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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20202B2471998-02-0303 February 1998 Proposed Revised TS in Response to 980127 RAI Re TS Change Request 59 ML20210Q2291997-08-21021 August 1997 Proposed Revised Tech Specs Re TS Change Request 59 ML20140C1441997-05-30030 May 1997 Proposed Revised TS Pages Re Decommissioning ML20134P3941996-11-25025 November 1996 Proposed Decommissioning TSs ML20112E8151996-05-17017 May 1996 Proposed Decommissioning TS Pages ML20094Q0691995-11-21021 November 1995 Proposed Tech Specs for Transfer of mgt-related Responsibilities for Plant from SNEC to Gpun ML20086A5791995-06-23023 June 1995 Proposed Tech Specs Pages 1,2 & 8,changing Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee Appropriately Maintained ML20084J3381995-06-0202 June 1995 Proposed Tech Specs,Reflecting Proposed Changes to TS App a Per TS Change Request 56 ML20072C2481994-08-0808 August 1994 Proposed Tech Specs,Revising Existing Content & Format & Analysis Applying Stds of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20062L8501993-12-20020 December 1993 Revised TS Pages Re Location,Exclusion Areas,Principal Activities & Administrative & Procedural Safeguards ML20045G7031993-06-23023 June 1993 Proposed TS A-4.3 Re Principle Activities Permitted by TS ML20094P0471992-04-0202 April 1992 Proposed TS Change Request 53,Rev 3 to License DPR-4, Removing Reactor Support Bldgs/Structures from TSs ML20090G8781992-03-0606 March 1992 Rev 2 to TS Change Request 53 to Amend License DPR-4, Requesting Removal of Reactor Support Bldgs & Structures from TSs ML20235H0441987-09-22022 September 1987 Proposed Tech Specs Change 53,reflecting Removal of Outbuildings & Structures ML20085D5831964-02-29029 February 1964 Proposed Tech Specs for Saxton Nuclear Experimental Corp ML20085D0701963-01-18018 January 1963 Proposed Rev of Suppl 1 to Tech Specs Re Automatic Switching of 440 Volt Buses During Operation of Safety Injection Pump ML20085C6331962-01-0505 January 1962 Proposed Tech Specs Re 5-yr R&D Program 1998-02-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206F6801998-04-22022 April 1998 Rev 0 to 6575-PLN-4542.08, ODCM, for SNEC ML20202B2471998-02-0303 February 1998 Proposed Revised TS in Response to 980127 RAI Re TS Change Request 59 ML20202F7111998-02-0202 February 1998 Rev 1 to 1000-PLN-3000.05, Saxton Nuclear Experimental Corp Facility Decommissioning QA Plan ML20211C2521997-09-16016 September 1997 Rev 0 to Procedure 6575-PLN-4542.09, SNEC Facility Process Control Program ML20210Q2291997-08-21021 August 1997 Proposed Revised Tech Specs Re TS Change Request 59 ML20140D2611997-06-0303 June 1997 to SNEC Facility Offsite Dose Calculation Manual ML20140C1441997-05-30030 May 1997 Proposed Revised TS Pages Re Decommissioning ML20134P3941996-11-25025 November 1996 Proposed Decommissioning TSs ML20112E8151996-05-17017 May 1996 Proposed Decommissioning TS Pages ML20094Q0691995-11-21021 November 1995 Proposed Tech Specs for Transfer of mgt-related Responsibilities for Plant from SNEC to Gpun ML20100H6231995-11-10010 November 1995 Rev 0 to Program 6250-PGD-2720, Engineering Support Personnel Training ML20100H6311995-11-0909 November 1995 Rev 0 to Procedure 6575-ADM-4500.07, SNEC Procedure Development,Change Requests & Safety Reviews ML20086A5791995-06-23023 June 1995 Proposed Tech Specs Pages 1,2 & 8,changing Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee Appropriately Maintained ML20084J3381995-06-0202 June 1995 Proposed Tech Specs,Reflecting Proposed Changes to TS App a Per TS Change Request 56 ML20107K0801995-04-20020 April 1995 Control of Hotwork ML20116A0811995-03-13013 March 1995 Rev 0 to Procedure 6575-PLN-4520.06, SNEC Site Characterization Plan ML20115K1141994-11-0101 November 1994 Rev 0 to Procedure 6575-PLN-4542.02, SNEC Soil Erosion & Sedimentation Control Plan ML20116A0731994-09-14014 September 1994 Rev 4 to Procedure 6210-ADM-2621.02, Maint Training Instructors ML20072C2481994-08-0808 August 1994 Proposed Tech Specs,Revising Existing Content & Format & Analysis Applying Stds of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20062L8501993-12-20020 December 1993 Revised TS Pages Re Location,Exclusion Areas,Principal Activities & Administrative & Procedural Safeguards ML20078A2701993-12-0303 December 1993 Rev 1 to Procedure 6575-SUR-4523.01, Quarterly Facility Insp Procedure ML20045G7031993-06-23023 June 1993 Proposed TS A-4.3 Re Principle Activities Permitted by TS ML20094P0471992-04-0202 April 1992 Proposed TS Change Request 53,Rev 3 to License DPR-4, Removing Reactor Support Bldgs/Structures from TSs ML20090G8781992-03-0606 March 1992 Rev 2 to TS Change Request 53 to Amend License DPR-4, Requesting Removal of Reactor Support Bldgs & Structures from TSs ML20090G8931992-03-0404 March 1992 Rev 0 to 6675-PLN-4542.01, Radiation Protection Plan ML20078A2621991-10-14014 October 1991 Rev 1 to Procedure 6675-ADM-4500.07, SNEC Procedure Development,Change,Requests & Safety Reviews ML20085C5001991-10-0202 October 1991 Procedure for Conducting 24 H Leak Rate Test ML20235H0441987-09-22022 September 1987 Proposed Tech Specs Change 53,reflecting Removal of Outbuildings & Structures ML20085C4491971-06-17017 June 1971 Containment Vessel Leakage Rate Determination by Absolute Method ML20085F5931968-02-28028 February 1968 High Radiation Evacuation Plan ML20085D5831964-02-29029 February 1964 Proposed Tech Specs for Saxton Nuclear Experimental Corp ML20085D2611963-06-10010 June 1963 Chemical Shim Test 308.3, Chemical Shim Control Under Nucleate Boiling Conditions ML20085D0701963-01-18018 January 1963 Proposed Rev of Suppl 1 to Tech Specs Re Automatic Switching of 440 Volt Buses During Operation of Safety Injection Pump ML20085C6331962-01-0505 January 1962 Proposed Tech Specs Re 5-yr R&D Program ML20085C6161961-11-15015 November 1961 Preoperational Tests ML20085F5871961-11-0101 November 1961 Plan for Hosp Reception of Radiation Casualties ML20085C5921961-08-17017 August 1961 Preoperational Test 304C, Component Cooling Sys Operational Test 1998-04-22
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SAXTON NUCLEAR EXPER! MEN ~AL CORPORATION DOCKET NO. 50-lh6 LICENSE NO. DPR-b
% 4E 0/ co%hanc, Proposed Changes in Techni:al Specifications Applicable to Conduct of Phase 1 of the Saxton Five-Year Research and Development Program Page 1, item 2 - Change "20 Kdt" to "23.5 int."
Page 2 - Chan;e (c) in second paragraph to rear'. "Maxinum mixed core exit c
tenperature at 20 K4t borated with 161:w/f t spiked subassembly -
5h60F maximun mixed ccre exit temperature at 23.51Nt bort - .a with 16 kw/ft spiked subassembly - 5500F."
Page 2, (b) " Power operation" - Change " Boric Acid" from "Less than 3.0 ppm as boron" to "A maximum of 2500 ppm as boron," and change
" Lithium (Li 7)* 3 ppm as required to maintain pH between 9.5 to 10.5 15 as measured at 25oC" to " Potassium - A maximum of 3.8 ppm potassium (KOH) or the chemical equivalent of lithiun (LiOH)." Delete footnote marked with an "*", which pertained to " Lithium (Li7)."
Also delete last sentence on page 2.
Page 3, item 6(b) - Change to read " Uranium Oxide (UO2 ) enriched to s.7% U-235 will be used in 20 of the 21 fuel assemblies. The remaining fuel tssembly will have enrichments as follows:
"63 rods (and) 9 central rods (or) 9 central rods "First lh pellets 5.69% 5.69% 5.69%
Next 2 "
7.30% 9.19% 7 30%
a 3
6.81% 8.57% 6.81%
12 "
6.h6% 8.13% 6.h6%
3 6.81% 8.57% 6.815
" 2 "
7.30% 9.19% 7.30%
Last lh "
5.69% 5.69% 5.69%
" Uranium oxide at the density being used has a melting point of approximately 50000 F."
Page h, item 6(c) - Add following sentence, "One 9-rod subassembly using 5.7%
enriched fuel will have cladding of Zircaloy b which has a melting point of approximately 30h50F."
Page b, item 6(e) - Change to read " Maximum total weight of fuel in the core is approximately 2250 lbs of UO2 enriched as shown in (b) above."
Page h, item 6(i) - Add following sentence, "The moderator tempera ure coefficient during the chemical shim tests will vary from -5.3 x 10- k/0F to
-1.6 x 10-b k/ F."
Page h, item 6(j), fourth paragraph - Change "200 ppm" to "2500 ppm" in first sentence. Ihlete last sentence.
9110040095 o10424 PDR FOIA DEKOK91-17 PDP F om C0 W4S- 33{
IP-Pace $, iten 6(k) - Change to read as follows: "Under steady-state conditions at 23.5 MWt. the principal temperature and thernal characteristics of the spiked fuel assembly are as follows:
" Maximum calculated heat flux Btu /hr-ft22 h70,000' Average heat flux Btu /hr-ft 161,000 Minimum burnout safety factor (WAPD Correlation ) 1.6h Maximum calculated fuel clad tenperature, OF 6h2 Maximum fuel heat generation, kw/f t 16 Average power density, kw/ liter - core 63.5-Page 5, item 6(1) - Change "less than 1.85" to "less than 1.16."
Page 6, item 7(g) - Change "High Power Level at Power (Maximum)" from "2h MW" to "27 MW."
Page 6, item 7(g) - Change "High Main Coolant Temperature (Hot Leg) (Maximum)"
from "6000F" te "$$h0F."
Page 17, iten 19(e) - Add item (8) to read as follews: "During the chemical shim control tests periodic measurements of the core reactivity shall be made. The total unexplained reactivity loss, including measure-ment and calculation uncertaintics, shall be limited to value such I that its release in the manner postulated in Section V-B-5 of Phase 1 of the Safeguards Repert does not exceed the accident criteria set in Section V-A-2. In performing the computations to determine this reactivity value, the experimentally determined core charact:ristics will be used. If the unaccounted for reactivity reaches the above limit, the experiment shall be discontinued and an evaluation instituted to determine if the reactivity change was due to poison deposition on the core."
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