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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20141K9941997-05-0505 May 1997 Amend 89 to License DPR-34,designating All Elements of Approved Decommissioning Plan as License Termination Plan ML20246J3091989-08-30030 August 1989 Amend 72 to License DPR-34,imposing Early Shutdown on Plant by Limiting Reactor Power to 2% of Full Power After 900630 ML20245J3671989-08-14014 August 1989 Amend 71 to License DPR-34,revising Provisions in Tech Specs Re Radiological Effluents ML20245C4991989-04-18018 April 1989 Amend 70 to License DPR-34,changing Amount of Radioactive Matl to Be Possessed for Analysis & Instrument Calibr ML20248D6461989-03-31031 March 1989 Amend 69 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20236A1351989-02-27027 February 1989 Amend 68 to License DPR-34,modifying Limiting Condition for Operation 4.4.1 & Surveillance Requirement 5.4.1 to Include Fixed High Temp Trip Setpoint for Steam Line Rupture & Detection Sys ML20205F9781988-10-24024 October 1988 Amend 65 to License DPR-34,amending Tech Specs Paragraph 2.D(3) to Require Compliance W/Amended Physical Security Plan & to Conform to 10CFR73.55 Requirements ML20154J7931988-09-15015 September 1988 Amend 64 to License DPR-34,changing Tech Specs for Plant DC Power Sys & Allowing for Future Changes to Station Batteries ML20154J4561988-09-15015 September 1988 Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20207F0061988-08-0505 August 1988 Amend 61 to License DPR-34,deleting Requirement to Monitor Temp of Dew Point Moisture Monitors in Section 4.4 ML20207F2141988-08-0505 August 1988 Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2 ML20151A9921988-06-20020 June 1988 Amend 60 to License DPR-34,revising Certain Setpoints for Protective Sys to Allow for Instrumentation Error ML20148S5901988-04-0707 April 1988 Amend 59 to License DPR-34,deleting Tabular Listing of safety-related Snubbers from Tech Specs ML20236U5191987-11-23023 November 1987 Amend 57 to License DPR-34,revising Tech Specs to Ensure Sufficient Helium Coolant Flow to Prevent Overheating of Fuel While in Low Power or Shutdown Modes ML20235N6441987-07-13013 July 1987 Amend 56 to License DPR-34,changing Certain Administrative Controls Under Which Plant Operated,In Partial Response to 860722 & 1205 Applications.Tech Spec Pages Encl ML20235E5201987-06-29029 June 1987 Amend 55 to License DPR-34,revising Tech Spec to Require Both Sections of Both Steam Generators to Be Available for DHR in Power Operation ML20214M4401987-05-20020 May 1987 Amend 54 to License DPR-34,modifying Surveillance Requirements for Standby Diesel Generator ML20215J8201987-05-0505 May 1987 Amend 53 to License DPR-34,changing Tech Specs to Show Actual Location of Fire Hose Station TH12-G4 ML20206J8411987-04-0606 April 1987 Amend 52 to License DPR-34,increasing Circulator speed-high Steam Trip Setting Listed in Table 4.4-3 of Tech Specs ML20207S1951987-03-0909 March 1987 Amend 51 to License DPR-34,revising Portions of Section 5.2 Through 5.4 of Tech Specs.Sections Pertain to Phase II of Util Inservice Insp & Testing Program ML20212J3171987-02-26026 February 1987 Amend 50 to License DPR-34,changing Tech Specs Re Steam Line Rupture Detection/Isolation Sys ML20212A8971986-12-15015 December 1986 Amend 49 to License DPR-34,revising Tech Specs to Add Section 4.9.3 Re Xenon Stability Testing ML20214P6731986-11-25025 November 1986 Amend 48 to License DPR-34,adding Section 7.7 Concerning Formalized Fuel Surveillance Program to Tech Specs ML20206C6721986-06-12012 June 1986 Corrected Amend 47 to License DPR-34,modifying Tech Specs to Allow Replacement of Mechanical Snubbers W/Hydraulic Snubbers ML20141N5451986-03-0404 March 1986 Amend 47 to License DPR-34,changing Tech Specs to Allow Mechanical Snubbers to Be Replaced by Equivalent Hydraulic Snubbers ML20244A6521979-04-20020 April 1979 Amend 20 to License DPR-34 to Revise Tech Specs to Install Eight Test Fuel Elements Into Reactor Core at First Refueling & to Install Graphite Surveillance Specimens Into Five Bottom Transition Reflector Elements 1997-05-05
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20141K9941997-05-0505 May 1997 Amend 89 to License DPR-34,designating All Elements of Approved Decommissioning Plan as License Termination Plan ML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20246J3091989-08-30030 August 1989 Amend 72 to License DPR-34,imposing Early Shutdown on Plant by Limiting Reactor Power to 2% of Full Power After 900630 ML20245J3671989-08-14014 August 1989 Amend 71 to License DPR-34,revising Provisions in Tech Specs Re Radiological Effluents ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245C4991989-04-18018 April 1989 Amend 70 to License DPR-34,changing Amount of Radioactive Matl to Be Possessed for Analysis & Instrument Calibr ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20248D6461989-03-31031 March 1989 Amend 69 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20236A1351989-02-27027 February 1989 Amend 68 to License DPR-34,modifying Limiting Condition for Operation 4.4.1 & Surveillance Requirement 5.4.1 to Include Fixed High Temp Trip Setpoint for Steam Line Rupture & Detection Sys ML20205F9781988-10-24024 October 1988 Amend 65 to License DPR-34,amending Tech Specs Paragraph 2.D(3) to Require Compliance W/Amended Physical Security Plan & to Conform to 10CFR73.55 Requirements ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20154J4561988-09-15015 September 1988 Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20154J7931988-09-15015 September 1988 Amend 64 to License DPR-34,changing Tech Specs for Plant DC Power Sys & Allowing for Future Changes to Station Batteries ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 ML20207F2141988-08-0505 August 1988 Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2 ML20207F0061988-08-0505 August 1988 Amend 61 to License DPR-34,deleting Requirement to Monitor Temp of Dew Point Moisture Monitors in Section 4.4 ML20151A9921988-06-20020 June 1988 Amend 60 to License DPR-34,revising Certain Setpoints for Protective Sys to Allow for Instrumentation Error ML20151S2411988-04-20020 April 1988 Application for Amend to License DPR-34,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery & Associated Battery Charger Disconnected from Dc Bus 1997-05-05
[Table view] |
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ps - a UNITED STATES
'p - NUCLEAR REGULATORY COMMISSION
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[' PUBLIC SERVICE COMPANY OF COLORADO 3 DOCKET NO. 50-267 I
l- -FORT ~ST. VRAIN NUCLEAR GENERATING STATION T:
b AMENDMENT-TO FACILITY OPERATING' LICENSE Amendment No. 20 License No. DPR-34 i
7 1. The Nuclear Regulatory Commission (the Commission) has found that:
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4 A. The applications for amendment by Public Service Company of -
- Colorado (the licensee) dated January 9, 1978, and January 26, c; . 1979, comply with the standards and. requirements' of the Atomic
- h- Energy Act of 1954, as amended (the Act) and the Commission's
. regulations set forth in 10 CFR Chapter I; B. 'The facility will operate in conformity with the application.
- ;- the provisions of the Act, and the regulations of the Commission;
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![ C. There is reasonable assurance (i) that the activities authorized
[ by this amendment can be conducted without endangering the health
- i. 'and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance-of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications'as indicated in the attachment to this license amendment, and paragraph 2.D(2) of facility Operating License No. DPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as' revised through Amendment No. 20, are hereby incorporated in i the license. The licensee shall operate the facility in accordance 'with the Technical Specifications.
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xm, i 'J -J'l Thisilicense amendment 'is; effective.' a s of the date. of its issuance.
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" 9 FOR THE NUCLEAR REGULATORI C0WIISSION
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Attachment:
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Date.of Issuance: April 20; 1979
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', ATTACHMENT-6 AMENDMENT NO. 20 TO
[ FACILITY OPERATING LICENSE DPR-34 Docket No. 50-267 Remove existing pages 6.1-3 and 6.1-4 of Technical Specifications, Appendix A, and replace them with the attached pages 6.1-3. through 6.1-6. The changed areas are reflected by marginal lines.
Also, add pages 5 2,-19 and 5 3-20, which add a new technical speci-fication.
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1 Each fuel element is.a hexagonal right prism with' nominal dimensions of 14.2 inches across the flats by 31.2 inches high. The fuel beds and coolant channels are distributed on a triangular array of about 3/4 inch pitch spacing with an ideal ratio of two fuel beds for each coolant channel. l l
The bottom of the fuel beds in the bottom fuel element of the control rod fuel column does not exceed a length of 23.1 inches from the top face of the fuel element.
Fuel The fuel consists of fissile uranium highly enriched (93.15%) in 235 U and fertile thorium. The initial fuel loading is about 773 Kg of uranium and 16,000 Kg of thorium. The initial core is loaded with 13 fuel compositions whose distribution within the core is designed to mock up the fuel content of the equilibrium cycle refueling regions and to shape the radial and axial power distribution. Fuel is designed for up to a six year life. Abput one-sixth of the core will be replaced at each refueling interval. The fuel loading in a reload segment will be about l
200 Kg of uranium and 2300 Kg of thorium.
All uranium and thorium in the reference fuel elements is in the form I
of heavy metal carbide and pyrocarbon, referred to as coated fuel particles.
The coatings form the primary fission product barrier. The coated fuel particles consist of two general types, fissile particles (TH:UC 2) and ;
fertile (TH C2) Particles. The fissile particles shall contain thorittm and uranium in a weight ratio of about 4.25 to 1 of thorium to uranium.
l l The fsrtile particles shall contain only thorium.
Amendment No. 20 1
{\'- 6.1-4 In addition to the reference fuel elements, eight test fuel elements are included in'the reactor core. These eight' test elements (FTEl-8) contain y small quantities of' test fuel particles that are in various ways dif ferent
} rom the reference fuel. The description of the test fuel elements is contained in Table 6.1-1.
The coated fuel particles are bonded together with a carbonaceous material to form fuel rods. The' fuel rods are completely surrounded and contained by graphite which forms the structural part of the fuel element
- and, in addition to .the carbon contained within the- fuel rods, also serves as the sole moderator. The reference fudl elements are fabricated from H-327 needle' coke (anisotropic) graphite, as described in the Fort St.
Vrain FSAR, Section 3.0. 'The test fuel elements are fabricated from H-451 near-isotropic graphite in anticipation of qualifying this material for future use in all reload fuel for'the reactor.
Reflector Reflector elements above, below, and immediately adjacent to the side of the active core are hexagonal right prisms with nominal dimensions of 14.2 inches across flats and 15.6, 23.4, or 31.2 inches high, as required.
The outer peripheral envelope of the reactor core reflector graphite contains boron to minimize the neutron flux leaving the reflector. The side reflector contains nominal 2.3 weight percent boron stainless steel pins l within the spacer blocks. The middle layer of lower reflector elements, excluding the central element in each core region, contains 25 weight percent boronated graphite pellets enclosed in hastalloy-X cans. The top layer of reflector above the hexagonal columns contains 1 weight percent i
Amendment No. 20
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crushed ' boronated graphite. , ' The top layer of reflector above the .
Permanent side re flector. blocks contains 1 weight percent boronated l
graphiteLenclosed in steel cans.
Basis for:. Specification e DF 6.1- ,
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- The above specifications form the general design bases and criteria-for the overal1 design features of the reactor core which were used to
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<b. . evaluate ,its general perf ormance. Further details concerning these design
. features are given in Section 3.0 of the FEAR and the Safety Analysis Report for Fort St. Vrhin Reload' 1 Test ' Elements FTE-1 through FTE-8, General i
Atomic Document C1;P-5494, June 30, 1977.
Amendment No. 20
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5.2-19 Specification SR 5.2.'22 PGX Graphite Surveillance
-PGX graphite surveillance specimens shall be installed into five (5) bottom transition reflector elements of the Fort St. Vrain core to provide a means for ' assessing the condition of the PCX ' graphite support blocks during operation of the reactor. These specimens (16 per reflector element) will be installed in reflector elements as indicated in. Table 1 and will be removed at subsequent refueling intervals, as indicated in Table 1, unless the progressive examination of the specimens dictate otherwise. +
Upon removal, these specimens will be subjected to nondestruc--
tive examination, and compared with laboratory control specimens in evaluating oxidation rates, oxidation profiles, and general dimensional characteristics.
The results of these tests and examinations shall be utilized to assess the condition of the PGX core support blocks in the reactor and shall also be utilized to modify, as necessary, the planned removal of subsequent PGX surveillance specimens.
The results of these examinations shall be submitted to the NRC staff for review.
Basis for Specification SR 5.2.22 The PGX graphite specimens will be placed in modified coolant channels in five (5) transition reflector elements in the hottest columns of regions 22, 24, 25, 27,and 30. The surveillance test specimens will be subjected to the primary coolant conditions as well as other reactor parameters that are normally seen by the PGX core support blocks. Exam-ination and tests of the surveillance test specimens at regular intervals can readily be utilized to assess oxidation rates, oxidation profiles, as well as general degradation of the PGX core support blocks to adequately predict the structural integrity of the core support blocks over the operating life of the reactor. ;
i Amendment No. 20
5.2-20 SR 5.2.22. PGX GRAPHITE SURVEILLANCE Table 1 TRANSITION ELEMENT ASSEMBLY WITilDRAWAL SCHEDULE Withdrawal at Refueling Reflector Region Column Number
- 25 7 2 30 3 4 24 7 6 22 6 9 27 2 17 J
- Schedule would be adjusted to remove transition element assemblies at a faster. rate should specimens at any withdrawal interval show a burnoff significantly greater than predicted.
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Amendment No. 20
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