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] |
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Document Control LR-N970543 Attachment 3 LCR S97-19 SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 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-75 are affected by this change request:
Technical Specification 3/4.1.3.l 3/4 1-13 thru 3/4 1-14 3/4.1.3.2.1 3/4 1-16 thru 3/4 l-16a In addition, BASES sections B3/4.l.3 and B3/4.2.2 are being revised by this proposed change.
9708250372 970819 PDR ADOCK 05000311 p PDR
Document Control LR-N970543 Attachment 3 LCR 897-19 Insert A (Page 3/4 1-13)
+/- 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 1-13)
+/- 18 steps (indicated position) at ~85% RATED THERMAL POWER or
+/- 12 steps (indicated position) at >85% RATED THERMAL POWER Insert C (Page 3/4 1-13)
+/- 18 steps (indicated position) at ~85% RATED THERMAL POWER or +/-
12 steps (indicated position) at >85% RATED THERMAL POWER, Insert D (Page 3/4 1-16)
+/- 18 steps at ~85% reactor power or if reactor power is > 85%
RATED THERMAL POWER +/- 12 steps Insert E (Page 3/4 1-16a) 18 steps when reactor power is ~ 85% RATED THERMAL POWER or if reactor power is > 85% RATED THERMAL POWER, 12 steps
REACTIVITY CONTROL SYSTEMS
~4.i.3 MOVABLE CONTROL ASSEMBLIES OUP HEIGHT ..
L1M1TING~ON01TION FOR OPERATION 3.l.3.l All full length (shutdown and control rods, shall be OPERABLE and positioned w1thi + steps indicated sitfon) f their group step counter demand posit on w t l'Dur a ter rod notion.
APPLICABILITY: MODES l* and 2*
ACTION:
- a. wt th one or nore ful 1 length. rods inoperable due ta be1 ng irmovable as a result of excessive friction or ITl!chanical interference or known ta be untrippable, determine that the SHUTOO~ MARGIN requirel!'l!nt of Specification 3.l.l.l is sati~fied within 1 ht)ur and be ; n HUT STANDS Y w1thi n 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
£.E.PIl4t1:.
w1'f(, ~ERT61
- b. wtth nore than one ful 1 length rod inoperable or m1s~om /
the group step counter demand position by lll)re than~
- Andicated*positioti)', be in HUT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. *,
f21:. pt,,A-t::-E
- c. wt th one full length rod inoperable due ta causes other than w ii/./ :CAJs&iT $
addressed by ACTION a, above, or mis*a11 ned from its ou step counter demand position by lll)re than + 2 steps (indicated~--
~sit1on}), POliER OPERATION may *continue prov1 ed that within one hour e1 f:ner:
- l. . The rod is restored to OPERABLE status wi thf n the above al fgnment requirements, or £&.PL~E wirll rp~.e2TC-.
- 2. The remainder of the rods fn the ba with the inoperable rod are aligned to within steps of the inoperable roe!
while maintaining the rod - and insertion lfmits of Figures 3.1-1 and 3.1-2; the THERMAL PO\IER level shall be restricted pursuant to Specification 3.1.3.5 during 1ubs9e1uent op*ration, or
- 3. Th* rod 1s d9clared 1noP9rlble and *the SHUTOIJ\14 MARGIN requirement of Sp*cification 3.1.1.1 is satisfied. PO\ER OPERATION may th*n CD.nti nu. provid*d that:
- See Special Test Exceptions 3.10.2 and 3.10.3.
SALEM
- UNIT 2 3/4 1-13 Amendment No. 48
- a) Ar~valuat1on of each acc:ident analysis of Table 3.l-l 1s performed w1th1n s days; this reevaluation shall c:anf1rm that the previously analyzed results of these acc:1dents remain valid for the duration of op*rat1on under these c:and1t1ons.
- b) The SHUTOO..e MARGIN require1111nt of Spec1ficat1an 3.1.l~l 1s determined at least once per 12 l'laurs.
c) A pawe~ d1str1but1an nap js obtained from the rmvable 1nc:are detectors and Fo(Z) and FJIH are verified to be within their limits within 7'Zl'laurs.
d) The THERMAL PO~R 1evel 1s reduced ta less than or equal ta 7~1 of RATED THERMAL PO~R within one naur and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron nux trip setpoint 1s reduced to less than or equal ta 851 of RATED THERMAL PO~R. THERMAL PO~R shall be maintained less than or equal to 751 of RATED THERMAL PO\ER until c:ampl i ance wi tn ACTIONS 3 .1.3 .1 ;c .3 .a and 3 .1.3 .l.c: .3 .c above a denonstrated. 1 J 1 1. 4POI "'
1 y/,p
-t~e /;,.,,; r~ e-5TQl()f1> -/;'
lu>11 f.,*,,7 a.o-rtc/;??~ fi,..r 0f~re; 0 SURVEILLANCE RECUIREMEMTS ' "
be 4.1.3.1.2 Each full length rod nat fully ins1rt1d 1n the cara shall be determined ta be OPERABLE by navemnt of at 11ast 10 st1ps 1r, any out*
direction at least once per 31 days.
SAUM *UNIT Z 3/4 1*14 Amendment Na. 48
REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION
==================================================================
3.1.3.2.1 The shutdown and control rod position indication systems shall be OPERABLE and capable of determining the ac~ual and demanded rod positions as follows:
- a. Analog rod position indicators, within one hour after rod motion (allowance for thermal soak) ;
All Shutdown Banks: +/- 12 steps the group demand counters for withdrawal ranges o steps and 200-228 steps.
<"": R.ep~A-cE £-V1T4 ~E-RT D Control Bank A:~l~ stepj)of the group demand counters for withdrawal ranges of 0-30 steps and 200-228 steps.
R.e.Pt.'4CE WI~ ,$µ.i;E~T D Control Bank B: +/- 12 steps of the group demand counters for withdrawal ranges o 0-30 steps and 160-228 steps.
P.El'Ll4-t:..E w17'4 ~ER/ U Control Banks c and D:~ps of the group demand counters for withdrawal range of 0-228 step_s.
- b. Group demand counters; +/- 2 steps of the pulsed output of the Slave Cycler Circuit over the withdrawal range of 0-228 steps.
APPLICABILITY: MODES 1 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 50\' of RATED THERMAL POWER wi~hin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> .. 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 2 3/4 1-16 Amendment No .1 48
- l. Verify that all analog rod position indicators for the affected bank are OPERABLE and that the 111lSt withdrawn rod and the least withdrawn rod of the. bank are within a maximum o flf~of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or
~ R.EPt..'4t:.E """, 11-1 :z=AJt;£~r E
- 2. Reduce THERMAL PO lrER to 1ess than soi of RATED THERMAL PO \CR within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REQJIREMENTS 4.l.3.2.l.l Each analog rod pos1tion indicator shall be determined to be OPERABLE by verifying that the demand position ind.ication system and the rod position indication system agree within steps (allow1ng for one hour thermal soak after rod 111>tion) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. REPt.l"IGE wirrl J'AJ~-E~7 E 4 .1.3 .2 .1.2* Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL calibration at least once per 18 111>nths.
SALEM
- UNIT Z 3/4 l*l6a Amendment.No. 48
- RiACTiyrTY.CONTROL SYSTEMS BASES The- bor.c;:in capability required belo"' 200"F ia a*u.fficient to provide a SHUTDOWN MARGIN of l\' delta k/k .&fter xenon dec.si.y and cooldown from 2oo*r to 140°F. This condition requires either 2,600 ga1lons of 6,560 ppm borated water fran the boric acid storage tanks or 7,1u0 gallon* of 2,300 ppm borated water fran the refueling water storage tank.
The 37,000 gallons limit in the refueling water storage tank for Modes 5 and 6 is based upon 21,210 gallon* that is undetectable due to lower tap location, 8,550 gallons for instrument error, 7,100 gallons 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 ll.O for the solution recirculated within containment after a LOCA. This pH band minimizes the e*~olution of iodine and minimizes the effect of chloride and caustic stress corrosion 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 system during REFU'BLING ensures that this system is available for reactivity control while in MODE 6.
3/4.l.3 MQVABLE CONTBOL A$SEMBLIEf.
The specifications of this section ensure that (ll acceptable power distribution limits are maintained, (2) the minimum SHCTDOWN MARGIN is maintained, and (3) limit the potential effecta of rod mis-alignment on associated accident analyses. OPEP~ILITY of the control rod position indicators is required to detei -ine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. OPERABLE condition for the analog rod position indicators is defined as being capable of indicating rod position to within :t 12 stepo o the bank demand position for a range of positions. For the Shut own B a, and Control Bank A this range is defined as the group demand counter indicated position between O and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusiva. This permit* the operator to verify that the control rods in these banks are either fully withdrawn or fully inserted, the normal operating modes for these banks. Knowledge of these banks positions in these ranges satisfies all accident analysis assumptions concerning their position. The range for control Bank B is defined as the group demand counter indicat~d position between O and 30 steps withdrawn inclusive, and between 160 and 228 steps withdrawn inclusive. For Control Banks c and D the range is defined as the group dezna.nd counter indicated position between O and 228 steps withdrawn.
Comparison of the group demand counters to the bar~ 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 specifically establi~hed for each cycle by the Reload Safety Analysis for that cycle. This position will be within the band established by RF'ULL WITHDRAWN" and will be administratively controlled. Thia band is allowable to minimize RCCA wear, pursuant to Information Notice 87-19.
SALEM - UNIT 2 B 3.'4 l-4 Amendment No. 133
POl."ER r:*ISTRIBCTIO~L"iITS BASES 314.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY .HOT CHANNEL N
A.\'"D RADIAL PEAKING FACTORS - FQ(Z) AND F6H The limits on.heat flux and nuclear enthalpy hot channel factors and RCS flow rate ensure that l) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event.of a LOCA the peak fuel clad temperature will not exceed the 2200°F ECCS acceptance criteria limit.
Each of these hot channel factors are measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3.
This periodic surveillance is sufficient to .insure that the limits are maintained provided:
- a. Control rod in a si{l1e group move together with no individual rod insertion differing~ more than +/- 12 step§) from the group demand
~y m"'re ~"' positio~ ---e._,
-the ec //;,wee( b.
.A 'DD_____,
Control rod groups are sequenced with overlapping groups as r~o-e 1Y1*'sr<l17,,,,~,,/, described in Specification 3.1.3.5.
- c. The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.
- d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
The relaxation in ~H as a function of THERMAL POWER allows c~ges in the radial power shape for all permissible rod insertion limits. r~ will be maintained within its limits provided conditions a thru d above, are
- When an F measurement is taken, both experimental error and manufacturing ~olerance must be allowed for. Five percent is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3% !s the appropriate allowance for manufacturina tolerance.
When ~ is measured, experimental error must be allowed for and 4% is the approprtUte allowance for a fuJrl core map taken with the incore detection system. The specified limit for ~ also contains an 8% allowaac* for uncertainties which mean that norma! operation will result *in rAB ~ l.SS/1.08.
- The 8% allowance is based on the following considerations:
SALEM - UNIT 2 B 3/4 2-4 Amendment No. 72