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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20155F4501998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Function Into Two New Functions in ITS Table 3.3.17-1 ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits ML20155F9551998-10-30030 October 1998 Proposed Tech Specs Pages to LAR 245,changing Methodology for Sf Pool B Criticality Analysis ML20154P3101998-10-16016 October 1998 Proposed Tech Specs Resolving USQ by Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1581998-09-30030 September 1998 Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR ML20238F4761998-08-31031 August 1998 Proposed Tech Specs,Proposing New Repair Process for Plant OTSGs ML20151X0431998-08-31031 August 1998 Proposed Tech Specs Adding Three Addl Reg Guide 1.97 Type a Category 1 Pami Variables & One Type B Category 1 Pami Variable to ITS Table 3.3.17-1, Pami ML20236V8831998-07-30030 July 1998 Proposed Tech Specs Pages Re CREVS & Ventilation Filter Test Program ML20236E9851998-06-30030 June 1998 Proposed Tech Specs Re Exigent License Amend Request 228,rev 1 for Once Through SG Tube Surveillance Program ML20249B2671998-06-18018 June 1998 Proposed Tech Specs Pages Re one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG Tubes ML20247P8931998-05-22022 May 1998 Proposed Improved Tech Specs 5.2.1 Re Onsite & Offsite Organizations ML20217P5181998-04-28028 April 1998 Proposed Tech Specs Re Reactor Coolant Pump Motor Flywheel Insp ML20217G0121998-04-23023 April 1998 Proposed Improved Tech Specs Section 5.7.2, Special Repts, Clarifying That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) ML20217C6341998-03-20020 March 1998 Proposed Tech Specs Re Editorial Changes to Improved TS Saftey Limits & Administrative Controls to Replace Titles of Senior Vice President,Nuclear Operations & Vice President, Nuclear Production W/Position of Chief Nuclear Officer ML20217C4931998-03-20020 March 1998 Proposed Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp ML20203D1611998-02-20020 February 1998 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS ML20198S9151998-01-22022 January 1998 Proposed Tech Specs Consisting of Rev 1 to TS Change Request 210,correction of Typo & Addition of Footnotes ML20202G8511997-12-0505 December 1997 Proposed Tech Specs Establishing New Improved TSs (ITS) Surveillance Requirement for Performance of Periodic Integrated Leak Test of Cche Boundary & Revising ITS Bases 3.7.12 to Define Operability of Cche ML20202G7991997-12-0505 December 1997 Proposed Tech Specs Revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal ML20199G8461997-11-21021 November 1997 Proposed Tech Specs Pages Involving Additional Restrictions, Editorial Clarifications & Typos ML20212F2741997-10-31031 October 1997 Proposed Tech Specs Pages Re Decay Heat Removal Requirements in Mode 4 ML20212C9801997-10-25025 October 1997 Proposed Tech Specs Re Power Operated Relief Valve Lift Setpoint TS Limit That Has Been Revised for Instrument Uncertainty ML20217F5231997-10-0404 October 1997 Proposed Tech Specs Pages Addressing Revision to Description of Electrical Controls for Operating Reactor Building (RB) Recirculation Sys fan/cooler,AHF-IC,as Discussed in FSAR & Improved TS ML20217D2741997-10-0101 October 1997 Proposed Tech Specs Adding Methodology to Monitor first-span Intergranular Attack (Iga) Indications & Disposition Growth During Future B OTSG Eddy Current Exams ML20210T9771997-09-12012 September 1997 Proposed Tech Specs Replacement Pages Re New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys ML20216F8481997-09-0909 September 1997 Proposed Tech Specs Re Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR ML20217Q2121997-08-26026 August 1997 Proposed Tech Specs Changing Design Basis of EDG Air Handling Sys ML20217N2501997-08-20020 August 1997 Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance ML20210K8921997-08-16016 August 1997 Proposed Tech Specs 3.8.1.3,requesting one-time Outage on Each EDG to Perform Necessary Mod & Maint ML20151L7541997-08-0404 August 1997 Proposed Tech Specs Extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified ML20196J1431997-07-29029 July 1997 Proposed Tech Specs Adding EDG Kilowatt Indication to post- Accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt ML20196H0281997-07-18018 July 1997 Proposed Tech Specs Changes Establishing Requirements for Low Temperature Overpressure Protection Sys ML20148K7811997-06-14014 June 1997 Proposed Tech Specs Re Efw,Hpi,Emergency Feedwater Initiation & Control Sys ML20138H8781997-05-0101 May 1997 Proposed Tech Specs Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J,Option B ML20137X5361997-04-18018 April 1997 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] |
Text
. . _. _ _ _ ~ _ . . _ _ _ _ _ _ _ - _ _ . _ -
- __ ___ ~ _ _ _ _ . _ _ ._ _ . _ _
Pag 2 7 of 10 ,f ATTACHMENT l l
2.5.2 Model Superposition 14ethod The modal superoositinn method elves a time history solution of l-the resnonse of an arbitrary structure to known nodal force or tround '
acceleration time histories. The structurir may include linear and nonlinear elements. The four types of nonlinear elements allowed, are 3 The uncoupled model eovations are i SilFM, SilFM, STIF2R and STIF42. ,
integrated analytically.
l 2.5.2.1 Model Suoerposition tiethod Theory l The equation of motion for a structure is: l (M) (5) + (C (2.5.2 1) g ) di + (Kg ) (X) = (F(t))
where (M)
(C) = damping matrix t
(Kt ) = stiffness matrix (F(t))
- nodal force or inertial force due to ground acceleration The damping matrix (Cg) and the stiffness matrix (Kt ) in Eq.
(2.5.2.1) are time dependent. This is due to the presence of nonlinear ;
elements in the structure. Let (Ct ) = (C) + (Cy) and (Kg ) = (K) + [K ,) (2.5.2-2)
(C) and IK) are time independent matrices consisting of the following:
- 1. damping and stif fness matrices of linear elements.
REY.R 2/10/82 2'b*II 9009040174 900823 PDR ADOCK 05000302 P PDC
.., Page 8 of 10 l
. i
- 2. dampino and stiffness matrices due to the initfel state of
)
the nonlinear elements. \
t (Cnt) and (Kn*,) are time deoendent matrices producedThe by chanoes I in the state of the nonlinear elements from their orteinal state. i substitution of (e. (2.5.2 2) into to. (2.5.2-1) nives: ;
(M) (5) + (C) (k) + (K) (1) * (F(t)) -[C,,) (k) - (K,,) (X)
(2.5.2-3) a (F ( t)) + (F ,,(X,0.W where ,
(2.5.2 4)
(F (X,i,t))
- nonlinear force = -(C 1 (i) - (K ) {XI Melrovitch,1967 (pp. 390-394), assumes that the dampino matrix, (C), can be reduced to a diagonal form by means of modal transformation.
be the naturs1 circular frecuency for the ith mode and ($) be the 1.et Wt matrix of modes, nomalized with respect to the mass matrix, associated with the eteenvalue problem:
r 0
(2.5.2 5)
' (4) (f) + (K) (X)
The coupled system of ecuations (2.5.2-3) is uncoupled by the linear transfomation (2.5.2-6)
(1) = (n) (c)
I Eq. (2.5.2 6) is substituted where (q) is a modal displacement vector.
in Eq.
(2.5.2 2) and the resulting equation is premultiplied by ($3T, These operations give the following uncoupled modal equations:
RE) R 2/10/82 2.5-12 l
L - - . - _ _ _ _ . _ _ _ _
- - Page 9 of 10 V
(')
d + D 2w ( *) (k) + N kl (Q) ii i
= (o[(F(t)) + [4[(F n.(X,k,t)) (2.5.2-7) ,
= (0) + {0n t.I where (a) = modal displacement vector w
g
= eicenvalue (i.e., the circular frequency) of the ith mode E
t
= model danpino for the ith node (Q) = generalized linear force vector
=
(+3T F(t)
(Ont)
= generalized, nonlinear force vector
=
(of(Fnt(X.X,t))
The ith nodal equation is:
V .. .
2 (2'5'2*8) 49 + ?>q ',j oj + 94qj*Q4+O n f,4 The yeneralized linear force, Qj, is due to the applied forces, in WECAN, during each time step, only linear variation of the
.spolied forcing function is allowed. So, the ceneralized linear force, Og, is represented as:
0 =C 3 +C (t-t ), t1<t<tg + t.t g
(2.5.2-9) 2j where l g =Ol g and Oi ltg + At 'O!i t g '[
0 *
. 2 ct !
4 V
REV.R 2/10/82 2.5-13
Pty;) 10 of 10 ,
i 6
The generalized nonlinear force, Onty.is due to the nonlinear elements This force is represented by the first tere of the in the structure. :
Taylor series (2.6.2 10)
=C (t t ), tg<t<t1 + at 0
q 3{ + C 4j 3 where C =Qnt l 3{ g *) !
3
~0 nt Ont4 l g\
t 3 t3 - at C
4{=
e 4
REY.T 7/1/84 2.5-14
ENCLOSURE 2 Page 1 of 2 CRYSTAL RIVER RACKS FPC RESPONSES TO INFORNAL NRC QUESTIONS The dose budget for Radiation Work Permit (RWP) 90 0144 for specific rack removal activities for the "B' spent fuel pool was determined using man hour estimates provided by the contractor and dose rates typically encountered in these work areas. This estimate was generated prior to commencement of the work in accordance with Crystal River Unit 3 Administrative Instruction (AI)-1600, "ALARA i' Program Manual."
Assumptions Nade in Generation of This Dose Budoett ;
- 1. The effective dose rate experienced for activities above the surface of the spent fuel pool will be 1 mrem /hr.
- 2. Equipment staging, setup, and removal performed in various areas of the Radiation Control Area (RCA) do not result in any appreciable dose.
- 3. Absence of any problems which could significantly increase project man hours.
The man hour figures supplied by the contractor for each rack are multiplied by the number of racks to be removed. No prov;sions are mada in the budget for any contingencies.
- 4. Dose rates from removed racks do not significantly increase General Area dose rates in the area of the spent fuel pool. (Removed racks are shipped on a timely basis and do not accumulate in or near the work area.)
- 5. Activities associated with installation of new high density fuel racks and their dose estimates are as follows:
! a. Refuel Floor Support Work (existing RWP) l l 0 Preparatory Activities:
l Equipment staging 64 man-hours negligible dose Equipment setup 64 man-hours negligible dose o Rack Removal Sequence:
Detorque/ remove anchor 150 man hours 0.100 man-rem nuts (25 man-hr/ rack at 1 mR/hr). Six racks will be removed from spent fuel pool "B".
Decontaminate, paint, 1,440 man hours 1.500 man-rem I
and prepare racks for l shipping (240 man-hr/ rack at I mR/hr).
ENCLOSURE 2 Page 2 of 2 o Pool Cleanup Activities:
Pool cleanup, etc. 128 man hours 0.100 man-rem at 1 mR/hr o Rack Installation:
New high density racks 2,560 man hours negligible dose installed, excluding diving work. A total of 8 racks will be installed.
(320manhr/ rack) o Acceptance Testing:
(8 man hr/ rack 64 man hours 0.050 man rem at 1 mR/hr)
- b. Diving Operations * -0.250 man rem (RWPtobewritten)
- c. Handling and Processing of Vacuum Filters * -1.500 man-rem (RWP to be written)
TOTAL
- The estimated dose budgets for these activities are based on available information.
Measures Utilized to Minimize Personnel Exposqtti
- 1. Health Physics Technician / worker review of NRC Information Notice 90-33 related to sources of unexpected exposures associated with spent fuel pool work activities.
- 2. Use of remote tooling to remove nuts from existing rack retainer bolts.
- 3. High pressure water decontamination of existing racks underwater prior to removal to reduce dose rates from surface contamination.
- 4. Strippable paint will be applied to the old racks to "fix" contamination in pla 9 to eliminate potential for skin exposures from hot particles.
- 5. Shipping of old racks intact. On-site cutting or other volume reduction techniques which may receive significant dose are not being performed.
- 6. Use of portable lead ' shielding racks to minimize dose rates from racks removed and stored on the 164 ft, elevation.
- 7. Cleanup of the spent fuel pool floor after rack removal to minimize diver dose rates from accumulated material there.
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