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
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{{#Wiki_filter:* I)ocument Control LR-N970627 Attachment 3 LCR S97-28 SALEM GENERATING STATION UNIT NO. 1 FACILITY OPERATING LICENSE DPR-70 DOCKET NO. 50-272 CHANGE TO TECHNICAL SPECIFICATIONS MOVABLE CONTROL ASSEMBLIES AND POSITION INDICATION SYSTEMS TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request:
Technical Specification 3/4.1.3.1 3/4 1-18 thru 3/4 1-18a 3/4.1.3.2.1 3/4 1-19 thru 3/4 1-19a In addition, BASES sections B3/4.l.4 and B3/4.2.4 are being revised by this proposed change.
\
- Oocument Control LR-N970627 Attachment 3 LCR 897-28 Insert' A (Page 3/4 1-18)
+/- 18 steps (indicated position) when reactor power is ~ 85% RATED THERMAL POWER, or +/- 12 steps (indicated position) when reactor power is > 85% RATED THERMAL POWER, Insert B (Page 3/4 1-18)
+/- 18 steps (indicated position) at ~85% RATED THERMAL POWER or
+/- 12 steps (indicated position) at >85% RATED THERMAL POWER Insert C (Page 3/4 1-18)
+/- 18 steps (indicated position) at ~85% RATED THERMAL POWER or +/-
12 steps (indicated position) at >85% RATED THERMAL POWER, Insert D (Page 3/4 1-19)
+/- 18 steps at ~85% reactor power or if reactor power is > 85%
RATED THERMAL POWER +/- 12 steps Insert E (Page 3/4 1-19a) 18 steps when reactor power is ~ 85% RATED THERMAL POWER or if reactor power is > 85% RATED.THERMAL POWER, 12 steps
REACTIVITY CONTROL SYSTEMS 3/4 .i .J MOvASU cdhTROL ASSEMBLIES GROUP REtGAf LIMITING CONDITION FOR OPERATION and I
APPllCABILITY: MODES t* and 2*
ACTION:
- a. With one or nar* full length rods 1naperabl* dUe ta being i1111av1bt1 as a result of 1xcess1ve fr1ct1on or 1'9Chanica1 interference or known ta be untrippable, d*term1ne that the SHUTOUWC MARGIN requirenmnt of Specification 3.l.l.l is sat1sf1ed w1th1n 1 hour and be 1n HOT STANDBY within 6 hours. *
- b. wtth nare than one full length rod 1naper1bl1 or m1 s~-~~s;.w...~
tne u ste co er demand position by rare than
- 12 steps (indicated position , be 1n HOT STANDBY within 6 l'IOur
- l
.Y .
- c. wttn one ful 1 length rod inoperable due to Cl!.#S*s other tl'lan -
addressed by ACTION a, above, or nris*aligned from its u step. ~f\il\..CE. witJLt counter Q.emand position by nare tl'lan ! steps ndicated * ~(\SGQ\ \?::>
(JX)s1tionl, PO~R OPERATION may continu* p v t at within one 3 ~ur 1~er: .
- l. The rod is restored ta OPERABLE status within tl'le above al 1gnnwnt requir1mnts, or @e\?\ltlce w iif-i.l.n ~e.ie\ C.
- 2. The r**inder*of the rods 1n the blnk w1th the inoperable rod are 111 pd ta within ! 2 steps of the inoperable rod wni le 11111 nt1i n1ng th* rod quenc. and insertion lilllits of F1gur*s 3.1-1 Ind 3.1-2; the THERMAL PO~R , ....1 Shill be restricted pursuant ta Spec1f1cat1on 3.l.l.S during Jubsequent oper1tion, or
- 3. The rod 1s dlclar*d inoperable Ind the SHUTOO..e MARGIN r1qu1r1l9nt of Spec1f1cation 3.1.1.1 is sat1sf1td. PO~R OPERATION 11111 then a>nt1nue provided that:
~ Special Test Exceptions 3.10.2 and 3.10.3.
SALEM
- UNIT l 3/4 1-18 Amendmnet No. 73
a) A reevaluation of each accident analysis of Table 3.l-l is perfo~l'llld within 5 days; this reevaluation sh~ll confirm that tne previously analyzed results of these accidents remain val id far th* 4'1ration* of operation under these conditions.
b) The SHUTOOwre MARGIN requ1re1111nt of Spec1f1catfon 3.1.l.l is determined at least once i-r 12 hours.
c) A po-.r di strfbut1an 1111p !s obtaf ned from the novabl e 1ncare detectors and Fo(Z) and FIH are var1f1ed to bl within their 11mits *within 7Z hours.
d) Th* THERMAL R>\lER 1ev*l 1s reduced ta less than. or equal ta 751 of RATED THERMAL PO\IER w1tnfn one tour and within the next 4 taurs the high ,.utron* flux trip setpofnt is 1"9ducld ta less than or equal ta ass of RATED THERMAL PO.a. THERMAL PO'° shall be maintained lass than or equal ta 751 of RATED ntERMAL PO\IER unt11 comp11 ana wf th ACTIONS 3 .. 1.3 .l .c .3 .a and 3 .1.3 .l .c .l .c above are dena nstr ated
- e \Ml\\ s e.stl\b\,c.;."i~ tM ~e.. .
SURVEILLANCE RE IRE1'1ENTS \\tM\~lv\~ ON\~\hOll\ fo,.. t/) (S)t.i.o.C 4.1.3.l.2 Each full length rod not fully inserted in the core shall be determined ta be OPERABLE by nove1111nt 01' at least 10 steps in any one direction at least once i-r 31 days.
SALEM
- UNIT l 3/4 l*lSa Amendment Na. 73
REACTIVITY CQNTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR pPERATION 3.l.3.2.l The shutdown and control rod position indication sy*tems shall be OPERABLE and capable of determining the actual and demanded rod positions as follow&:
- a. An61.og ~bd position indicators, within one hour after rod motiqn (allowance for therma.l soak); ()_ I .u_ *t ~
. . tef' r\Ce w i '""' 'J..n~t2. . -
All Shutdown Banks: +/- 12 steps of the group demand counters for withdrawal ranges of steps and 200-228 steps.
- - - - *...,*- Qep\ACe "'\ ~ 1ns.erb J)
Control Bank A:(+/- 12 step~of _the group demand counters for withdrawal ranges of 0-30 steps and 200-228 steps.
_....,...,,.---{r )<Q.\'\M{? w~~ :r(\~rt J:>
Control Bank B:ti 12 stepsjof the group demand counters for withdrawal ranges of 0-30 steps and 160-228 steps.
_ _,,.....-......i;.-~f\l'\Ce l.\H'\t, J:o~A. D Control Banks c and D:(i 12 step)) of the group demand counters for withdrawal range of 0-228 steps.
- b. Group demand counters; :t: 2 steps of the pulsed output of the Slave Cycler Circuit over the withdrawal range of 0-228 steps.
AfiLICABILITX: MODES l and 2.
ACTION:
- a. With. a maximum of one analog rod position indicator per bank inoperable either:
- 1. Determine the position of the non-indicating rod(s) indirectly by the movable incore detectors at least once per 8 hours and within one hour after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or
- 2. Reduce THERMAL POWER to less than SOt of RATED THERMAL POWER within 8 hours.
- b. With two or more analog rod position indicators per bank inoperable, within one hour restore the inoperable rod position indicator(s) to OPERABLE status or be in HOT- STANDBY within the next 6 hours. A maximum of one rod position indicator per bank may remain inoperable following the hour, with Action (a) above being applicable from the original entry time into the LCO.
- c. With a maximum of one group demand position indicator per bank inoperable either:
SALEM - UNIT l 3/4 1-19 Amendment No. 166
I
. l. Verify that al 1 analog rod position indicators for tne
.affected bank are OPERABLE and that the nost withdrawn rod and the l;ast. withdrawn rod of the bank are within a maxi1111m of~ ste~i\\.of eacn other at least once per 8 l'Durs, or
-C.. fu\~ce 11..1 l\li l;\.:,u t E *
- 2. Reduce THERMAL -Al"'R to less than SOI of' RATE.ll THERMAL POltER w1th1 n 8 hours.
- SURVEILLANCE RE qJ IREMENTS *
** ~ l?erl\l\Ce. w\~ \'/\~rt E 4.1.3.2.1.1 Each analog rod position indicator shall be determined to be OPERABLE by ver1fy1 ng that the demand position f nd~catfon system and the rod position 1nd1catian syste11 agrH within ({2 stei!Hallawing far one hour thermal soak after rod notion) at least one. per 12 hours except dur1 ng time intervals when the Rod Fos1t1an Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours.
4.l.3.Z.1.2 Each of the above required rod position fndicator(s) sttall be determ1 ned to be OPERABLE by performance of a CHANNEL cal 1brat1on at least once per 18 nonths.
SALEM - UNIT l 3/4 l-l9a Amendment No. 73
- BIAC'fMTX COBTR.QL SXSTDIS
!!.UBS '
The boron Capability required .below 200"1' i* 91l:ffic.ient to provide a SHOTDOWN DRGIN of lt delta k/Jt after xencm decay *and C'-Cl:'Jldown fran 200°F to 140°F. Thie condition requint* either l,,~00 gallcir:tli of 5-,560 ppm borated water fran tha boric acid storage tanScs or 7. l.OC g!i.::-.:1 cn>i* of 2300 ppm borated water fran the refueling water storage tanJt.
The 37,000 gallon limit in the refuelinq watex .etarage tank for Mode* s and 6 ie based upon 21,210 gallons that is undetectable due to lower tap location, 8,550 gallons for instrument error, 7,100 g~lLon* required for shutdown margin, and an additional 140 gallons due to rounding up.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.Q for the aolution recirculated within containment after a LOCA. 'nlis pH b&nd-.ainimizes the evolution of iodine and minimizes the effect of chloride and cau*tic stre*s corro*ion on mechanical systems and components. The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
The OPERABILITY of one boron injection mystem during RBPOBLING ensures that this syatem ia available for reactivity control while in llJDB 6.
3/4.l.3 tl'YABLi CONTROL A$SIMBLIIS The specifications of this section en*ure that (1) acceptable power distribution limits are maintained, (2) the minimum SHDTDOWR MARGIN is maintained, and (3) limit the potential effects of rod mis-alignment on associated accident analyse*. OPBRABILITY' of the control rod position indicators is required to determin~ control rod positions and thereby ensure compliance with the control rod ali~"'lDent and insertion limits. OPBRABLB condition for the analog rod position indicators is defined LB being capable of indicating rod position to within.;+/- 12 step* of the baiJk demand position for a range of poait1ona. For the Snu *, and Control Ban>t A this range is defined as the group demand counter indicated po*ition between a and 30 steps withdrawn inclusive, and between 200 and 228 step* withdrawn inclusive. 'I1li* permit* the operator to verify that the control rods in these banks are either fully withdrawn or fully in*erted, the normal operating modes for the** bmika. JCnowledge of the*e banks positions in these ranges satisfies all acci~ analymi* ***wnption* concerning their poaition. 'nle range for control Beak B i* dllfined a* the group demand counter indicated position between O alJd 30 *tep* withdrawn inclusive, and between 160 and 228 steps withdrawn incluaive. Por Control Ban>ts C and D the range is defined as the group demand counter indicated position between o and 228 steps withdrawn.
Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (after thermal soak after rod motion) is sufficient verification that the control rods are above the insertion limits. The full out position will be ei;*~i::ifically established for each cycla by the RGload Safety Analysis fer tl:'.at cycle. Thie position will be within the band established by "PULLY WITHDRAWN" and will be administratively controlled. This band is allowable to minimize RCCA wear, pursuant to Information Notice 87-19.
SALEM - ONIT l B 3/4 l-4 Amendment No. 145
*POW£R DtSTRIBUTtON LIM!iS *
- SAS!S 3/4.2.2 and. 3/4.2.3 HEAT Ft.UX ANO NUCLEAR ENTHALPY HOT CAANNa ANO RACIAL PEAKING FACTORS*
F0(Z), F1"~ and Fxy('l)
The 1imits on heat f1ux and nuc1ear enthalpy hot channe1 factors ensure that 1) the design limits on peak loca1 power density and m'lninx.:=
ONBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200~F ECCS acceptance cr1ter1a limit.
Each of these hot channel factors are measurab1e but will no?"'!:l!.lly only be determined periodically as specified 1n Specifications 4.2.2 and 4.2.3. This periodic surveillance is sufficient ta insure that the hot channe1 factor limits are m&intained provided:
. a.
b ..
- c. The cont1"01 rod insertion limits of Specifications 3.1.3.4 a"~
3.1.3.5 are maintained.
- d. The axial power distribution, expressed in t!r.ns of .A.XIAL F1.UX DIFFC'.RENC£, is maintained within the limits.
The relaxation in ~ as a function of nfE?JW. PciWER a11ows changes
!R the radial power shapiHfor all permissible rod insertion limits.
rAH wi11 be maintained within its limits provided conditions a thMJ d acove, are maintained. .
When an F measurement is taken. beth. experimental error and man-ufacturing tol~rance must be allowed for. s: is the appropriate allowance for a fu11 core map taken with the 1ncort detector flux mapping system and When ~ is 3~ is the appropriate allowance for manufacturing tolerance.
measured, experimental en-or iaUst be al1owed for and 4:;
is the appr$~riate allowance for a fu11 cor!N_map taken with the incore detection system. The specifieJ-1imit for r:H also contains an S~
a11~nce for uncertainties which mean that Aonnal operation w111 resu1t iry F"~H !. 1.55/1.0S. The 8~ allowance is based on the following consider~ . .
tions: ~-
SALEM - UNIT 1 B 3/4 2-4 Amendment No.
20
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