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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability ML20078A7731994-06-24024 June 1994 Proposed Tech Specs Reflecting Removal of Recirculation Flow Scram ML20069M8231994-06-15015 June 1994 Proposed Tech Spec 2.3.D, Reactor High Pressure,Relief Valve Initiation ML20070R5261994-05-12012 May 1994 Proposed TS Sections 3.1 & 4.1 for Protective Instrumentation ML20029E0451994-05-0606 May 1994 Proposed Tech Specs Clarifying Requirements for Demonstrating Shutdown Margin ML20065M9991994-04-19019 April 1994 Proposed Tech Specs Updating & Clarifying TS 3.4.B.1 to Be Consistent W/Existing TS 1.39 & 4.3.D Re Five Electromatic Relief Valves Pressure Relief Function Inoperable or Bypassed During Sys Pressure Testing ML20029C7571994-04-15015 April 1994 Proposed TS Change Request 215,deleting Audit Program Frequency Requirements from TS 6.5.3 & Utilize Operational QA Plan as Controlling Document 1999-07-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20198H4831998-08-13013 August 1998 Rev 1 to Procedure 5000-ADM-7350.06 (EMP-002), Modifications ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20198J8831997-09-10010 September 1997 Rev 8 to Procedure 5000-ADM-7311.02 (EP-009), Design Verification ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing 1999-09-05
[Table view] |
Text
_... - - - -. -.. - - - - -
^
TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIREMENTS Reactor Modes Min. No. of Min. No. of in which Function OPERABLE or Instrument Must Be OPERABLE OPERATING Channels Per Trip
[ tripped]
OPERABLE Action Function Setting Shutdown Refuel Startuo Run Trio Systems Trio System ' Reauired*
D. Core Soray Consider the respective
- 1. Low-Low X(t)
X(t)
X(t)
X 2
2(pp)'
core spray Reactor Water Level loop inoperable,
- 2. High Drywell 5 3.5 psig X(t)
X(t)
X(t) X 2(k) 2(k)(pp) and comply Pressure with Spec. 3.4 1
- 3. Low Reactor 2 285 psig X(t)
X(t)
X(t)
X 2
2(pp)
Pressure (valve permissive)
E. Containment Sprav Comply with Technical Specification 3.4 F. Primary Containment Isolation
- 1. High Drywell 5 3.5 psig X(u)
X(u)
X(u) X 2(k) 2(k)(oo) Isolate 1
Pressure containment or PLACE IN
- 2. Low-Low 2 7'2" above X(u)
X(u)
X(u) X 2
2(oo)
COLD SHUT-Reactor Water TOP OF DOWN Level ACTIVE FUEL CONDITION G. Automatic Depressurization
- 1. High Drywell
< 3.5 psig X(v)
X(v)
X(v) X 2(k) 2(k)
See note h.
Pressure i
- 2. Low-Low-Low 2 4'8" above X(v)
X(v)
X(v) X 2
2 See note h.
Reactor Water TOP OF Level ACTIVE FUEL
- 3. Core Spray Booster Pump d/p Permissives: > 21.2 psid X(v)
X(v)
X(v) X note i.
note i.
See note i.
I OYSTER CREEK 3.1-11 Amendment No.: 44, 79,112,160,171 Change 4; Correction: 5/l1/84 9610230202 961010 PDR ADOCK 05000219 P
PDR
..__m TABLE 3.1.1 (CONT'D)
Action required when minimum conditions for operation are not satisfied. Also permissible to trip inoperable trip system. A channel may be placed in an inoperable status for up to six hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE instmment channel in the same trip system is monitoring that parameter.
See Specification 2.3 for Limiting Safety System Settings.
Notes:
Permissible to bypass, with control rod block, for reactor protection system reset in REFUEL MODE.
a.
b.
Permissible to bypass below 800 psia in REFUEL and STARTUP MODES.
One (1) APRM in each OPERABLE trip system may be bypassed or inoperable provided the c.
requirements of Specification 3.1.C and 3.10.C are satisfied. Two APRMs in the same quadrant shall not be concurrently bypassed except as noted below or permitted by note.
Any one APRM may be removed from service for up to six hours for test or calibration without inserting trips in its trip system only if the remaining OPERABLE APRMs meet the requirements of Specification 3.1.B.1 and no control rods are moved outward during the calibration or test. During this short period, the requirements of Specifications 3.1.B.2,3.1.C and 3.10.C need not be met.
d.
The IRMs shall be inserted and OPERABLE until the APRMs are OPERABLE and reading at least 2/150 full scale.
j Offgas system isolation trip set at $2.1/5 Ci/sec where E = averag, gamma energy from noble gas in e.
offgas after holdup line (Mev). Air ejector isolation valve closure time delay shall not exceed 15 minutes.
f.
Unless SRM chambers are fully inserted.
g.
Not applicable when IRM on lowest range.
h.
With one or more instrument channel (s) inoperable in one ADS trip system, place the relay contact (s) for the inoperable initiation signal in the tripped condition within 4 days, or declare ADS inoperable and take the action required by Specification 3.4.B.3.
With one or more instrument channel (s) inoperable in both ADS trip systems, restore ADS initiation capability in at least one trip system within I hour, or declare ADS inoperable and take the action required by Specification 3.4.B.3.
Relief valve controllers shall not be bypassed for any more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (total time for all controllers) in any 30-day period and only one relief valve controller may be bypassed at a time.
OYSTER CREEK 3.1-16 Amendment No.: 75,108,110,171
TABLE 3.1.1 (CONT'D) i.
With two core spray systems OPERABLE:
1.
A maximum of two core spray booster pump differential pressure (d/p) switches may be inoperable provided that the switches are in opposing ADS trip systems
[i.e., only: either RV-40 A&D or RV-40 B&Cl. Place the relay contacts associated with the inoperable d/p switch (es) in the de-energized position, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Restore the inoperable d/p switch (es) within 8 days, or declare ADS inoperable and take the action required by Specification 3.4.B.3; or, 2.
If two inoperable d/p switches are in the same ADS trip system [i.e., RV-40 A&B or RV-40 C&Dl, place the relay contacts associated with the inoperable d/p switch (es) in the de-energized position, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the inoperable d/p switches within 4 days, or declare ADS inoperable and take the action required by Specification 3.4.B.3.
With only one core spray system OPERABLE:
If one or more d/p switches become inoperable in the OPERABLE core spray system, declare ADS inoperable and take the action required by Specification 3.4.B.3.
j.
Not required below 40% of turbine rated steam flow.
}
1
?
4 i
i OYSTER CREEK 3.1-16a Amendment No.: 184
TABLE 4.1.1 (cont'd) a Instrument Channel Check Calibrate Test Remarks (Apply to Test & Calibration)
- 29. Drywellliigh N/A Each re-Each re-Radiation fueling fueling outage outage
- 30. Automatic Scram N/A N/A 1/wk Note 1 Contactors
- 31. Core Spray Booster Pump Differential Pressure N/A 1/3 mo 1/3 mo By application of a test pressure
' Calibrate prior to startup and normal shutdown and thereafter check 1/s and test 1/wk until no longer required.
LEGEND: N/A = Not Applicable; 1/s = Once per shift; 1/d = Once per day; 1/3d = Once per 3 days; 1/wk := Once per week; l/mo = Once per month; 1/3 mo = Once every 3 months; l/20 mo = Once every 20 months; 1/24 mo = Once every 24 months Note 1:
Each automatic scram contactor is required to be tested at least once per week. When not tested by other means, the weekly test can be performed by using the subchannel test switches.
Note 2:
At least daily during reactor POWER OPERATION, the reactor neutron flux peaking factor shall be estimated and flow-referenced APRM scram and rod block settings shall be adjusted, if necessary, as specified in Section 2.3 Specifications A.1 and A.2.
Note 3:
Calibrate electronic bistable trips by injection of an external test current once per 3 months.
Calibrate transmitters by application of test pressure once per 12 months.
The following notes are only for item 15 of Table 4.1.1:
A channel may be taken out of service for the purpose of a check, calibration, test or maintenance without declaring the channel to be inoperable.
a.
The Channel Test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1) Instrument indicates measured levels above the alarm setpoint.
- 2) Instrument indicates a downscale failure.
- 3) Instrument controls not set in operate mode.
- 4) Instrument electrical power loss.
OYSTER CREEK 4.1-6 Amendment No.: 63,80,108,116,141,152, 171; Changes: 5,7