Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 ML18102B6081997-10-0606 October 1997 Proposed Tech Specs Revising LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys. ML18102B5571997-08-27027 August 1997 Proposed Tech Specs,Providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, Which States That Three CCW Pumps Required to Meet LCO ML18102B5301997-08-19019 August 1997 Proposed Tech Specs,Providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Salem Unit 2 ML18102B5341997-08-18018 August 1997 Proposed Tech Specs,Incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies ML18102B4891997-08-0101 August 1997 Proposed Tech Specs Section 4.2.1 Rewording Section to State Util Will Adhere to Section 7,Incidental Take Statement Approved by Natl Maring Fisheries Svc ML18102B3911997-06-12012 June 1997 Proposed Tech Specs,Representing Addition of New Spec 3/4.7.10, Chilled Water Sys - Auxiliary Bldg Subsystem. ML18102B3061997-05-14014 May 1997 Proposed Tech Specs,Revising SR 4.7.6.1.d.1,to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & Reflecting Filter Dp Acceptance Value Greater than 2.70 Water Gauge ML18102B2631997-05-0101 May 1997 Proposed Tech Specs,Adding New Spec 3/4.7.10, Chilled Water Sys - Auxiliary Bldg Subsystem. ML18102B2601997-05-0101 May 1997 Proposed Tech Specs 3/4.7.7 Revising Certain Allowed Outage Times & Creating 3/4.7.11 to Address Switchgear & Penetration Area Ventilation Sys ML18102B0341997-04-25025 April 1997 Proposed Tech Specs 3.5.2 Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2 1999-08-25
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 1999-09-10
[Table view] |
Text
3/4.1 REACTIVITY CONTROL SYSTE~S 3/4.1 .1 BORATION CCNT~O(
SHUTDOWN MARGIN - Tavg > 2oo*F LIMITING CONDITION FOR OPERATION Mr/~
3.1.1.1 The SHUTDOWN MARGIN shall be!. 1.61 Ak/k.
APPLICABILITY: MODES 1., a*. 3, and 4.
ACTION:
tVJ{~
With the SHUTDOWN MARG!N < 1.61 Ak/k, i1T111ed1at1ly initiate and continue boration at> 10 gpm of 20,000 ppm boric: acid solution or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMENTS
. Md~
- 4. 1 *1 *1 . 1 The SHUTDOWN MARG IN sha 11 be d1termi ned ta bl !. 1. 6~ .:. I</~:
- a. Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ther11ft1r while the rod(s) is inoperable. If tht inoperable control rod is innovable or untrippable, tht above required SHUTDOWN MARGIN shall be increased by an amount at least equal ta the withdrawn wor-th of the i111novabl1 or untrippable control rod(s).
- b. When in MOOES 1 or 21 , at 111st onct per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank withdraw.1 .is wHhin the limits of Specification 3.1.3.S.
c *. When in MOOE 21", within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is.within the limits of specification 3.1.3.5 .
- See Special Test Exception 3.10. 1
. With "eff !. 1 .a
With Keff < 1.0 SALEM
(
I
~A:_?e~
1~~e '
'~ 7 I~ o.J i()(t(/(
r;,~;~fo Qll ly.
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- d. Prior to initial operation above S~ RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.5.
- e. When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:
- 1. Reactor coolant system boron concentration,
- 2. Control rod position,
- 3. Reactor coolant system average temperature,
- 4. Fuel burnup based on gross thermal energy generation,
- 5. Xenon concentration, and
- 6. Samarium concentration.
4.1. l. l .2 The overal 1. core reactivity balance shall be compared to oredicted values to demonstrate agreement ~ithin + l~ 1k/k at least once per 31 Effective Full Power Days (EFPO). This comparison shall consider at least those factors stated in Specification 4.1.1 .1.1.e, above.
ihe predicted reactivity values shall be adjusted (normalized) to corre-scond to the actual core conditions prior to exceeding a fuel burnup of SO Effective Full Power Days after each fuel loading.
SALEM
TABLE 3.3-4 (Continued\
ACTUATION SYStEH ~NSTRUHENTATION TRIP SETPOINTS 1
ENGINEERED SAFETY--FEATURE
4-..-a..~~~=
c ALLOWABLE VALUES z
-I FUNCTIO"AL UNIT TRIP SETPOJNT
. ~
- 2. CONTAINMENT SPRAY
- a. Manual Initiation Not Appltcable Not Appltcable e
- b. Autollilttc Actuatton Logic Not. ~ppl tcable Not Applicable
- c. Containment Pressure--tttgh-Htgh a-: ps 1g <ff pstg
. 3. CONTAINMENT ISOLATION w
N I
- 1. Manual Not Appltcable Not Appl tcable
~
- 2. From Safety Injection Not Appl kable Not Appl tcable Automatic Actuation logic
- b. Phase NON Isolation .
- 1. Hanua 1 Not Applicable Not Appltcable
- 2. Automatic Actuation logic Not Applicable Not Applicable
- l. -Containment Pressure--High-High ~ ~ psig ~ ~pstg
- c. Containment Ventilation Isolation
@V <f£D
- l. Manual Not Applicable Not Appl tcable
e IAILE J.]*4 CContlnytd)
H
~
toil
... fMICllRIAL Miii EIGllEEBEp SAFETY FEATURE ACIUAIIOI IVIIEI lllTIUIEITAllOI JllP SETPOllTI Illr lllPOIU ALLOMAllE YALUEI Z. Cont1ln*1nt At*oeph1re
, , , Itbh J.J-6 G1e1ou1 l1dte1ctlvlty
- 4. IIEAI Liii llOLAllOI
- b. Auto*ttl~ Actu1tlon Lo1lc lot Appl lc1ble lot Appl lctbh lot Appl I c1bh e
w w
- c. Cont1ln*1nt Pr11eur1**ll1h*ll1h !. ~p1l1 lot Appllc1bl1
!.~**
I ~
- 4. It*** Flow In lMO It*** Lin**** a* funct loo defined ** ~~ct Ion N
!_ defined **
"' ll1h Coincident Mith foll0Me1 A AP corr1epondln1 folloM1: A 4p correepondln1 I1v1 ** LoM*loM or to 401 of full *t*** flow to 441 of full ate** flow It*** line rr1eeur1 ** loM b1tw11n 01 1nd ZOI lo1d ind b1tM11n 01 ind 201 lo1d ind then* AP lncr111ln1 lln11rly then
- 4p lncre1eln1 llne1rlv to
- 4p correepondln1 to 1101 of full *t*** floM 1t 111.51 of full 1te1* flow et fut l lotd. full lo1d.
I l1v1 ?.. UJ*f
?.. 600 p1l1 *t*** line pr111ur1
,,.,, ?.. 541*1
?.. 579 pel1 ate** line pr1eeur1
..r
.g=
N
TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE ITEMS INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- l. Manual
- a. Safety Injection (ECCS) Not Applicable Feedwater I*olation Not Applicable Reactor Trip (SI) Not Applicable containment I*olation-Pha*e "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water Sy*tem Not Applicable Containment Fan Cooler Not Applical:lle
- b. containment Spray Not Applicable Containment !*elation-Ph&** "B" Not Applical:lle Containment Ventilation Isolation Not applicable
- c. Containment Isolation-Ph&** "A" Not Applicable Containment Ventilation Isolation Not Applicable
- d. Steam Lin* I*olation Not Applical:lle
- 2. containment Pr***ure-High
- a. Safety Injection (ECCS) ~27.0(l)
- b. Reactor Trip (from SI) ~2.0 c *. reedwater I*olation ., ~10.0
- d. containment I*olation-Pha** "A" $17.0(2)/27.0(3)
- containment Ventilation I*olation Not Applical:ll*
- f. Auxiliary Feedwater Pump*
$60 ~~
9* Service Water Sy*t*m $13.0(2)/ * (3)
Add: , ,, . Con+..:,,,,,~,,+ .&;" U.krs SALEM - t:NIT l - 3/4 3-2"' Amen~nt No. 132
TABLE J.3-5 IContir.ued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIM!! IN SECONps
- 3. Pressurizer;: P;:es !1!.U:!!-Low
- a. Safety Injection (ECCS) s 21.0< 1 >112.0 12 l
- b. Re-actor Trip (from SI) s 2.0
- c. Feedwater I*olation s 10.0
- d. Containment holation - Pha*e "A" $ 18. 0 ( 2 )
- e. Containment Ventilation I*olation Not Applicable
- f. Auxiliary Feedwater Pump* $ 60 9* Service Water Sy*t*m $ 49.0< 1 >113.0< 2 >
- 4. Differential Pr***ure Between Steam Line*-Hiqh
- Safety Injection (ECCS) $ 12.0< 2 >122.0< 3 >
- b. Reactor Trip (from SI) $ 2.0
- c. Feedwater I*olation s 10.0
- d. containment I*olation - Pha*e "A" $ 17.0< 2 >121.0< 3 >
- Containment Ventilation I*olation Not Applicable
- f. Auxiliary Feedwater Pump* s 60 9* Service Water Sy*t*m s 13.0< 2 >/48.0< 3 >
S. Steam Flow in Two St*1111 Lin** - High Coincident with Tavq -- Low-Low
- a. Safety Injection (ECCS) s 15.75< 2 >;25.75< 3 >
- b. Reactor Trip (from SI) s 5.75
- c. Feedwater I*olation s 15.0
- d. containment I*olation - Pha*e *A* s 20.15< 2 >;30.15< 3 >
- containment Ventilation I*olation ** Applicable
- f. Auxiliary Peedwater Pwnp* s 61.75
- q. Service Water Sy*tem $ 15.75< 2 >;50.15< 3 >
- b. Steam Line I*olation $ 10.75 *
- ~13.75 until r**tart following th* tenth refueling outage.
SALEM - UNIT 1 3/4 3-28 Amendeent No.132
TABLE 3.3-5 (Con~;nuectL ENGINE!RED SAFETY FEATURES RESPONSE TIMJ:S INITIATING SIGNAL ANO FUNCTION RESPONSE TI!q IN SECONDS
- 6. Steam Flow in Iwo Steam Lines-High Coincident with Steam Line Pres1ure-Low
- a. Safety Injection (ECCS) $ 12.0( 2 ) /22.o( 3 l
- b. Reactor Trip (from SI) s 2.0
- c. Feedwater Isolation $ 10.0
- d. Containment I1olation-Pha1e "A" $ l7.0< 21 ;21.0< 3 l
- e. Containment Ventilation I1olation Not Applicablt
- f. Auxiliary Feedwat*r Pump* $ 60
- . S1rvic1 Wat1r Sy1tem $ l4.0< 2 >;4a.0< 3 l
- h. St*&m Line I1olation $ a.o *
- 7. Containrn*nt pre11yre--High-High
- a. Containment Spray
- b. Containmtnt Iaolation-Pha** "&* Not Applic&Dlt
- c. St*&m Line Iaolation $ 7.0 *
~. ~ 49,9
- 8. Stttm G1n1rat9r Wattr Level--High High
- b. reedwater Iaolation $ 10.0
- 9. sieam 99n1r1tor W1t1r L1v1l--L9w-Lgw
- Motor-Driven Auxiliary Ftedwater .,
Pwnp*(4) $ 60.0
- b. Turbine-Driven Auxiliary reedwater Pwnp*(S) $ 60.0
- $10.0 aecond* until r1atart following the tenth refueling out191.
SAI.EH - UNIT l 3/4 3-29 Amen~nt ?lo. 132 I
3/4. 1 REACTIVITY CONTROL SYSTEMS 3/4. 1. 1 BORATION CONTROL SHUTDOWN MARGIN - Tavg > 200°F LIMITING CONDITION FOR OPERATION At/d.* ~
- 3. 1. 1. 1 The SHUTDOWN MARGIN shall be greater than or equal to 1.6% delta k/K.
APPLICABILITY: MODES 1, 2~, 3, and 4.
ACTION: A:rlt/: ~
. \:/!;5:./
With the SHUTDOWN MARGIN less than 1.6% delta k/k, immediately initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 20,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMENTS
- 4. 1. 1. 1. 1 The SH~~ MARGIN shall be determined to be greater than or equal to 1. 6% delta k/k *
- a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable.
If the inoperable control rod is i11111ovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).
- b. When in MODE l or MODE 2 with K greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by veri?~f ng that control bank withdrawal is within the limits of Specification 3. 1.3.5.
- c. When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor cri!ftality by verifying that the predicted criti-cal control rod position is within the limits of Specification 3.1.3.5.
- See Special Test Exception 3. 10. 1 A-Jd.'
SALEM - UNIT 2 3/4 1-1
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- d. Prior to initial operation above ~ RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3. 1.3.5.
- e. Whan in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:
- 1. Reactor coolant system boron concentration,
- 2. Control rod position,
- 3. Reactor coolant systetll average temperature,
- 4. Fuel burnup based on gross therllljll energy generation,
- 5. Xenon concentration, and
- 6. SamariUll concentration~
- 4. 1. l. 1.2 Th* overall core reactivity balance shall be compared to predicted values to d1110nstrate agreement within : lS delta k/k at least once per 31 Effective Full Power Days (EFPO). This comparison shall consider at least those factors stated in Specificativn 4. 1. 1. 1. l.e, above. The predicted reactivity values shall b* adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.
SALEM - UNIT 2 3/4 l-2
~
TABLE 3.3-4 (Continued) r-
!R ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTllltENTATION TRIP SETPOINTS c:
z
.... TRIP SETPOINT ALlflMBLE VALUES
~
FUNCTIONAL UNIT N
- 2. CONTAllllENT SPllAY
- a. Manual Initiation Not Applicable Not Applicable e
- b. Aut.atlc Actuation logic Not Appllcable Not Appllcabl*
- c. Contal1111ent Pre&&ure--Htgh-Hlgh ~@*ta
- 3. CONTAINMENT ISOLATION /5:0 ~**
lb.O w ** Phase *A* Isolation
- 1. Manual Not Applicable Not Applicable N
- 2. frc111 Safety Injection Not Appllcabl* Not Applicable
"' Auto.atlc Actuation logic
- b. Plaas* *a* l&olatlon e
- 1. lllnual Not Appltcabl* llot Appl tcabl*
- 2. Auto.atlc Actuation logic llot Applicable Not. Appllcele
~**
- 3. Contal.-nt Pn11un--Htgb-Hlgb ~~p*ta 16.0
- c. .
Contal1111ent Ventilation l&olatton 15".0
- 1. Manual Not Applicable Not Appltuble
- 2. Aut~ttc Actualton Logtc Nol Appl tcabl* Not Applicable
IAILE ],J-4 <<Continued>
ENGINEEREp SAFEI! fEAIURE ACTUATION SJSIEM INSJBUMEITATIOI TRIP SETPOllTS FUICllOIAL VIII IllP HTPOIU ALLOHAILE VALUES
- 2. Cootaln*ent At*o*phere Per Table J.J-6 Ge5eou1 ladloectlvlty
- 4. STEAM i11E llOLAllOI
- Manual llot Appl I ubh llot Applicable
- b. Auto*atlc Actuation Lo1lc llot Applicable llot Applicable
- c. Conteln**nt Preaeure*-ll9h-Ml1h
~J-' *11
~***
1S:o w d. St*** Flow In Two St*** Linea-- .!. A unction defined **
~
....... 11th Coincident with .!. A iunctlon defined **
~ followe: A 4P correepondln1 followa: A 4P correapondlng w Tev1 *- low-Low or to 401 of full *te** flow I to 441 of full ate** flow tJ St*** Line Preeeure -- low between 01 and 201 load and OI between 01 end 201 lo*d *nd then* 4P lncreeeln1 llneerly then* ~p lncre*alng llneerly to
- 4p correapondlng to 1101 of full *t*** flow et 111.51 of full ate** flow et full load. full loed.
I *v1 ?.. 54J*t T ev1 ?.. 54PF
?.. 600 p*l1 *t*** line ?.. 579 pelt *t*** line preaeure preeaure i::I i=-
rt
.if
.C>
.... w TA3!'...E J. J-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL ANO FUNCTION RESPONSE TIME IN SECONDS
- 1. Manual
- a. Safety Injection (ECCS) Not Applic&Dle Feedwater I*olation Not Applicable Reactor Trip (SI) Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumpa Not Applicable Service Water Sy*tem Not Applicabl1 Containment Fan Cooler Not Applicable
- b. Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Ventilation I*olation Not applicable
- c. Containment I*olation-Phase "A" Not Applicable Containment Ventilation I*olation Not Applicable
- d. Steam Lin* I*olation Not Applicable
- 2. Containm1nt Pr***ure-High
- a. Saf1ty Injection (ECCS) ~ 21.0< 1 >
- b. R1actor Trip (from SI) $ 2.0
- c. F11dwat1r I*olation ~ 10.0
- d. Containment I*olation-Pha** "A" ~ 17.0< 2 >/27.0( 3 )
- containment Ventilation I*olation Not Applica))le t*. Awciliary reedwater Pump* ~ 60 q5.'g) 9* service Water Sy*t*m d 13.0< 2 > /4&re(l)
U,,,fb.;11111 e,,+ J:;.,. Cao/er~
1
'". £:, 'tS:O SALD - UNIT 2 3/4 3-28 Amend.::11nt No. 111
.., ,..,. ~
3.3-5 rcontinuedl ENGIN!!REC SAFETY FEATUBES RESPONSE TIMES INITIATING SIGNl\,L ANQ FUNCTION RESPONSE TIM!! IN SECONDS
- 6. Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure-~ow
- a. Safety Injection (ECCS) s 12.0 12 >;22.01 3 >
- b. Reactor Trip (from SI) s 2.0
- c. Feedwater Isolation s 10.0
- d. Containment Isolation-Phase "A" s 17.0< 2 >;21.0< 3 >
- e. Containment Ventilation I*olation Net Applicable
- f. Auxiliary Feedwater Pump* s 60
- 9. Service Water Sy*tem s 14.0< 2 >;4s.0< 3 >
- h. Steam Line Isolation s 8.0*
- 7. Containment Pre**ure--High-Hiah
- a. Containment Spray Gfi.o) s~
- b. Containment I*clation-Pha*e "B" Not Applicable
- c. Steam Line I*olation s 7.0*
4 CoRcaLnnieR& F*R Cool**
' 40.0
- s. Steam Generator Water tevel--High-Hiqb
- b. Feedwater I*clation s 10.0
- 9. Steam Generator Water Level --Low-Low
- a. Motor-Driven Auxiliary Feedwater s 60.0 Pump*(~)
- b. Turbine-Driven Auxiliary Feedwater Pumpe(S) .,s 60~0
- $10.0 eecond* until re*tart followin9 the *ixth refuelin9 outage.
SAI.&H - UNIT 2 3/4 3-30 Amendment No. 111 I