stroke times from BwVP 200-2T1/3T1, Results of Stroke Timing Test (Braidwood Unit 1), and record the
% . stroke times in Attachment A, Valve Stroke Time Comparison Sheet.
- a. BwVP 200-2T1/3T1 is maintained by the In-Service Testing Group at Braidwood Station.
- 2. Stroke each simulator valve listed in Attachment A and record the stroke time to the nearest tenth of a second.
F. ACCEPTANCE CRITERIA
- 1. The simulator's valve stroke time shall be t10% or 12 seconds of the Braidwood Unit One stroke time, whichever is greater.
- 2. The, simulator's valve stroke times shall not exceed the maximum allowable acceptance criteria listed on Attachment A.
G. DOCUMENTATION
- 1. Retain Attachment A which will be used to document simulator compliance.
(
D 887M/1 6/89 OM i
o - _ _ _ _ _ _ _ _ _____ _ _ ______
- t' Test Numbar: ST-1 Revision Number /Date: 0. 04/04/32_
Frequ:ncy: _ _ Ann.u'l
, 7 ^3 ATTACHMENT A t j-
'~~ VALVE STROKE TIME COMPARISON SHEET (Max. Allowed Time) BwVP 200-2/3T1 Simulator System Valve # Acceptance Criteria (sect} U-1 St,roke Time (secs) Siroke Time (secs.)
1 AF 006A < 15 006B < 15 017A < 15 017B < 15 013A < 30 013B < 30 013C < 30 013D < 30 __
013E < 30 013F < 30 013G < 30 013H < 30 CC 9412A <120 9412B <120 9347A < 10 9347B < 10
[s ')/ 9473A 9473B
<120
<120 685 < 10 9413A < 10 9414 < 10 9416 < 10 9438 < 10 CS 001A < 30 001B < 30 007A < 30 007B < 30 009A < 30 009B < 30 019A < 30 019B < 30
%,)
887M/2 6/89
. t. Test Number: ST-1 Revision Number /Date: _L 04/04/89 Frequ:ncy: Annual
.- ' . ATTACHMENT A k
,')
VALVE STROKE TIME COMPARISON SHEET (Max. /silowed Time) BwVP 200-2/3T1 Simulator SyJ12E Valve # Angepigagg_ Criteria (segg} U-1 Stroke Time (sees) Sircle_Ilm d tggl CV 8110 < 10 8111 < 10 8114 < 5 8116 < 5 112B < 10 1120 < 10 112D < 15 .__
112E < 15 8104 < 10 ___
8100 < 10 8105 < 10 8106 < 10 8112 < 10 8152 < 10 8160 < 10 _
8804A < 10 _
,[ FP 010 < 12 v
IN 035A < 6 035B < 6 0350 < 6 '
035D < 6 043A < 6 043B < 6 0430 < 6 043D < 6 009A < 5 009B < 5 _
009C < 5 009D < 5 039A < 6 039B < 6 0390 < 6 039D < 6
,r)
\,.__j '
887M/3 6/89 l
- - 8' Test Numbar: ST-1 Revision Number /Date: 0. 04/04/82_
Frcqu:ncy: _Annel ATTACHMENT A
(~~'x{
V
- VALVE STROKE TIME I COMPARISON SHEET (Max. Allowed Time) BwVP 200-2/3T1 Simulator System Valve # Astrptance criteria (secs) U-1 Stroke Time (secs) Strake Tire (secs) l IA 065 < 15 066 < 15 MS 101A < 6 101B < 6 101C < 6 _
101D < 6 018A < 20 018B < 20 0180 < 20 018D < 20 001A < 5 001B < 5 0010 < 5 001D < 5 ,
- OG 057A < 60
! 079 < 60
\'-} 080 < 60 081 < 60 082 < 60 083 < 60 084 < 60 085 < 60 PR 001A < 4.5 001B < 4.5 066 < 5 PS 228A < 15 228B < 15 . _ _ .
229A < 15 229B < 15 230A < 15 230B < 15 9354A < 10 9354B < 10 9355A < 10 9355B < 10 9356A < 10 9356B < 10 9357A < 10
(~ 9357B < 10
\
887M/4 6/89 I
_ _ -. _ _ _ _ _ -. ___________________-____a
'+' Test Number: ST-1 Rsvision Humber/Date: 0. 04/04/89 FrequIncy: Annual =
'W' ATTACHMENT A m L: VALVE STROKE TIME
- , COMPARISON SHEET
. (Max. Allowed Time) BwVP'200-2/3T1 Simulator SYSI.?B .L Valve # h ytance Criteria (secs) 11-1 Stroke Time (sees) Stroke Time (secs)
RC- 014A'- 1 0 014B < 2 0140'- < 2 014D, < 2 RE 9157. -<30 9159A < 10-
>9159B <, 10 9160A < 10 9160B <'10
'9170 < 10 1003 ( 10 RF 026 ( 15 ^ '
027 < 15 O ' RH 8701A 8701B'
'8702A (120 (120-
<120 8702B (120
. RY 455A' < 2.5 456: < 2.5 ._
8000A < 10 8000B < 10 8025 < 10 8026 < 10 8028 < 10 8033 < 10 SA 032 < 4.5 033 < 4.5 O 887M/5 6/89
m .c - ,
/ Tzat Numbrr: ST-1 Rsvision Number /Date: __0. 04/04/89_
Frequ;ncy: .. Annual
?:
,-m ATTACHMENT A i
l
' VALVE STROKE TIME COMPARISON SHEET
. (Max. Allowed Time) BwVP 200-2/3Tl Simulator SJf t.tm Valve # Arceptance Criteria (secsl U-1 Stroke Time (secs) Stroke Time (secs}
SD 002A < -7.5 002B < 7.5 0020 < 7.5 002D < 7.5 002E < 7.5 002F < 7.5 _
002G < 7.5 _
002H < 7.5 005A < 3 005B < 3 _
005C < 3 005D <- 3 SI 8811A <120 '
8811E (120 8804B < 10 ___
(~N < 15
(,) 8807A 8807B < 15 8812A < 15 8812B < 15 8814 < 10 8821A < 10 _
8821B < 10 ..
8920. < 10 __.
8924 < 15 .
8830 < 15 _
8838 < 15 8871 < 15 _ _ _
8964 < 15 __. _
8801A < 10 __
88013 < IC . ._
8302A < 10 _ _
8802B < 10 _ . _ . _.
830c < 15 . .
9909A < *LD _._
8809B e 10 -_ - . _ _ _ . . . _
8813 < 10 . _ _ . _ _ _ . - . -
8835 < 10 __. - _ . _ _ _ . . . .
8860 < 15 -
, .l i
v) 887M/6 6/89
. Test; Number: ST-1 ' _
Revision Number /Date: 0.-04/04/89 l '
Frequency: ' Annual:-
M ATTACHMENT A
- (
VALVE' STROKE TIME.
COMPARISON SHEET
.(Max. Allowed Time) BwVP-200-2/3T1 Simulator System - '17alve'#' Acceptance Criteria (secs)' U-l'Str2 ke Time (secs) Stroke Time (secs)-
SX 016A <.15 016B:. < 15 027A < 15 027Bl < 15.
112A. < 6 112B < '6 114A <6 ._
114B < 6 169A < 20-169B < 20 VQ 001A < 5 001B . <-5 002A < 5 002B < 5 -
003- ( 5 f 004A < 5
-* 004B < 5 005A <5 005B < 5
.005C < 5 WO 006A < 50 006B < 50 .
020A. < 50 020B < $0 ._,
.056A < 50 _
056B < 50 .
. . r% -
887M/7 6/89
- - - _ - - _ _ _ _ _ _ - - . . _ - _ - __ - - . _ - _ - x