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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 ML20199A6101997-11-0505 November 1997 Proposed Tech Specs Pages,Updating TS Bases Section 3/4.4.9, to Reflect Results of Revised Analysis That Was Reviewed & Accepted by NRC as Part of License Amends 55 & 44.Analysis Results Not Incorporated Into TS Bases Due to Oversight ML20210T7401997-09-0404 September 1997 Proposed Tech Specs,Revising TS to Allow Use of Elbow Tap Differential Pressure Measurements Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate ML20217M8351997-08-18018 August 1997 Proposed Tech Specs Incorporating Revs to TS 3.7.1.6, Atomospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Mode 1 & 2 ML20210L5801997-08-14014 August 1997 Proposed Tech Specs Allowing Tolerance of RCS Volume Provided in Specification 5.4.2 to Account for SG Tube Plugging ML20198F2211997-08-0505 August 1997 Proposed Tech Specs,Providing Suppl Info Re Amends to Licenses to Convert STP TS to Improved STS Format ML20148G1531997-05-29029 May 1997 Proposed Tech Specs Providing Administrative Changes to Affected Page Re Removal of Surveillance Requirement 4.7.7.e.5 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999 Rev 4 to Severe Weather Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20210J0481999-07-28028 July 1999 STP Unit 1,Cycle 9 Startup Testing Summary Rept ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20209H3151999-06-23023 June 1999 Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20209H3081999-06-0101 June 1999 Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 1999-09-08
[Table view] |
Text
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1 ATTACHMENT 3 ,
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ANNOTATED TECHNICAL SPECIFICATION PAGES :
AND REVISED BASES ;
F I
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9505080004 950427 PDR ADOCK 05000498
,P PDR T90 0%9%4 t7 901 ,
e _ TABLE 3.3-9'(Continued) g '
M REMOTE SHUTDOWN SYSTEM b TOTAL NO. MINIMUM-3 READOUT OF CHANNELS i INSTRUMENT LOCATION CHANNELS OPERABLE.
C
$ 8. Auxiliary Feedwater Flow Rate ASP-QDPS 4-1/ steam 1/ steam generator -
v generator 3 steam generators #
o- 9. Auxiliary Feedwater Storage . ASP-QDPS 3 ~2 m Tank Water Level
- 10. C:re rvD he-eceup'er ?SP-Q0rs ## ^ ther-eceuplc:/-
- r 42 dr nt (DEW RED) w TOTAL NO. MINIMUM.
1 TRANSFER SWITCHES AND TRANSFER SWITCH CONTROLS OF' CHANNELS.
ASSOCIATED CONTROLS LOCATIONS LOCATION CHANNELS OPERABLE
- 1. Steam Generator PORVs ZLP-653 (Train A) ASP 4 2#
ZLP-654 (Train B)
ZLP-655.(Train C) -
ASP (Train D) .
- 2. Reactor Head Vent Throttle ZLP-700 (Train A) ASP 2 1 Valves ZLP-701 (Train B)
- 3. Reactor Head Vent Isolation ZLP-700 (Train A) ASP 2 pair 1 pair Valves ZLP-701 (Train B)
- 4. AFW Pumps and Valves ZLP-653 (Train A-AFW Pump)~ ASP 4 2#.
ZLP-700 (Train A-AFW Valves)
ZLP-654 (Train B-AFW Pump)
ZLP-701 (Train B-AFW Valves)
ZLP-655 (Train C-AFW Pump)
ZLP-709 (Train C-AFW Valves) 2DA ASP (Train D) %R&
~
. R[C o>
w P- 9 3
v, TABLE 3.3-9 (Continued) *
.8 g REMOTE SHUTDOWN SYSTEM h TOTAL NO. MINIMUM
$; TRANSFER SWITCHES AND TRANSFER SWITCH CONTROLS OF CHANNELS
, ASSOCIATED CONTROLS LOCATIONS LOCATION CHANNELS OPERABLE E
M 12. EAB HVAC Fans ZLP-709 (Train C) ZLP-709 (Train C)
- (Continued) ZLP-655 (Train C- ZLP-655 (Train C-
- e. Battery Room and Battery Room
~ Electrical Penetration and Electrical Space Fans) Penetration Space Fans) u, 13. Reactor Containment Fan ZLP-700 (Train A) ZLP-700 (Train A) 6 3 2: Coolers ZLP-701 CTrain B) ZLP-701 (Train B) u, ZLP-709 (Train C) ZLP-709 (Train C) h
- ASP - Auxiliary Shutdown Panel
- QDPS - Qualified Display Processing System
- Must be in the same OPERABLE RCS loop / secondary loop.
-f#A-tota 4--cf 50 thui...;;euples are previded "ith 25 thermacesples e. codi vi iwu i.ra i ri> . Quodi oiii.3 5 ciid -
-O"have 6 UiesmeGGuplCO PCT train COOh. QU0drants a 3nd C e3cp 3;g; ; thg7;gegeple; 33 gn; tr;ja snd 7 thnrmee99nic3 33 th; gthtp tp3jr, Thg. p(ggj3jgg3 gf ,*,CTION b, ;7; ggt gpp]j ggb];- 3; ]Ong gg garh
-quedient has 4 ther;;;;uplc; per trsin OPE"AOLE.
i S@d a n ::
Q Nh
ES a
s- ,.
TABLE 4.3 .
o . REMOTE' SHUTDOWN MONITORING INSTRUMENTATION .
y SURVElLLANCE_ REQUIREMENTS M CHANNEL CHANNEL CALIBRATION'
$ ~ INSTRUMENT CHECK _
[ 1. Neutron Flux - Extended Range 5
g a. Startup Rate M R
[ b. Flux Level M R
- 2. Reactor Trip Breaker Indication M N.A.
- 3. Reactor Coolant Temperature--
Wide _ Range 3 a. Hot Leg M R a b. Cold Leg M R e
- 4. Reactor Coolant Pressure-Wide Range / Extended Range M R
- 5. Pressurizer Water Level M .R 7
- 6. Steam Line Pressure 'M R
- 7. Steam Generator Water Level-Wide Range _ M R-
- 8. Auxiliary Feedwater Flow Rate M R-
- 9. Auxiliary Feedwater Storage Tank Water Level M R
- 10. S n Erit W :;s;cupic3 u o .
[ay
., "s a
~
.. , ,__,, .- ,, -,_..-.--,- . .- -- ..,-.,.. .. .,.-..-. . . . . . . ---. -., . . . . _ . , . , . . . . . . . _ . .w. .. . . _ . , _ _ - . . . _ . - ~ - ..i-________ _ - - . -
~.
TABLE 3.3-10 (continued)_ .
9 .
ACCIDENT HONITORING_ INSTRUMENTATION .
f 3
TOTAL NO. OF MINIMUM CHANNELS OPERABLE ACTION
, INSTRUMENT' CHANNELS
~
5 13. Containment" Water Leve F 2, 1 36 G (Narrow Range) ' "
Containment Water Level (Wide Range) 3- 1 37 3 14
<x t
- 15. Core Exit Thermocouples ** f i th:= ::uple:/ core
- 42 Aua28aC 1/ steam line 1/ steam line 40
- 16. Staam line Radiation Monitor w
'; 17. Containment - High Range Radiation 2 1 39 w Monitor
$ 2* 1*
41
'e
- 18. Reactor Vessel Water Level (RWL) .
1 36
- 19. Neutron Flux (Extended Range) 2 1 36
- 20. Containment Hydrogen Concentration 2
+
Containment Pressure (Extended Range) 2 1 36 21.
- 22. ~ Steam Generator Blowdown Radiation 40 Monitor 1/ blowdown line 1/ blowdown line
- 23. Neutron Flux - Startup Rate 2 1 36 (Extended Range)
- A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or more in the uoper section and three or more in the lower section, are OPERABLE. m cn
- f total of 50 tnermocouples are provided witn a thermocouples on each of two trains. Quadrants 8 and D have 6 thermocouples per train each. Quadrants A and C each have 6 thermocouples on one train ds a >E =5 and 7 thermocouples on the other train. No ACTION is required as long as each quadrant has 4 ^(C
%o>
thermocouples per train OPERABLE. y A ebannel is CPERAEAE if at least b/o core edi- fhermocouples F com c{uadrant are { (> PE e
ed d leosi ore ctuadroM 'hos at leost -rcor orenAnie we<mee oeles. e
}
- -- . . , . - . - - . - ~ - . . .~.. , - . .
~
ST-11L-AE-5079 Attachment 3
- E
, TABLE 3.3-10 (Continued) ,
ACTION STATEMENTS (Continued)
ACTION 39 - a. With the number of OPERABLE channels one less.than the Total Number of Channels requirements, restore one inoperable channel '
to OPERABLE status within 7 days, or be in at least HOT i 5HUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. >
- b. With the number of OPERABLE-channels less than the Minimum Channels Operable requirements, restore at least one inoperable ;
channel 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 t HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 40 - With the number of OPERABLE channels less than the Minimum Channels Operable requirements, restore at least one inoperable channel 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 H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 41 - a. With the number of OPERABLE channels one less than the Required :
Number of Channels, either restore the system to OPERABLE t I
status within 7 days if repairs are feasible without shutting
down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability ,
and the plans and schedule for restoring the system to OPERABLE ;
status,
- b. With the number of OPERABLE Channels one less than the Minimum !
Channels OPERA 9tE in Table 3.3-10, either restore the inoperable ;
channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without sh,utting down o.. ,
i
- 1. Initiate an alternate method of monitoring the reactor i vessel inventory; i Prepare and submit a Special Report to the Commission i 2.
pursuant to Specification 6.9.2 within 30 days following -
the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and L I
- 3. Restore the system to OPERABLE status at the next scheduled refueling.
ouples ACTION 42 per -[With the per quadrant number of OPERABLE train, restore channels.
these thermocou less than 4 the to OPERABLE ;
status within 31 days, or be in at least H
~
UTDOWN within RERNE the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
mTa alSERT
- b. With the number of OPERfdEE channels less than 6 thermocouples per quadrant, restorF these thermocouples to OPERABLE status n &( N be in at least HOT SHUTDOWN witbin the'next SOUTH TEXAS - UNils 1 & 2 3/4 3-71
ST-HL-AE-5079 Attachment 3 Page 6 of 7 INSERT FOR ACTION 42:
- a. With one required channel inoperable, restore the required channel to OPERABLE -
status within 30 days; otherwise, a report shall be prepared and submitted in accordance with Specification 6.9.2 within the next 14 days or as otherwise approved by the Region. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.
- b. With two required channels inoperable, restore one required channel to OPERABLE status within 7 days; otherwise, be in liOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in IIOT SIIUTDOWN in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
3 J
l 1-1 i
m ...i n .
i L-i i
ST-HL-AE-5079 Attachment 3 Page 7 of 7 P
REVISED BASES i 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables '
following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980. The instrumentation listed in Table 3.3-10 corresponds to the Category 1 instrumentation for which selection, design, qualification and display criteria are described in Regulatory Guide 1.97, Revision 2.
Consistent with the requirements of NUREG-0737, an evaluation was made of the minimum number of valid core exit thermocouples necessary for measuring core cooling. The evaluation determined the reduced complement of core exit thermocouples necessary to detect initial core recovery and trend the ensuing core heatup. Based on this evaluation, adequate ,
core cooling is ensured with two valid core exit thermocouple channels per quadrant with two core exit thermocouples per required channel. The core exit thermocouple pair are oriented radially to permit evaluation of core radial decay power distribution. Core exit temperature is ,
used to determine whether to terminate Safety Injection, if still in progress, or to reinitiate Safety injection if it has been stopped. Core exit temperature is also used for unit stabilization and cooldown control.
Two OPERABLE channels of core exit thermocouples are required in each quadrant to provide indication of radial distribution of the coolant temperature rise across representative regions of the core. Two randomly selected thermocouples are not sufficient to meet the two thermocouples per channel requirement in any quadrant. The two thermocouples in each channel must meet the additional requirement that one is located near the center of the core and the other near the core perimeter, such that the pair of core exit thermocouples indicate the radial temperature gradient across their core quadrant. The unit specific response to Item II.F.2 of NUREG-0737 further discusses the core exit thermocouples. Two sets of two thermocouples ensure a single failure will not disable the ability to determine the radial temperature gradient. The subcooling margin monitor requirements are not affected by allowing 2 thermocouples/ channel / quadrant as long as each channel has at least four operable thermocouples in any quadrant (e.g., A Train has four operable thermocouples in one of the quadrants, and C Train has four operable thermocouples in the same quadrant or any other quadrant.). This preserves the ability to withstand a single failure.
TT( 9%90 t 17 001
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