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| OTHER 2 SIT | | OTHER 2 SIT F&D I PCV VALVES PC~......i-------------- -itb. . -Vl *.........._-r-PC~--------------1---Vl~ll-.I OIAROINO PUMPS |
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| ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES April 11, 1990 2 Pages OC0390-0005-NL02 | | ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES April 11, 1990 2 Pages OC0390-0005-NL02 |
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| ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 11, 1990 2 Pages OC0390-0005-NL02 | | ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 11, 1990 2 Pages OC0390-0005-NL02 |
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| TABLE 4.2.1 Minimum Frequencies for. Sampling Tests.' .:.;*1 | | TABLE 4.2.1 Minimum Frequencies for. Sampling Tests.' .:.;*1 |
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| : h. The Low-Pressure Safety Injection Plow* Control Valve CV-3006 shall | | : h. The Low-Pressure Safety Injection Plow* Control Valve CV-3006 shall |
| .be opened and disabled (by isolating the air supply) to prevent spurioua closure. * | | .be opened and disabled (by isolating the air supply) to prevent spurioua closure. * |
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| : i. The Safety Injection bottle motor~operated isolation valves shall be opened with the electric power supply to the valve motor disconnected. | | : i. The Safety Injection bottle motor~operated isolation valves shall be opened with the electric power supply to the valve motor disconnected. |
| : j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open. | | : j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open. |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18066A6641999-09-30030 September 1999 Proposed Tech Specs Re Surveillance Implementation ML18066A6501999-09-17017 September 1999 Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 ML18066A5911999-07-30030 July 1999 Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432 ML18066A5691999-07-19019 July 1999 Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS ML18066A5011999-06-11011 June 1999 Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 ML18068A5851999-05-0303 May 1999 Proposed Tech Specs Section 3.5,converting to ITS ML18066A4551999-04-0707 April 1999 Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1 ML18066A4431999-03-30030 March 1999 Proposed Tech Specs Section 3.7,converting to ITS ML18066A4251999-03-22022 March 1999 Revised TS Pages for ITS Section 3.4 ML20207B2501999-03-0101 March 1999 Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS ML18066A3281998-11-0909 November 1998 Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI ML20154N2901998-10-12012 October 1998 Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs ML20151Z8111998-09-14014 September 1998 Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1 ML18066A3021998-09-14014 September 1998 Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages ML18066A2011998-06-17017 June 1998 Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1801998-03-13013 March 1998 Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A8161998-01-26026 January 1998 Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20 ML18066A4901998-01-20020 January 1998 Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment. ML18067A7071997-10-0101 October 1997 Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12 ML18067A6731997-09-0303 September 1997 Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 ML18067A6001997-06-27027 June 1997 Proposed Tech Specs Revising Electrical Power Systems ML18067A4701997-03-28028 March 1997 Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174 ML20137H5901997-03-27027 March 1997 Proposed Tech Specs Change Request Re Change in Co Name ML18067A4531997-03-26026 March 1997 Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065B0331996-10-25025 October 1996 Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS ML18065B0171996-10-18018 October 1996 Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR ML18065A9551996-10-0202 October 1996 Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves ML18065A9111996-09-0404 September 1996 Proposed Tech Specs 3.7, Electrical Power Systems. ML20117K9581996-09-0303 September 1996 Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments ML18065A8631996-08-14014 August 1996 Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items ML18065A5861996-03-29029 March 1996 Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1 ML18065A4911996-02-0606 February 1996 Proposed Tech Specs Re Removal of cross-train Testing Requirements from LCO Action Statements ML18065A4411996-01-18018 January 1996 Proposed Tech Specs Allowing Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas ML18065A4361996-01-18018 January 1996 Proposed Tech Specs Re Primary Coolant Pump Flywheel Insps ML18065A4111996-01-10010 January 1996 Proposed Tech Specs,Requesting Exemption from 10CFR50 App J & TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3841996-01-0505 January 1996 Proposed Tech Specs,Revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3771995-12-27027 December 1995 Proposed Tech Specs,Rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3481995-12-11011 December 1995 Proposed Tech Specs,Revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 of TS Relocating in CPC Quality Program Description ML18065A3341995-12-0606 December 1995 Proposed Tech Specs,Relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1761995-10-17017 October 1995 Proposed Tech Specs,Changing Pressurizer Cooldown Limit from 100 to 200 F/H,Adding Word Shall to TS 3.1.2c,adding Average Hourly to Column Headings in TS 3.1.2c & Removing Action 3.3.3C from Page 3-31 to 3-30 ML18065A1241995-09-21021 September 1995 Proposed Tech Specs Re Diesel Generator Testing ML18064A8411995-07-0505 July 1995 Proposed Tech Specs,Deleting Section 6.4, Training, & Revising Sections 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7611995-05-0101 May 1995 Proposed Tech Specs Re Requirements for Periodic DG Peak Load Tests ML18064A7331995-04-27027 April 1995 Revised Proposed Ts,Consisting of Changes to Basis in First Paragraph of Page 3-2 & Rev to List of Approved Methodology Repts ML18064A7361995-04-27027 April 1995 Proposed Tech Specs,Supporting Action Statements for Inoperable Safety Valves in Proposed Specs 3.1.7 of TS Change Request of 950103 ML18064A6631995-03-30030 March 1995 Proposed Tech Specs for One Time Surveillance Deferment ML18064A6691995-03-24024 March 1995 Proposed TS Re pressure-temp Limits ML18064A6221995-02-20020 February 1995 Proposed TS Figure 3-4, LTOP Setpoint Limit. 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999 Proposed Tech Specs Re Surveillance Implementation ML18066A6501999-09-17017 September 1999 Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 ML18066A5911999-07-30030 July 1999 Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432 ML18066A5691999-07-19019 July 1999 Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS ML18066A5011999-06-11011 June 1999 Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 ML18068A5851999-05-0303 May 1999 Proposed Tech Specs Section 3.5,converting to ITS ML18066A4551999-04-0707 April 1999 Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1 ML18066A4431999-03-30030 March 1999 Proposed Tech Specs Section 3.7,converting to ITS ML18066A4251999-03-22022 March 1999 Revised TS Pages for ITS Section 3.4 ML20207B2501999-03-0101 March 1999 Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS ML18066A3281998-11-0909 November 1998 Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI ML20154N2901998-10-12012 October 1998 Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs ML18066A3021998-09-14014 September 1998 Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages ML20151Z8111998-09-14014 September 1998 Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1 ML18066A2011998-06-17017 June 1998 Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18066A1841998-06-10010 June 1998 Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period. ML18068A3451998-04-29029 April 1998 Rev 9 to EI-9, Offsite Radiological Monitoring. ML18068A3441998-04-28028 April 1998 Rev 3 to EI-6.6, Gamma E Determination. ML18065B2271998-04-21021 April 1998 Reactor Vessel Neutron Fluence Methodology. ML20217C3101998-03-24024 March 1998 Palisades,Review of Actual Fluence Determination ML18065B1801998-03-13013 March 1998 Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown ML18065B2021998-03-10010 March 1998 Rev 7 to Relocated TS Per GL 89-09. ML18067A8161998-01-26026 January 1998 Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20 ML18066A4901998-01-20020 January 1998 Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment. ML20197G3851997-12-17017 December 1997 Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan ML18065B2321997-10-24024 October 1997 Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment. ML18067A7071997-10-0101 October 1997 Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12 ML18067A6731997-09-0303 September 1997 Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 ML18067A6001997-06-27027 June 1997 Proposed Tech Specs Revising Electrical Power Systems ML18067A4701997-03-28028 March 1997 Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174 ML20137H5901997-03-27027 March 1997 Proposed Tech Specs Change Request Re Change in Co Name ML18067A4531997-03-26026 March 1997 Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18067A5151997-02-11011 February 1997 Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment. ML18065B2011996-12-24024 December 1996 Rev 11 to Offsite Dose Calculation Manual. ML18065B0861996-11-27027 November 1996 Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20. ML20134P4071996-11-19019 November 1996 Suitability,Training & Qualification Plan, Rev 16 ML20137G3871996-10-29029 October 1996 Rev 6 to Relocated TS Per NRC GL 89-09 ML18065B0331996-10-25025 October 1996 Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS ML18065B0171996-10-18018 October 1996 Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR ML18065A9551996-10-0202 October 1996 Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves ML18065A9111996-09-0404 September 1996 Proposed Tech Specs 3.7, Electrical Power Systems. ML20117K9581996-09-0303 September 1996 Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments ML18065A8631996-08-14014 August 1996 Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items ML18065A7661996-06-10010 June 1996 Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys. ML18065A7651996-06-10010 June 1996 Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys. ML18065A5861996-03-29029 March 1996 Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1 ML18065A8021996-02-21021 February 1996 Rev 2 to EM-09-13, ISI Pressure Testing Program. ML20137G3631996-02-16016 February 1996 Rev 10 to Offsite Dose Calculation Manual 1999-09-30
[Table view] |
Text
SIT FILL AND DRAIN I SAMPL*E LINEUP SIRWT
- uo
-1:1!.
llJ .
l>O T-82 T-82 00
~8
._~SAMPLE SINK 0-0 gg
-08~
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CUI
~ ~* *(JI-**;-
I I
I CV-3069
/ i
--.:___J a
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OTHER 2 SIT F&D I PCV VALVES PC~......i-------------- -itb. . -Vl *.........._-r-PC~--------------1---Vl~ll-.I OIAROINO PUMPS
ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES April 11, 1990 2 Pages OC0390-0005-NL02
~ TABLE 4.2.1 M~um Frequencies for Sampling FSAR Section Test Frequency Reference
- 1. Reacior Coolant Gross Activity Deter- 3 Times/7 days with* a None Samples mination maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> be-tween samples (T avg greater than 500°F).
Gross Gamma by Fission Continuous when T avg is None Product Monitor greater thant 500°F(l).
Isotopic analysis 1/14 days during power None for dose equivalent operation I~l31 concentration i
- Radio chemical for 1/6 months (2) None E determination Isotopic analysis a) Once/4 hours, whenever for iodine, including dose equivalent I-131 I-131, 133, 135 exceeds 1.0 µCI/gram, and b) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> follow-ing a thermal power change exceeding 15%
of rated thermal power within a one hour period.
Chemistry (Cl and 02) 3 times/7 days with a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples (T avg greater than 210°F).
Chemistry (Fl) Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.
- 2. Reactor Coolant Boron Concentration Twice/Week None Boron
- 3. SIRW Tank Water Boron Concentration Monthly None Sample
- 4. Concentrated Boron Concentration Monthly None Boric Acid Tanks
- 5. SI Tanks Boron Concentration Monthly 6.1.2
- For T-82A, for the remainder of Cycle 8 but not after I September 30, 1990, following a PCS boron change greater I than 80 ppm below the equivalent hot full power value, I a sample will be taken within one hour. I 4-14 Amendment No. l~. 7<<, tti, OC0390-0005-NL02
3.3 EMERGENCY CORE COOLING SYSTEM Applicability Applies to the operating status of the emergency core cooling system.
Objective To assure operability of equipment required to remove decay heat from the core in either emergency or normal shutdown situations.
Specifications Safety Injection and Shutdown Cooling Systems 3.3.1 The reactor shall not be made critical, except for low-temperature physics tests, unless all of the following conditions are met:
- a. The SIRW tank contains not less than 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm at a temperature not less than 40°F.
- b. All four Safety Injection tanks are operable and pressurized to at least 200 psig with a tank liquid level of at least 186 inches (55.5%) and a maximum level of 198 inches (59%) with a boron *.
concentration of at least 1720 ppm but not more than 2000 ppm. I
- c. One low-pressure Safety Injection pump is operable on each bus.
- d. One high-pressure Safety Injection pump is operable on each bus.
- e. Both shutdown heat exchangers and both component cooling heat exchangers are operable.
- f. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.
- g. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable.
- h. The Low-Pressure Safety Injection Flow Control Valve CV-3006 shall be opened and disabled (by isolating the air supply) to prevent spurious closure.
- i. The Safety Injection bottle motor-operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.
- j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.
- For the remainder of Cycle 8, but not after September 30, 1990, Safety I Injection Tank T-82A is required to have a boron concentration greater than I or equal to the equivalent hot full power primary coolant system boron I concentration, but not to exceed 2000 ppm. I 3-29 Amendment No. 7<<, t~t.
OC0390-0005-NL02
ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 11, 1990 2 Pages OC0390-0005-NL02
TABLE 4.2.1 Minimum Frequencies for. Sampling Tests.' .:.;*1
.r""-* .,, <~*~
FSAR ,
Section -- :: $
Test* Frequency *Reference l* Reactor Coolant Gross Activity Deter- 3 Times/7 days with a None Samples*
- mination maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> be-tween samples (T avg greater than 500°F).
Gross Gamma. by Fission . Continuous when T'avg is None .:
Product Monitor greater thant 500°F(l).
Isotopic analysis 1/14 days during power None for dose equivalent operation*
. I-131 concentration Radio chemical for 1/6 months (2) - None E determination Isotopic analysis a) Once/4 hours, whenever for iodine, including dose equivalent I-131 I-131, 133, 135 exceeds 1.0 µCI/gram, and b) One sauiple between
.2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> follow-ing a thermal power.
change exceeding 15%
of rated thermal power within a one hour period.
Chemistry- (Cl and 02) 3 times/7 days with a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples (T avg greater than 210°F).
Chemistry (Fl) Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.
- 2. Reactor Coolant. Boron Concentration Twice/Week Norte Boron
- 3. SIRW Tank Water Boron Concentration Monthly None
- 4. Concentrated** Boron Concentration Monthly None Boric Acid Tanks
- 6. 1. 2 ~ I
- '. S SI Tanks e..pT~ b.J1.;J Boron* Concentration
.30/ /q?D,1 JJc: .t/ow1rio Monthly For--T-~,:J.A 1 .p.c:n -li.t.. ~e,,,;;~4e~~/~ ~,,, bvT~~-r 4j'r~
.t!t- pr1"'11'1t:v1'1 c.oo/C;rl/..S:~sT~
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Po1WJ c/JPn')c..e_ ~C)..12t>J41 c/h~4~f Pf' :;i q Sa-n/71~ U/ll/. -
- 1. ---1---:* I * - ul . _..,,A )op)- Amendment No. Z0. 11** 11.
p{!_ ./ O/~ e.VI TF-1 'l'1 ..,.,~ * ' March 25, 1988 TSP0987-0155-NL04
- .:[ k::**-~
-~
. .J "****
J * ~-
3.3 EMERGENCY CORE COOLING SYSTEM
~: . '.: .
. _ Applicability ,
. Applies, co. the operacing status of the emergency core cool*ing system.
~--N Objective To ci.ssu*ra* operability of equipment required: to* remove decay heat from
- the core in either emergency or normal shutdown s~tuations.
Specifications*
Safety Injection and Shutdown Cooling System&
- 3. 3. l The reactor shall not be made cr.1tical ~ except for low-temperature physics tests, unless all of the* following conditions are.met:
- a. The SIRW tank contains not less than* 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm. at a temperature not less than_ 40°r. .
- b. All four Safety Injection tanks are operable and pressuriZed to~at
- least 200 psig wit~ a tank liquid level of at least 186 inches .-;:
(55.5%) and a maximum. level of 198 inches (59%) with a boron _*
concentration of at least 1720 ppm but not more than 2000 ppm *.f * .j
- c. One. low-pressure Safety Injection pump is operable. on each bus.
- d. One high-pressure Safety Injection pump is operable on.each bus.
- e. Both shutdown heat* exchangers and both component cooling heat exchanger~_ are operable.
f.* Piping and valve~ shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.
- g. All valves,. pipµig _and interlocks associated with the-above components and required to function during accident conditions are operable.
- h. The Low-Pressure Safety Injection Plow* Control Valve CV-3006 shall
.be opened and disabled (by isolating the air supply) to prevent spurioua closure. *
- i. The Safety Injection bottle motor~operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.
- j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.
-* For<-+h~ 1-~~0l;r'I d V\ a.8- t'.!4d~ g,1 b JIr>'IO\ a¢T".a-i "'S""~T-... b.vJ 3~ f
- 1GJfo.1* S'a<f?"T'1 T...,j,;-r;-~ \°'""'):::. 1-1?.2.l'i ,.s- l--"'i'.S"..:.""d -ro h~
3-29 . Amendment No. 7i, 101_ ,
. . February 10, 1987 . _ :
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- a... b ~ ~ C...:...V, ~-n. ;rl~ D ~eoT..J11 %~ o-., e 't}'-'e l l."o -t-ke~v1v~/lkt7 o1 <f"tJJJ pow-lA, p>--1hYlt:t.114 ~oc\o.:...,j s-11..?}'. b ~- ; - -
TSP1285-03S4;..NL04
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