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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 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI 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 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 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 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 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 ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 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 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
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4 l
ATTACHMENT 1 Consuniers Power Corapany ,
Palisades Plant i Docket 50 255 I
l I
l TECHNICAL SPECIFICATION CHANGE REQUEST l ENRICHMENT IN NEW AND SPENT FUEL STORAGE ;
PROPOSED NEW PAGES October 28, 1991 2 Pages 01110600Y4 Y 110:Z:s PDR ADOCK 05000255 P PDR
5.4 FUEL STORASE
~ 5.4.1 Etw_ fuel Storagg-
- a. The pitch of the new fuel storage rack lattice is 29,375 inches, and every other position in the lattice shall be permanently occupied by an;8" ',1" structural steel box beam or core plugs such that the minimur inter-to-center spacing of new fuel assemblies in the
-alternal g storage _ array is 13.26". This distance in the alternating storage lattice is sufficient so that X will not
, exceed 0.95 where fuel assemblies with 216 002 or Gd2 0 rub,r fuel rods or metal rods and a maximum average planar enrichment in the U0, or Gd are in place and optimum mod,0r VO, fueleration is 4.20 rods of assumed.
w/o U 'ed K includes appropriate The calcul?t conservatisms as described in Siemens NucTear Power Corporation
-Report EMF-91-1421(P).
- b. New fuel may also be stored in shipping containers,
- c. The new fuel storage racks are designed as a Class I structure.
5-4 Amendment No # , Q , JM
<,e
5.4.2 Spent fuel Storace
- a. Irradiated fuel bundles Elli be stored, prior to off-site shipment in the stainless steel lined spent fuel pool.
- b. (Deleted)
- c. The spent fuel storage pool and spore (north) tilt pit are divided into two regious identified as Region I and Region !! as illustrated in Figure 5.4 1. Region I racks are designed and shall be maintained with h nominal 10.25" center-to-center distance between fuel assemblies with the exception of the single Type E rack which has a nominal 11.25" center-to-center distance between fuel assemblies. The Region I spent fuel storage racks are designed such that fuel having a maximum assembly planar average U enrichment of 4.40 w/o placed in the racks would result in a K,, 233 equivalent to s 0.95 when flooded with unborated water. The K ' of s 0.95 includes a conservative allowance for uncertainties. for enrichments above 3.27 w/o U the fuel assemblies must contain 216 rodswhichareeitherUO,,d85, 20 3-U0, or solid metal .
- d. Region 11 racks have a 9.17 inch center-to-center spacing. Because of this smaller spacing, strict controls are employed to evaluate burnup of the fuel assembly prior to its placement in Region- 11 cell locations. Upon determination that the fuel assembly meets the burnup requirements of Table 5.4-1, placement in a Region 11 cell is authorized. These positive controls assure the fuel enrichment limits assumed in the safety analyses will not be exceeded.
- e. (Deleted)
- f. The minimum spent fuel pool water boron concentration shall be 1720 ppm. Boron concentration shall be verified ci least once monthly..
- g. The spent fuel racks are designed as a Class I structure.
- h. (Deleted)
- 1. Storage in Region II of the spent fuel pool and spare (north) tilt pit shall be restricted by burnup and enrichment limits specified in Table 5.4-1.
NOTE: Until needed for fuel storage, one Region 11 rack in the northeast corner of the spent fuel pool may be removed and replaced with the cask anti-tipping device.
L Re ferences FSAR Update Chapter 5 FSAR Update Chapter 9 Amendment No. JpJi, JJJ t
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. .. j ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 ,
. TECHNICAL SPECIFICATION CHANGE REQUEST ENRICHMENT IN NEW AND SPENT FUEL STORAGE FARKED UP PAGES October 28, 1991 1
1 l
l 2 Pages i
l
_ - . . . - - - . - . - - - . - . . . . . - - . - . . . ~ . - . _ . _ _ -
9- 5.4 FUEL--STORAGE 5,4,1 New Fuel Storaae i
-i a.- The pitch- of the new fuel . stor ge rack lattice is 29.375 inches, and every other position in e lattice shall be permanently occupied by an 8" x 8" str- tural steel box beam or core plugs >
such that the minimum cer er-to-center spacing of new fuel assemblies in the alter ting storage array is 13,26". T his distance in the altern ting storage lattice is sufficient so that ,
K ,, will not exceed 0. , where fuelp hi;h centeir3 n;t Cre +h ? " -- I 4+-P y ~ e fM E e, u . .I c ; 7 r 4e t e er 3ctium ruel n;;1bly
.14 in place and optimum (ie, m;p us fees}-moderation is assumed , i
-e n d +h e M,,, a i " "+ ev:nd 0 7 h h :tocege area i; fbeded- '
with unLvioicJ naici. The cal lated K ,, includey2 cen;;rvati e fe. wucertainties - [. w en t :
"~=: described.i, LPC siter; cf-
-12/19/70 and 1/12/77.
- b. New fuel'may also be stor d in shipping co ainers,
- c. The new fuel storage r eks are designed s a Class I structure.
( .;
7 e 44pa7p sawWNq decnkdid El9mE Aluc/ pan Pown0gn6 ydTEMF-9Hwid ,
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)~ 0 YJ~ 00 0ff3fQA2 Amendment Nu 35, #9, W 4e1y 2?r-19aZ I
u -
5.4.2 spent Tuel Storage
- a. Irradiated fuel bundles will be store shipmentinthestainlesssteel-linedhpriortooff-site ut fuel pool,
- b. (Deleted)
- c. ~he spent fuel storage pool and opare (north) It pit are divided into two regions identified as Region I .d Region 11 as illustrated in Figure 5.4-1. Region I racks are signed and shall be maintained with a nominal 10.25" center-to enter distance between fuel assemblies with the exception o the single Type E rack which has.a nominal 11.25" center-t. center distance between fuel assemblies. The Region I spent fu storage racks are designed such that fuel having a maximum U-235 g f h f' .Loadio 4,U. v/o f " 23L pieced in the racks vould result in aF equivalent to s 0.95 when flooded with unborated veter, e' of s 0.95 includes a conservative allevance for uncerIkknties,
< d. Region II rack hcve a 9.17 inch center-to-center spacing.
//,/g 7 Because of th smaller spacing, strict controls are employed to evaluate bur. p of the fuel assembly prior to its placement in Region II ce 1 locations. Upon determination that the fuel assembly me es the burnup recuirements of Table 5.4-1, placement in a Regio. II cell is authorized. These positive controls-assure the fuel enrichment limits assumed in the safety analyses will not e exceeded,
- e. After i stallation of the two-region high density spent fuel racks, he maximum loading for fuel ensemblies in the spent fuel racks a 3.27 v/o of U-235.
- f. The inimum spent fuel pool water boron concentration shall be 172 ppa. Boron concentration shall be verified at least once mo hly.
- g. T e spent fuel racks are designed as a Class I structure,
- h. Deleted) / >
- 1. Storage in Region II of the spent fuel pool and spare (north) tilt pit.shall be restricted by burnup and enrichment limits specified in Table 5.4-1.
OTE: Until needed-for fuel storage, one Region Il rack in the-northeast cornet of the spent fuel pool may be removed and replaced with the cask anti-tipping device.
References FSAR Update Chapter 5 FSAR Update Chapter 9
[ ~c 1 % :c. ) m h O b t A S $ Y O 0;t 2 f , E R- "Y w f),k <r,w.iT*caEits) A /6 Hd.1 wksh ou "&
UOz,C4 03-UD TSP 0287-02:3-N1,04 z e s ehd ad%) . N"**"'Ei*'*
1
ATTACHMENT 3 .
i Consumers Power Company Palisades Plant Docket 50-255 l
L 1;
TECHNICAL SPECIFICATION CHANGE REQUEST ENRICHMENT IN NEW AND SPENT FUEL STORAGE ,
SIEMENS NUCLEAR POWER PROPRIETARY tlEPORT EMF-91-174(P)
October 28, 1991 l.
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