Proposed Tech Spec Changes Reflecting Installation & Calibr of Condensate Demineralizer Backwash Effluent Monitor RM-L11ML20077D160 |
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Summer |
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Issue date: |
07/22/1983 |
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From: |
SOUTH CAROLINA ELECTRIC & GAS CO. |
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Shared Package |
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ML20077D154 |
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References |
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NUDOCS 8307260399 |
Download: ML20077D160 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen 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Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation ML20078B6121994-10-20020 October 1994 Proposed TS Page,Incorporating Approved Amend 116 & Requested SR Replacement TS Change ML20076J6691994-10-17017 October 1994 Proposed Tech Specs,Reflecting Relocation of Seismic Monitoring Instrumentation Lco,Srs & Associated Tables & Bases in TS Section 3/4.3.3.3 to FSAR or Equivalent Controlled Document ML20073D4111994-09-20020 September 1994 Proposed TS Pages,Including Page 6-16a,revising Rev Level & Date of WCAP-10216-P-A to Reflect Updated Methodology Used in Determining Plant Core Operating Limits ML20149G1301994-09-20020 September 1994 Proposed TS 3/4 5-6 Re Charging Pump Runout Flow Limit ML20071K3761994-07-22022 July 1994 Proposed TS Page 3/4 3-56,reflecting Required Action to Restore One Inoperable Hydrogen Monitor Channel to Operable Status,W/Less than Min Number of Channels Operable ML20070J7561994-07-20020 July 1994 Proposed Tech Specs,Permitting Alternative Equivalent Testing Methods to Be Performed on Diesel Fuel Purchased for EDGs & Changing Rev Level of WCAP-10216-P-A,that Will Be Used to Determine Core Operating Limits for Future Cycles ML20070J7881994-07-20020 July 1994 Proposed TS Pages for TS Tables 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints & 3.3-4, ESFAS Instrumentation Trip Setpoints ML20065B8361994-03-25025 March 1994 Proposed Tech Specs Pages for Missing Page Numbers of TS Pages Submitted in ML20064H9591994-03-11011 March 1994 Proposed TS 4.8.4.1.a.3,deleting Fuses Used as Penetration Overcurrent Protection Devices from SRs & from Bases B 3/4.8.4 ML20064H9251994-03-11011 March 1994 Proposed Tech Specs 3/4.4.9.3,changing AOT for RHR Suction Relief Valves from 7 Days to 72 H ML20064H4501994-03-11011 March 1994 Proposed Tech Specs Re Steam Generator Replacement ML20064G5541994-03-11011 March 1994 Proposed Tech Specs Re Limiting Safety Sys Settings for Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint ML20064C6421994-02-25025 February 1994 Proposed Tech Specs,Incorporating Current Provisions of 10CFR50.36(a)2 Re Semiannual Radioactive Effluent Release Rept to Be Submitted Annually Rather That Semiannually ML20062K6321993-12-13013 December 1993 Proposed Tech Spec Figures 3.9-1 & 3.9-2,permitting Storage of Fuel Assemblies in Regions 2 & 3 of Spent Fuel Storage Racks,Respectively ML20059G2901993-10-29029 October 1993 Proposed Tech Specs Supporting SG Replacement ML20056F7951993-08-24024 August 1993 Proposed Revised TS Re Emergency Feedwater Per 10CFR50.59 ML20045F7771993-06-30030 June 1993 Proposed Tech Specs SR 4.7.1.2 for Performance of Turbine Driven EFW Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig ML20045C3441993-06-16016 June 1993 Proposed Tech Spec 4.7.1.2.a.2 Supporting Request to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig ML20044G7551993-05-25025 May 1993 Proposed Tech Specs Revising Page 3/4 7-4,re Changing TS 4.7.1.2.a.2,to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psi ML20128H9781993-02-12012 February 1993 Proposed TS Modifying Insp Requirements of TS 3/4.4.5 Re SGs & LCO for 3/4.4.6.2 Re Operational Leakage to Establish Interim Plugging Criteria ML20128K1821993-02-10010 February 1993 Proposed Tech Specs Re Main Steam Safety Valves 1999-08-19
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20212H4651999-05-0404 May 1999 Amend 17 to Training & Qualification Plan ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20202C3271998-08-31031 August 1998 Amend 16 to Training & Qualification Plan ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20153F9241998-04-23023 April 1998 Change A,Rev 10 to FEP-1.0, Fire Emergency Procedure Selection ML20153G7081998-03-30030 March 1998 Rev 2 to FEP-4.1, Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire in Control Building ML20153F9691998-03-25025 March 1998 Rev 3 to FEP-3.1, Train B Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire ML20153F9341998-03-23023 March 1998 Rev 3 to FEP-2.0, Train a Plant Shutdown to Hot Standby Due to Fire ML20202G6891998-02-0909 February 1998 Proposed Tech Specs Requesting Removal of Table 4.8-1, Diesel Generator Test Schedule & SR 4.8.1.1.3,Repts ML20203H5741998-02-0505 February 1998 Rev 31,change C to EPP-002, Communication & Notification ML20203H5981998-02-0202 February 1998 Rev 3 to EPP-105, Conduct of Drills & Exercises ML20203H5831998-01-27027 January 1998 Rev 5 to EPP-103, Emergency Equipment Checklist ML20153F9461997-10-22022 October 1997 Rev 2 to FEP-2.1, Train a Shutdown from Hot Standby to Cold Shutdown Due to Fire, Change B ML20153F9511997-10-22022 October 1997 Rev 2 to FEP-3.0, Train B Plant Shutdown to Hot Standby Due to Fire, Change B ML20153F9931997-10-22022 October 1997 Rev 2 to FEP-4.0, Control Room Evacuation Due to Fire, Change D ML20210V2481997-06-30030 June 1997 Amend 15 to Training & Qualification Plan ML20217H3521997-06-16016 June 1997 Amend 14 to, Training & Qualification Plan ML20141K2481997-05-21021 May 1997 Proposed Tech Specs Revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Emergency Safeguards Features Air Handling Units ML20140C1071997-03-26026 March 1997 Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves ML20140C1401997-03-26026 March 1997 Proposed Tech Specs Re Change to Core Alteration Definition ML20140C0641997-03-26026 March 1997 Proposed Tech Specs 3.8.1.1 Re AC Sources - Operating ML20137F8501997-02-0404 February 1997 Change E,Rev 7 to Inservice Testing of Pumps Second Ten Year Interval RC-96-0229, Startup Report for VC Summer Nuclear Station Power Uprate1996-09-23023 September 1996 Startup Report for VC Summer Nuclear Station Power Uprate ML20138H7191996-09-0606 September 1996 Rev 22 to ODCM for VC Summer Nuclear Station ML20134J9741996-06-0505 June 1996 V C Summer Fuel Assembly Insp Program ML20107G3511996-04-16016 April 1996 Proposed Tech Specs 3/4.6 Re Containment Sys,Per App J, Option B ML20138H7141996-03-25025 March 1996 Rev 21 to ODCM for VC Summer Nuclear Station ML20101E6461996-03-19019 March 1996 Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR ML20097F4721996-02-10010 February 1996 Proposed Tech Specs,Revising Testing Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20093F6131995-08-31031 August 1995 Rev 7 to General Test Procedure (Gtp) GTP-301, IST of Pumps Second Ten Yr Interval ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20107L8771995-01-31031 January 1995 Rev 19 to Offsite Dose Calculation Manual ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation 1999-08-19
[Table view] |
Text
- ' '
m g ote TABLE 3.3-12
. rh EO '
g-
=
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION c 88 no ,
i h 9 '
MINIMUM '
g S CilANNELS gg. INSTRUMENT OPERABLE l
ACTION
- 1. GROSS RADI0 ACTIVITY MONITORS.PROVIDING ALARM AND AUTOMATIC -
TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line - RM-L5 or RM L9 1 31 dAf$ @) b. Nuclear (Processed Steam Genera' tor) Blowdown Effluent Line RM-L7 or RM-L9 i 1 -
)2'g .
- c. Steam Generator Blowdown Effluent Line f
, 1. Unprocessed during Power Operation - RM-LIO or RM-L3 1 ; 32 g 2. -Unprocessed during Startup - RM-L3 1 . 32 T "
d ' Turbine Building Sump Effluent Line'- RM- 8 'l 33'
$ change 6d c. .
Condensfe Dernimalsw Mush E0ver* Ine N W .l yp
- 2. FLOW RATE MEASUREMENT DEVICES
- i' a, Liquid Radwaste Effluent Line - Tanks 1 and 2 1/ tank 'l 34
- b. Penstocks Minimum Flow Inter. lock"* 1 34 c.. Nuclear Blowdown Effluent Line
{
1 34
- d. Steam Generator (Unprocessed) Blowdown Effluent Line 1 34
- 3. TANK LEVEL INDICATING DEVICES '
N '
k
- a. Condensate Storage Tank 1 ,35 i M
.p I
[ ^ Flow rate for the monitor RM-L9 is determined by adding flow rates for monitors RM-LE and RM-L7.
P ** Minimum ~ dilution flow.is assured,by an . interlock termi.nating liquid waste releases if tr inimum m dilution flow is not available.
, 9
, y
,l 19 -
.e 9 R. .
S- ,
8* e I G. . a
, g
~
4 INSTRUMENTATION
[i r TABLE 3.3-12 (Continued)
'v' TABLE NOTATION ACTION 31 - With the number of channels OPERABLE.less than required by the A Minimum Channels OPERABLE requirement, effluent releases may V. continue for up to 14 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta and gamma) at a limit of detection of at least 10 7 microcuries/ gram:
p As a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of
'he ~
the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE' requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for. gross radioactivity (beta and gamma) at a limit of detection of at least 10 7 microcuries/ gram.
ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
O 4 O
(d SUMMER - UNIT 1 3/4 3-69
r INSTRUMENTATION TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank to prevent overflow.
Ch1Ay b)
Ac4 ton %- 0% ik nudu d dennels TerO b4 A% O qu, red % w minimum che<nnels OEMBLE recpremed eQ{lvenI releases NY omhnve for up 40 30 des providect h san 9fe I are ancdyard in guardance win spu Mca4 W 4.ti.l.l.1 ad 4. ll .l.5 1 e
e SUMMER - UNIT 1 3/4 3-70 8
t
O O O GD 0 0 O~ .
E TABLE 4.3-8 3
!" RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E.
" CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS
' PROVIDING ALARM AND AUTOMATIC TERMINATION 0F RELEASE
- a. Liquid Radwaste Effluent Line - RM-LS, RM-L9 D P R(3) Q(1)
- b. Nuclear Blowdown Effluent Line - RM-L7 D P R(3) Q(1)
- c. Steam Generator Blowdown Effluent Line - D M R(3) y RM-L3, RM-LIO Q(1)
Y d. Turbine Building Sump d Effluent Line - RM-L8 D M R(3) Q(1) changt 6) G. Condensa4e Deminomhte PedwaA LW rat-lll O g g(3)
- 2. FLOW RATE MEASUREMENT DEVICES N5)
- a. Liquid Radwaste Effluent Line D(4) N.A. R Q
- b. Penstacks Minimum Flow Interlock D(4) N.A. R Q
] c. Nuclear Blowdown Effluent Line 0(4) N.A. R Q
, d. Steam Generator Blowdown D(4) N.A. R Q Effluent Line
- 3. TANK LEVEL INDICATING DEVICES
- a. Condensate Storage Tanks D N.A. R Q i
..j..
-INSTRUMENTATION TABLE 4.3-8 (Continued)
TABLE NOTATION (1) The ANALOG CHANNEL OPERATIONAL. TEST shall also demonstrate that automatic
-isolation of this pathway and control r.oom alarm annunciation occurs if any of the following conditions exists:
l' . Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Loss of Power (alarm 'only). . .
t Instrument indicates a downscale failure (alarm only).
3.
- 4. Instrument controls not set in operate mode.
(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. ' Instrument indicates measured levels .bove the alarm setpoint.
- 2. Loss of Power.
- 3. Instrument indicates a downscale failure.
f
- 4. Instrument controls not set in operate mode. '
( s (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certifiec by the National ~Eureau cf Standards or using standards that have been cbtained f rcm suppliers that participate in reasurement assurance' activities with NES. These standarcs shall permit calicrating the system over its intendec range cf energy and measurement range. For subsequent CHANNEL CALIERATION, sources that have been related to the initial calibration shall be used.
(4) . CHANNEL CHECK shali consist of verifying incication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on wnich continuous, periodic, or batch releases are made. .
shall (j5\'The ANALOG CHANNEL OPERATIONAL
.isolationofthispathwayandSEfm TEg}c'fiS$b,also demons alarm annunciation occurs if any of the following conditions exists: (~
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Loss of Poser (alarm only).
- 3. Instrumer.t indicates a downscale f ailure (alarm only).
4 Instrument controls not set in operate mcde.
3, S OUTH C AROLINA ELECTRIC & GAS COMPANY j' COLUMBIA. SOUTH CAROLINA l ( 07 21 83 ff)W,4 ffQ NO. G5419 PAY '
f5 "f b ' te ' ' ' J' .b ? EDOLLARS $ *****4,000.00*****
F US NUCLEAR REGULATORY COMM ] SOUTH CAROLINA ELECTRIC & GAS COMPANY VCGUM ER NUCLEAR STATION - NSTRUCilON ACCOUNT TO Tnt "o ' "
OFFICE OF CONTROLLER WASHINGTON, DC 20555 h o
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