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| {{Adams
| | #REDIRECT [[L-99-068, Forwards Application Requesting Consent to Transfer of Dl Ownership Interests in Bvps,Units 1 & 2 to Penn Power & Dl Operating Authority Under FOLs DPR-66 & NPF-73 to Firstenergy Nuclear Operating Co]] |
| | number = ML17355A304
| |
| | issue date = 04/26/1999
| |
| | title = Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6
| |
| | author name =
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| | author affiliation = FLORIDA POWER & LIGHT CO.
| |
| | addressee name =
| |
| | addressee affiliation =
| |
| | docket = 05000250, 05000251
| |
| | license number =
| |
| | contact person =
| |
| | document report number = L-99-068, L-99-68, NUDOCS 9905040069
| |
| | package number = ML17355A303
| |
| | document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| |
| | page count = 32
| |
| }}
| |
| | |
| =Text=
| |
| {{#Wiki_filter:L-99-068 Attachment 3
| |
| ATTACHMENT 3 PROPOSED LICENSE AMENDMENTS FOR ADMINISTRATIVE CHANGES TO FACILITY OPERATING LICENSES AND TECHNZCAL SPECIFICATIONS P
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| PO ED F ZLITY OPERATING LI ENSE PAGES DP -
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| 1 page 3
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| PR POSED FA ZLITY PERA IN LI ENSE PAGE DPR-41 page 4
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| PR POSED TE HNICAL PE IFI ATZONS INDEX PAGES Pages iv, v, vi, viii, x, xi, xiv, xxi, xxii, xxiii, xxiv PROPOSED TECHNI AL SPECIFZCATION PAGES page 3/4 1-14 FIGURE 3.1.2.5, Page 3/4 1-14a page 3/4 7-18 TABLE 4.7-1, Page 3/4 7-18a PDR ADGCK 05000250
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| m nr r
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| n DELETED hr hAmnmn
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| ~ ~ DPR-31 Page 3
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| DELETED FPL shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report (UFSAR) for Turkey Point Units 3 and 4 and as approved in the Safety Evaluation Report (SER) dated March 21, 1979 and supplemented by NRC letters dated April 3.
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| 1980. July 9.
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| 1980.
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| December 8,
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| 1980.
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| January 26, 1981.
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| May 10,
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| : 1982, March 27, 1984, April 16,
| |
| : 1984, August 12.
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| 1987
| |
| ~
| |
| and by Safety Evaluation dated February 25 '994. subject to the following provision.
| |
| The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
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| H.
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| f r
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| n in n
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| Pl DELETED m
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| nr rR irPr r
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| DELETED r
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| Tr inin n
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| lifi i n Pl n
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| DELETED K.
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| n r
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| DELETED L.
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| The license shall fully implement and maintain in effect all provisions of the Commission-approved physical security.
| |
| guard training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR net.U'6, 73.55 (51 FR 27817 and 27 2) a t
| |
| hor't gf 10 CFR 50.90 an 10 CFR 50.54( ).
| |
| e p ans, whic contain afeguar s I ormation pr ecte
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| : urger, 10 C
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| . are entitled:
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| "Turkey Po'
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| : Plant, Un' 3 and 4 S curity P n."
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| with revisi s submitted rough Apri 13, 1988:
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| " urkey Point lant.
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| U ts 3 and 4.
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| Tr ning and Qu ification an," with evisions su mitted t rough December 8
| |
| ~
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| 1986; a
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| "Turkey oint Plant.
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| Units 3 | |
| a d
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| 4 Saf guards Conting ncy Plan ~ " wi revisions submitted t ough July 1
| |
| 1985.
| |
| Changes made accordance w
| |
| h 10 CFR 7.55 shall be implemented n accord nce with the hedule set fo h therein.
| |
| This license is effective as of the date of issuance,
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| .and shall expire at midnight July 19 '012.
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| | |
| P
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| hr hAmnmn
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| .. OPR-41 Page 4
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| The licensee may make changes to the approved Fire Protection Program without prior approval of the Comoission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
| |
| G.
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| f r
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| n in n
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| Pl n
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| DELETED m
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| nr r
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| irPr r
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| DELETED r
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| Tr inin n
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| lifi i nPl n
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| DELETED f
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| r DELETED K.
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| n r
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| DELETED L.'he license shall fully implement and maintain in effect all provisions of the Corrrnission-approved physical
| |
| : security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Niscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to he authorit of 10 CFR 50.90 and 10 CFR 50.54( ).
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| guar orma io pro c e e
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| FR
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| .24 are entitled:
| |
| "Turkey ointzPlant Units 3
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| an 4 Segurity Plant'it reviPio s
| |
| : submi, ed ter'ough A ril 13',
| |
| 1988 "Tur(dy Poi t Plant, Ut) ts 3 an 4,
| |
| Training tfd Qu ifica on Pla,"
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| w th re isiog sub i'tted h
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| ugh December 8,
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| 1 6:
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| and "Turke/ Poin Plan@
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| Units 3 a
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| d 4 fe uards Contin ncy P an,"
| |
| re fsions submitted 6roug July 15K 1985.
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| Chang s
| |
| made in acc rdance with CFR 73.55 shall e
| |
| imp emented in aeee -dance-w~
| |
| ched e-se forth-the~n.
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| 1 This license is effective as of the date of issuance, and shall expire at midnight April 10, 2013.
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| | |
| I
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| | |
| INDEX L MITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION
| |
| ~PAG 3 4.0 APP ICABI ITY................................;...............
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| 3/4 0-1 3 4.1 R ACTIVITY CONTROL SYSTEHS 3/4.1.1 BORATION CONTROL Shutdown Margin - T Greater Than'00'F.......--..-.-....
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| FIGURE 3.1-1 REQUIRED SHUTDOWN HARGIN VERSUS REACTOR COOLANT BORON CONCENTRATION......-.......
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| Shutdown Margin - T Less Than or Equal to 200'F........
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| avg Hoderator Temperature Coefficient.............-..-........
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| Hinimum Temperature for Criticality.......................
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| 3/4 1-1 3/4 1-3 3/4 1-4 3/4 1-5 3/4 1-7
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| ~O0 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION EVENT OF AN INOPERABLE FULL-LENGTH ROD..
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| Position Indication Systems - Operating....
| |
| TABLE 4.1-1 ROD POSITION INDICATOR SURVEILLANCE REQU Position Indication System - Shutdown......
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| Rod Drop T>me..............................
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| Shutdown Rod Insertion Limit...............
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| IN THE IREHENTS.......
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| Control Rod Insertion Limits............................
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| 3/4.1.2 BORATION SYSTEMS Flow Path Shutdown.....;................................
| |
| Flow Paths - Operating...............
| |
| Charging Pumps - Operating............
| |
| Borated Mater Source - Shutdown..
| |
| Borated Water Sources - Operating.........................
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| Heat Tracing..............................
| |
| FlgoRC 3.L-Z g~R>c P ClD TAI"K Nl INl~oM VOLV~F.
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| 3/4.1.3 MOVABLE CONTROL ASSEHBLIES roup Heighto ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| G 3/4 1-8 3/4 1-9 3/4 1-11 3/4 1-12 3/4 1-14 3/4 1-16 3/4
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| )" i/a.
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| 3/4 1-17 3/4 1-19 3/4 1-20 3/4 1-22 3/4 1-23 3/4 1-24 3/4 1-25 3/4 1-26 TURKEY POINT - UNITS 3 L 4 iv ANFNAHvNv un~
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| 167 own 151
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| r Aj 1
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| r)
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| INDEX 4
| |
| I L H TING CONDITIONS fOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION 3 4. 2 POWER DISTR BUTION LIHITS PAGE 3/4.2.1
| |
| /4.2.2 3/4.2.3 3/4.2.4 3/4.2.5 AXIAL FLUX DIFFERENCE....-...
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| HEAT FLUX HOT CHANNEL FACTOR..............
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| NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.
| |
| QUADRANT POWER TILT RATIO.... -. -.. -........
| |
| DNB PARAMETERS...........
| |
| 3/4 2-1 t
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| 3/4 2-4 3/4 2-11 3/4 2-13 3/4 2-16 3 4. 3 INSTRUMENTATION 3/4.3. 1 REACTOR TRIP, SYSTEM INSTRUMENTATION.....
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| TABLE 3.3-1 REACTOR TRIP SYSTEH INSTRUMENTATION..
| |
| TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREHENTS..................................
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| 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.....
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| TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...............
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| ~..........
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| TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUHENTATION TRIP SETPOINTS.....
| |
| TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4.3. 3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations.................
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| 3/4 3-1 3/4 3-2 3/4 3-23 3/4 3+5 31o 3/4 3-35, 3
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| 3/4 3-8 3/4 3-13 3/4 3-14 FlQQQC.
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| '5
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| ~ Z-~
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| P,gIAI-FLUX DIFF'fgCggE LIHlfS A> A FgQcTlohl o' RAwq5 THERMAL Po~~
| |
| ~ 3/q z-3 TllRKFY POINT - UNITS 3 5 4 AMENDMENT NQS 167 AND 161
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| I J
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| ~$
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| ~
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| I 1
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| I 4
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| INOEX LIHITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION TABLE 3.3-4 TABLE 4.3-3 TABLE 3.3-5 TABLE 4.3-4 TABLE 3.3-7 TABLE 4.3-5 TABLE 3,3-8 TABLE 4.3-6 RADIATION MONITORING INSTRUHENTATION FOR PLANT OPERATIONS.......
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| RADIATION MONITORING INSTRUHENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.....
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| Movable Incore Detectors.....
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| Accident Monitoring Instrumentation...
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| ACCIDENT MONITORING INSTRUHENTATION....;.
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| ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Fire Detection Instrumentation -........................
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| Radioactive Liquid Effluent Monitoring Instrumentation RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION..
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| RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
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| Explosive Gas Monitoring Instrumentation EXPLOSIVE GAS MONITORING INSTRUMENTATION...........,....
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| EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS.............
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| PAG 3/4 3-36 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42 3/4 3-46 (DELETED)
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| (DELETED)
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| (DELETE (DELETED)qp 3/4 3PI 3/4 3 Pb 3/4 3PP) gg AHC
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| ~ eau)H TURKEY POINT UNITS 3 5, 4 V1 AMENDMENT NOS.
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| i88AND182
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| I J
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| pl t'
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| LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION t
| |
| PP~ uC 8 4 S ufo unJ 3/4.4. 9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.........
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| FIGURE 3.4-2 TURKEY POINT UNITS 354 REACTOR COOLANT SY EA L
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| TATIONS (60 F/hr)
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| I'i APPLICABL'E UP TO EFPY FIGURE 3.4-3 TURKEY POINT UNITS 31I4 REACTOR COOLANT SY HEATU NITATIONS (100'F/hr)
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| IR APPLICABLE UP Pf EFPY.
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| ~
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| FIGURE 3.4-4 TURKEY POINT UNITS 3%4 REACTOR COOLANT SY 0
| |
| OMN LIMITATIONS (100'F/hr) s'r APPLICABLE UP 0
| |
| EFPY.
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| Pressur izer...........................................
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| Overpressure Mitigating Systems...........................
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| 3/4.4.10 STRUCTURAL INTEGRITY......................................
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| 3/4.4.11 REACTOR COOLANT SYSTEM VENTS..............................
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| PAGE 3/4 4-30 3/4 4-31 3/4 4-32 J
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| 3/4 4-33 3/4 4-35 3/4 4-36 3/4 4-38 3/4 4-39 3 4. 5 E
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| GENCY CO E COOLING S MS 3/4.5. 1 ACCUMULATORS..............................................
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| 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T~ GREATER THAN OR EQUAL TO 350 F......
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| 3/4 5-3 FIGURE 3.5-1 RHR PUMP CURVE........................................
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| 3/4 5-6 3/4.5.3 ECCS SUBSYSTEMS - T~ LESS THAN 350 F.....................
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| 3/4 5-9 3/4.5.4 REFUELING MATER STORAGE TANK..............................
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| 3/4 5-10
| |
| ~~6LF-Q $ -5 V ~C~o~
| |
| VESSEL RN'CRIRL S
| |
| g,ogigLApl~, PR0gjE',pg-YHDRAu'JAL SCHEDULE (OSLO P*O). 3/g TURKEY POINT - UNITS 3
| |
| : 5. 4 AMENDMENT NOS.170 AND 164
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| i'
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| SECIIQH 3/4.7. 1 TURBINE CYCLE Safety Valves
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| TABLE 3.7-1 HAXIMUH ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURI THREE LOOP OPERATION.........................
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| TABLE 3.7-2 STEAH LINE SAFETY VALVES PER LOOP...
| |
| Auxi1iary Feedwater System.
| |
| TABLE 3.7-3 AUXILIARY FEEDWATER SYSTEM OPERABILITY.
| |
| Condensate Storage Tank Specific Activity.................................
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| NG 3/4 7-1.
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| 3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-5 3/4 7-6 3/4 7-B TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIV AND ANALYSIS PROGRAH.
| |
| Main Steam Line Isolation Valves ITY SAMPLE Standby Steam Generator Feedwater System....
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| 3/4.7.2 COMPONENT COOLING WATER SYSTEM...............
| |
| 3/4.7.3 3/4.7.4 3/4. 7. 5 pO~
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| 3/4. 7. 6 3/4.7.7 3/4.7.8 3/4.7.9 SEALED SOURCE CONTAMINATION EXPLOSIVE GAS MIXTURE GAS DECAY TANKS...
| |
| ~
| |
| ~
| |
| ~
| |
| ~
| |
| ~
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| INTAKE COOLING WATER SYSTEM....
| |
| ~
| |
| ~
| |
| ~
| |
| ULTIMATE HEAT SINK............................
| |
| CONTROL ROOM EHERGENCY VENTILATION SYSTEM.
| |
| NUBBERS
| |
| ~
| |
| ~
| |
| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
| |
| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| S 3/4 7-9 3/4 7-10 3/4 7-11 3/4 7-12 3/4 7-14 3/4 7-15 3/4 7-16 3/4 7-18 3/4 7-22 I
| |
| 3/4 7-24 3/4 7-25 s~ueecp VISUAL. iespecqtppl ggyp j~~l,, p/q ~ ip~
| |
| TURKEY POINT UNITS 3 E
| |
| 4 X
| |
| AMENPMENT NPS 188 ANP182
| |
| | |
| 1 f
| |
| 1+
| |
| | |
| ~MD X
| |
| M TING COND TIONS FOR OP RATION AND SURV ILLANCE RE UIREHENTS
| |
| 'ECTION PAG 4.8 C
| |
| C POW R SYST M
| |
| 3/4.8.1 AC SOURCES ADD 0perating...............................
| |
| NOT USED
| |
| ~ ~ ~ ~
| |
| ~ ~
| |
| ~ ~ ~ ~
| |
| ~
| |
| ~ ~ ~ ~ ~ ~
| |
| Shotdown...........................................
| |
| TABLE 4.8-1 3/4.8.2 DC SOURCES 0perat~ng.........................................
| |
| hUtdown................................'..................
| |
| S 3/4.8.3 ONSITE POMER DISTRIBUTION 0perating.....................
| |
| TABLE 3.8-1
| |
| .U TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS......................
| |
| 3/4 8-1 3/4 8-10 I
| |
| 3/4 8-11 3/4 8-13 3/4 8-16 3/4 8-17 3/4 8-18 TABLE 3.8-2
| |
| ~
| |
| ~ ~ ~ ~ ~
| |
| ~
| |
| ~
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| ~ ~
| |
| ~
| |
| ~
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| ~
| |
| ~
| |
| ~ ~ o 3/4 8 21 Y ~
| |
| ~
| |
| ~
| |
| ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~
| |
| ~ ~ ~ ~ ~ ~ ~
| |
| ~
| |
| hutdown..................................................
| |
| S 3/4 8-22 3/4 8-23 POD APPLlCAel 6, To urv>T '3 Base o oN unfT + Lo~&
| |
| /Cla TELIC HoToR Co TRow gsmyeR g NOPE &ABLE' Ll oWA BLE, ouTAge APpLlCABLE To u>>T ~
| |
| BASE 0 o/4 ul4(j 5 LoA~
| |
| 04NTEg5 H OTO R
| |
| %a TROl l
| |
| OP~ <+SLE.
| |
| A LLoMAe LE
| |
| ~~TAGC Wit4FS TURKEY POINT - UNITS 3 5 4 X1 AMENDMENT NOS.159 AND 153
| |
| | |
| (OELETED)
| |
| TURKEY POINT UNITS 3 5
| |
| 4 AMENDMENT NOS.188 AND182
| |
| | |
| 1
| |
| )
| |
| il
| |
| | |
| DESIGN FEATURES SECTION INDEX PAGE
| |
| : 5. 1 SITE
| |
| : 5. 1. 1 EXCLUSION AREA.
| |
| 5.1.2 LOW POPULATION ZONE 5.1.3 MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5-1 5-1 5-1
| |
| : 5. 2 CONTAINMENT
| |
| : 5. 2. 1 CONFIGURATION.........
| |
| 5.2.2 DESIGN PRESSURE AND TEMPERATURE....
| |
| FIGURE 5.1-1 SITE AREA MAP.
| |
| FIGUR E 5. 1-2 PLANT'REA MAP 5-1 5-1 5-2 5-3 5.3 REACTOR CORE
| |
| : 5. 3. 1 FUEL ASSEMBLIES 5.3.2 CONTROL ROD ASSEMBLIES 5-4 5-4 5.4 REACTOR COOLANT SYSTEM 5.4. 1 DESIGN PRESSURE AND TEMPERATURE..........
| |
| 5.4.2 VOLUME 5-4 5-4
| |
| : 5. 5 METEOROLOGICAL TOWER LOCATION.
| |
| 5-4 5.6 FUEL STORAGE
| |
| : 5. 6. 1 CRITICALITY.
| |
| : 5. 6. 2 DRAINAGE
| |
| . 6. 3 CAPACITY.
| |
| 5.
| |
| 5-5'-6 5"6
| |
| : 5. 7 COMPONENT CYCLIC OR TRANSIENT LIMIT...........................
| |
| TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS..................
| |
| 5-6 5-7 TURKEY POINT - UNITS 3 8'
| |
| XX1 giY AMENDMENT NOS 137AND 132
| |
| | |
| ADMINISTRATIVE CONTROLS INDEX SE'CTION 1
| |
| RESPONSIBILITY...
| |
| PAGE 6-1
| |
| : 6. 2 ORGANIZATION...
| |
| 6-1
| |
| : 6. 2. 1 ONSITE AND OFFSITE ORGANIZATION.
| |
| 6.2.2 PLANT STAFF..........
| |
| TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION..
| |
| 6.2.3 SHIFT TECHNICAL ADVISOR..
| |
| 6-1 6-2 6-4 6"5 6.3 FACILITY STAFF UALIFICATIONS...........:.....
| |
| 6-5
| |
| : 6. 4 TRAINING...
| |
| 6-5a-I
| |
| : 6. 5 REVIEW AND AUDIT.
| |
| 6.5. 1 PLANT NUCLEAR SAFETY COMMITTEE Function..
| |
| Composition.
| |
| ~........
| |
| Alternates...................
| |
| Meeting Frequency.
| |
| Quorum.
| |
| Responsibilities...
| |
| Records............
| |
| ~.
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| ~
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| 6-5~
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| I 6"6 6-6 6-6 6-6 6"6 6-8 TURKEY POINT - UNITS 3 8
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| 4 XX1 pfLAC ppD AMENDMENT NOS.l37AND 132
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| | |
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| A Consultants...................;...........'...........
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| ~ e ~ ~
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| ~ ~
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| ~
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| Heeting frequency...........................................
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| 6.5.2 COHPANY NUCLEAR REVIEW BOARD unCtiOneooooooooooooooo
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| 6e10 6e11 6.5.3 TECHNICAL REVIEW AND CONTROL Activities 6-11 6-12 6-12 6-13 6-18 I
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| 6.9 1
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| ROUTINE REPORTS...
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| Startup Report Annual Reports Annual Radiological Environmental Op Annual Radioactive Effluent Release Honthly Operating Report....
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| Peaking Factor Limit Report.........
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| crating Report..........
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| Report...........
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| ~ ~ ~ ~
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| ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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| ~
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| Core Operating Limits Report......................
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| 6.9.2 SPECIAl. REPORTS..............
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| ee18 I
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| 6-18 I
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| 6e19 I
| |
| 6-20 I
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| eezo I
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| eeZO I
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| eeZ3 I
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| TURKEY POINT - UNITS 3 5 4
| |
| xxiii I
| |
| POD AHENDHENT NOS.192 AND 186
| |
| | |
| II'
| |
| | |
| ~ ~ 0 ~ 00 ~ ~ 0 ~ 00 ~ 0 ~ 00 ~ ~ ~ ~ ~ ~ ~ ~
| |
| 0 ~ ~ ~ ~ ~ ~ ~
| |
| 6-24
| |
| ~ 0000 ~ ~ ~ 00 ~ 000 ~ 00 ~ 00 ~ 0 ~ 00 ~ ~ ~
| |
| ~ ~ ~ ~ 0 ~ ~ ~ 0 ~ ~ ~
| |
| ~ ~
| |
| 6-24 t
| |
| 0 ~ 0 ~ ~ 0 ~ ~ 00000
| |
| ~ 00 ~ ~ ~ ~ ~ ~ ~ 0 ~ 0 ~ 0000
| |
| ~
| |
| ebs.
| |
| I 6026 I
| |
| TURKEY POINT - UNITS 3 E 4 OE. LB<~
| |
| xx<v AHENOHENT NOS.192AND 186
| |
| | |
| r'P t
| |
| t
| |
| | |
| REACTIVITY CONTROL SYS BORATED MATER SOURCES - OPERATING LIt1ITING CONDITION FOR OPERATION
| |
| : 3. l. 2. 5 The following borated water sources shall be OPERABLE:
| |
| a.
| |
| b.
| |
| A Boric Acid Storage System with:
| |
| 1)
| |
| A minimum indicated borated water volume in accordance with Figure DELETE.
| |
| i)
| |
| ELETE')
| |
| A boron concentration in accordance with Figure 3~~
| |
| and 3)
| |
| A minimum boric acid tanks room temperature of 55 F.
| |
| 5 i
| |
| 2 Qp.
| |
| The refueling water storage tank (RMST) with:
| |
| 1)
| |
| A minimum indicated borated water volume of 320,000 gallons, 2)
| |
| A minimum boron concentration of 1950 ppm, 3)
| |
| A minimum solution temperature of 39'F, and 4)
| |
| A maximum solution temperature of 1004F.
| |
| - APPLICABILITY:
| |
| MODES 1, 2, 3, and 4.
| |
| ACTION:
| |
| Mith the required Bor'.c Acid Storage System inoperable verify that the RMST is OPERABLE; restore the system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours* and borated to a SHUTDOMN NRCIN equivalent to at least 1X hk/k at 200'F; restore the Boric Acid Storage System to OPERABLE status within the next 72 hours or be in COLD SHUTDOWN within the next 30 hours.
| |
| b.
| |
| C.
| |
| Mith the RWST inoperable, restore the tank.to OPERABLE status within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLO SHUTDOWN within the following 30 hours.
| |
| Mith the boric acid tank inventory concentration greater than 3.5 wtX, verify that the boric acid solution temperature for boration sources and flow paths is greater than the solubility limit for the concentration.
| |
| If this action applies to both units simultaneously, be in at least HOT STANDBY within the next twelve hours.
| |
| TURKEY POINT - UNITS 3 5 4 3/4 1-14 AMENDHENT NOS. 144 AND 139
| |
| | |
| BOR I
| |
| D LRTe Figure S.1MW 8 1->
| |
| C ACID TANK MINIMUM VOLUME (1)
| |
| Modes 1,2,3 and 4
| |
| M 0
| |
| 0 0
| |
| U Q
| |
| 0 16 15 1 4 13 12 15,000 10,400 Acceptable Two Operatio 13,200 Accept ble One Unit Op ration (2)
| |
| Unit 1,800 0
| |
| E E
| |
| 10 9
| |
| 8 9,500 Una c ceptable rQtign 8 800 3.25 wt.%
| |
| 3.5 wt.% >3.5 WT.%
| |
| (5682ppm)
| |
| (6119pprn)
| |
| ERAT Inventory Concentration 3.0 wt.%
| |
| (5245pprT1) 3/4 1 14 a Minimum Acceptable Minimum Acceptable Two Unit Operation One Unit Operation Notes; (1) Combined volume of all available boric ocid tanks assuming RW'ST, boron concentration greater than or equal to 1950 pprn.
| |
| (2) Includes 2900 gallons for shutdown unit.
| |
| TUP.KEY POINT - UNITS 3 8
| |
| 4 Amendment Nos.
| |
| 144 and 139
| |
| | |
| 0
| |
| | |
| PLANT SYSTEMS (i'T 3/4.7.6 SNUBBERS-LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers shall be OPERABLE.
| |
| The only snubbers excluded from the requirements are those installed on nonsafety"related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
| |
| APPLICABILITY:
| |
| MODES 1, 2, 3, and 4.
| |
| MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
| |
| ACTION:
| |
| With one or more snubbers inoperable on any system, within 72 hours replace or re-store the inoperable snubber(s) to OPERABLE status and perform an engineering eval-uation per Specification
| |
| : 4. 7. 6f.
| |
| on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
| |
| SURVEILLANCE RE UIREMENTS 4.7.6 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in addition to the require-ments of Specification
| |
| : 4. 0. 5.
| |
| ~li T
| |
| As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
| |
| b.
| |
| C.
| |
| Visual Ins ections Po
| |
| '~,7 Z
| |
| Snubbers are cat r'd as inaccessible or accessible during reactor operation.
| |
| Ea of these categories (inaccessible and accessible) may e inspected 'e ndently according to the schedule determined by Tabl 4.7-1.
| |
| Th visual inspection interval for each type of scrubber s all b
| |
| determined based upon the criteria provided in Table
| |
| . -1 n
| |
| the first inspection interval determined using this criteria s all be based upon the previous inspection interval as established by the requirements in effect before Amendment 151 Pnd 146.
| |
| Visual Ins ection Acce tance Criteria Visual inspections shall verify that:
| |
| (1) the snubber has no visible indi-cations of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
| |
| Snubbers which appear inoperable as a result of visual TURKEY POINT - UNITS 3 5 4 3/4 7-18 AMENOMENT NOS.[ST ANO
| |
| | |
| be,Lowe TABLE 4. 7-1
| |
| + ~ 7 g.
| |
| SNUBBER VZSUAL ZNSPECTZON INTERVAL NUMBER OP UNACCEPTABLE SNUBBERS Population or Category (Notes 1 and 2)
| |
| Column A Extended Znterval (Notes 3 and 6)
| |
| Column B
| |
| Repeat Znterval (Notes 4 and 6)
| |
| Column C
| |
| Reduce Znterval (Notes 5 and 6) 80 100 150 200 300 400 500 750 1000 or greater 12 20 29 0.
| |
| 12 18 24 40 56 13 25 36 78 109 Note 1:
| |
| Note 2:
| |
| Note 3:
| |
| Note 4:
| |
| Note 5:
| |
| The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval.
| |
| Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
| |
| These categoxies may be examined separately or jointly.
| |
| : However, the licensee must make and document that decision befoxe any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
| |
| Znterpolation between population or category sizes and the number of unacceptable snubbers is permissible.
| |
| Use next lower integer for the value of the limit for Col.umns A,
| |
| B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
| |
| Zf the number of unacceptable snubbers is equal to or less that the number in Column A, the next inspection interval may be twice the previous interval but not greater that 48 months.
| |
| Zf the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
| |
| Zf the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
| |
| However, if the number of TURKEY POINT UNITS 3
| |
| ANO 4 3/4 7-18a AHEN04ENT NOS. ]5]}}
| |