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Category:ARCHIVE RECORDS
MONTHYEARML20202B5081999-01-0808 January 1999 Rev 2 to Calculation M-734, RHR & Core Spray Pump Suction Strainer Debris Head Loss NPSH Evaluation ML20217H3291998-02-23023 February 1998 Rev 0 to Calculation M-778, Evaluation of RPV Flange to Adjacent Shell 145 Deg F Differential Temp Limit ML20202B4981997-12-22022 December 1997 Rev E3 to Calculation M-662, RHR & Core Spray Pump NPSH & Suction Pressure Drop ML20203A1231997-12-18018 December 1997 Rev 3 to M500, Range of Salt Svc Water Sys Header Pressures & Pump Flows ML20203A1111997-11-21021 November 1997 Rev 0 to M-771, RBCCW Heatup Immediately Following DBA- Loca ML20148T5101997-04-11011 April 1997 Rev E2 to Calculation M-662, RHR & Core Spray Pump NPSH & Suction Pressure Drop ML20137W2901997-04-11011 April 1997 Rev 0 to RHR & Core Spray Pump Suction Strainer Debris Head Loss NPSH Evaluation ML20133N6071996-03-20020 March 1996 Rev E1 to RHR & Core Spray Pump NPSH & Suction Pressure Drop ML20141D2521996-01-19019 January 1996 Rev 4 to PS-79, EDG Loading ML20249B4451996-01-0404 January 1996 Rev 0 to Calculation C15.0.3270, Fuel Pool Cooling He E206A & E206B GIP Evaluation ML20249B4461996-01-0404 January 1996 Rev 0 to Calculation C15.0.3273, RHR Heat Exchanger E207A & E207B GIP Evaluation ML20092G9381995-06-29029 June 1995 Scram Times for Tech Spec 3.3.C.1 ML20117K8601994-01-31031 January 1994 Rev 0, Fragility Analysis of SBO Dg,Pilgrim Nuclear Power Station ML20249B4731994-01-0808 January 1994 Rev 0 to Calculation C15.0.3216, LAR 016 Location:Reactor Bldg Ei 23'-0 ML20249B4661993-11-0808 November 1993 Rev 0 to Calculation C15.0.3216, LAR 017 Location:Reactor Bldg El 37'-0 ML20249B4811993-11-0606 November 1993 Rev 0 to Calculation C15.0.3216 for LAR 024 Location:Aux Bay Bldg Ei 3'-0 ML20249B4541993-10-25025 October 1993 Rev 0 to Calculation C15.0.3216, LAR 005 Location:Turbine Bldg Ei 37'-0 ML20058P2211993-07-29029 July 1993 Package Consisting of Attachment to Employee Concerns Programs ML20117K8511993-06-30030 June 1993 Ipeee,Building Structures Fragility Analysis. Rev 1 ML20065L7941993-06-0404 June 1993 Reactor Building Seismic Model ML20064K8411993-01-26026 January 1993 Soil Properties for SSI Analysis for Pilgrim Site ML20099B5521992-05-0505 May 1992 Audit 92050S, Scientific Ecology Group Supplier Implementation & Qualification, Conducted on 920324-27 ML20118A3561992-03-24024 March 1992 Scientific Ecology Group,Supplier Implementation & Qualification Audit 92050S ML20086T2241991-12-19019 December 1991 Boston Edison Pilgrim BWR Plan RWCU Sys Evaluation of Crack Growth & Stability for 4-Inch Pipe to Elbow Weldment ML20079M9561991-11-11011 November 1991 Response to NUMARC Auquatic Resource Questions,Socioeconomic Questions for All Utils & Waste Mgt Questions ML20011F4471990-01-19019 January 1990 Salt Svc Water Pump P208A,Casing Stresses Due to Accidental Drop. ML20011F4721990-01-19019 January 1990 Operability Evaluation of Salt Svc Water Pump Columns. ML20079M9811989-12-31031 December 1989 Response to NUMARC Survey Re Approximate Number & Cause for Most Notable Fish Mortalities at Pilgrim Nuclear Station for Period of 1973-1989 ML20106A6371989-03-0303 March 1989 Spec C-114-ER-Q-EO, Pilgrim Unit 1 Spec for Seismic Response Spectra ML20151W1811988-08-16016 August 1988 Attachment I to Ltr,Consisting of Response to Allegation a Re Deliberate Reduction of Radiation Survey Results to Avoid Further Surveys ML20238E6921987-12-30030 December 1987 Packages Consisting of marked-up Rev 0 to Safety Evaluation 2144 & Slides of Facility Safety Enhancement Mods ML20236R0801987-11-18018 November 1987 Package Consisting of Viewgraphs Re Util Simulator Status, Requalification Plans for Reactor Operators/Senior Reactor Operators Prior to Startup,Training Schedule & Control of Reactor Operator/Senior Reactor Operator Overtime ML20236N8471987-11-12012 November 1987 Package of Documents Re Util Actions Concerning ATWS, Including Purchase Orders,Correspondence W/Ge,Work Instructions,Field Rev Notices & Maint Requests ML20236Y6151987-11-0505 November 1987 News Article Re Shutdown of Facility for Six More Wks to Deal W/Mgt Troubles ML20237A1151987-11-0505 November 1987 FSAR Section 5, Containment ML20236K8561987-07-22022 July 1987 Calculation M-300 Re Cable Fire Heating of Torus Compartment Ceiling Beams ML20236Y6171987-07-0909 July 1987 Newsarticle Entitled, Judges Asked to Limit Pilgrim Picketing ML20237A0171986-06-28028 June 1986 Newsarticle Entitled, Two Towns Want Out of Pilgrim Evacuation Plan ML20237A0551986-06-27027 June 1986 Newsarticle Entitled, Dept of Public Utils Blasts Edison, Cites 'Paralysis' at Top ML20237A0461986-06-24024 June 1986 News Article Entitled, Edison Says Pilgrim Missed Another Deadline for Safety Tests ML20237A1661986-06-21021 June 1986 Jm Hendrie Ltr to Editor of Ny Times Re D Ford & R Pollard 870519 Advertisement Trying to Draw Similarities Between GE Reactors & Chernobyl Nuclear Reactor & Warning of Safety Problems,Based on Hendrie & Hanauer Notes ML20237A0211986-06-0909 June 1986 Portions of Vol 8,Number 12 to Inside NRC Re Denton Urging Industry to Settle Doubts About Mark I Containments ML20237A0441986-05-26026 May 1986 News Article Re Chernobyl Accident & Difference Between Us & Soviet Plants ML20237A1961986-05-23023 May 1986 Newsarticle Entitled, Pilgrim on List of Worst-Run Nuclear Units ML20237A0511986-05-21021 May 1986 News Article Discussing NRC Announcement That Facility Will Remain Closed Until Util Corrects Safety Problems ML20236N0881986-05-19019 May 1986 Viewgraphs from 860519 Meeting Re Util Response to Confirmatory Action Ltr CAL-86-10,860612 Program for Excellence Task Force Rept & Facility Operation ML20235S1511986-04-25025 April 1986 Preliminary Critical Path Projection for RF07 ML20207G2661986-04-19019 April 1986 Package of Documents,Including Aii Exit Notes,Rhr Containment Isolation Leakage Notes,Comments on Util Response to Confirmatory Action Ltr 86-10 & Partially Deleted Inspector Notes for Rept 50-293/86-17 ML20236K2221986-04-12012 April 1986 Package of Handwritten Excerpts from NRC Headquarters Operations Officer Log Re Leakage Past Two Isolation Valves Reportable Event Numbers 04196 & 04198 ML20237A1981985-06-18018 June 1985 Newsarticle Entitled, NRC Says Pilgrim Skipped Routine Tests 1999-01-08
[Table view] Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20202B5081999-01-0808 January 1999 Rev 2 to Calculation M-734, RHR & Core Spray Pump Suction Strainer Debris Head Loss NPSH Evaluation ML20217H3291998-02-23023 February 1998 Rev 0 to Calculation M-778, Evaluation of RPV Flange to Adjacent Shell 145 Deg F Differential Temp Limit ML20202B4981997-12-22022 December 1997 Rev E3 to Calculation M-662, RHR & Core Spray Pump NPSH & Suction Pressure Drop ML20203A1231997-12-18018 December 1997 Rev 3 to M500, Range of Salt Svc Water Sys Header Pressures & Pump Flows ML20203A1111997-11-21021 November 1997 Rev 0 to M-771, RBCCW Heatup Immediately Following DBA- Loca ML20148T5101997-04-11011 April 1997 Rev E2 to Calculation M-662, RHR & Core Spray Pump NPSH & Suction Pressure Drop ML20137W2901997-04-11011 April 1997 Rev 0 to RHR & Core Spray Pump Suction Strainer Debris Head Loss NPSH Evaluation ML20133N6071996-03-20020 March 1996 Rev E1 to RHR & Core Spray Pump NPSH & Suction Pressure Drop ML20141D2521996-01-19019 January 1996 Rev 4 to PS-79, EDG Loading ML20249B4451996-01-0404 January 1996 Rev 0 to Calculation C15.0.3270, Fuel Pool Cooling He E206A & E206B GIP Evaluation ML20249B4461996-01-0404 January 1996 Rev 0 to Calculation C15.0.3273, RHR Heat Exchanger E207A & E207B GIP Evaluation ML20092G9381995-06-29029 June 1995 Scram Times for Tech Spec 3.3.C.1 ML20117K8601994-01-31031 January 1994 Rev 0, Fragility Analysis of SBO Dg,Pilgrim Nuclear Power Station ML20249B4731994-01-0808 January 1994 Rev 0 to Calculation C15.0.3216, LAR 016 Location:Reactor Bldg Ei 23'-0 ML20249B4661993-11-0808 November 1993 Rev 0 to Calculation C15.0.3216, LAR 017 Location:Reactor Bldg El 37'-0 ML20249B4811993-11-0606 November 1993 Rev 0 to Calculation C15.0.3216 for LAR 024 Location:Aux Bay Bldg Ei 3'-0 ML20249B4541993-10-25025 October 1993 Rev 0 to Calculation C15.0.3216, LAR 005 Location:Turbine Bldg Ei 37'-0 ML20117K8511993-06-30030 June 1993 Ipeee,Building Structures Fragility Analysis. Rev 1 ML20065L7941993-06-0404 June 1993 Reactor Building Seismic Model ML20064K8411993-01-26026 January 1993 Soil Properties for SSI Analysis for Pilgrim Site ML20086T2241991-12-19019 December 1991 Boston Edison Pilgrim BWR Plan RWCU Sys Evaluation of Crack Growth & Stability for 4-Inch Pipe to Elbow Weldment ML20011F4721990-01-19019 January 1990 Operability Evaluation of Salt Svc Water Pump Columns. ML20011F4471990-01-19019 January 1990 Salt Svc Water Pump P208A,Casing Stresses Due to Accidental Drop. ML20106A6371989-03-0303 March 1989 Spec C-114-ER-Q-EO, Pilgrim Unit 1 Spec for Seismic Response Spectra ML20236K8561987-07-22022 July 1987 Calculation M-300 Re Cable Fire Heating of Torus Compartment Ceiling Beams 1999-01-08
[Table view] |
Text
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B05 TON EDISON PILERIN BWR PLAM REACTOR WATER CLEAMIP $YSTEM s ..
Evaluation of crack Growth "
and $tability for a 4' Pipe to Elbow Weldsent C
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Evaluation of Crack Growth and $tability for a 4* Pipo to Elbow Weldat
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l Crack Stability Resulti _
l The resv'ts of the stability calculations are shown graphically in Figure 1= i These results are based on the fcilowing pipe stresses: l Pressure stress - 3505 psi e Deadweight stress = 130 psi Pm = 3635 psi (Pn will based on the Pres + Deadwt stresses)
Thermal stress e 1226 psi Fitup offset stress - 745 psi (20% of the Thermal stress) j Po - 1471 psi (Pe will be based on the Thermal 4 '
Fitupstresses) f The curves snown in Figure 1 shcw the region of stable crack gr4wth based on '
the requironants in Section XI of the ASHC Code. These calculations include safety factors (3F) as shown on the figure. Th6 SF of 2.77 is frr Normal ;
loacs and the SF of 1.39 is for Emergoney loads. These factors a safety ..
I are conservatisms that are include 0 in the calculations per the requirernents of the ASME Code.
Tne most conservative or Icwer bound result is obtained using a SF of 2.77.
For r is case the data used in plotting the figure indicate that a maximum
- crat- 1ength of 51.4% (of the circustrerence) is acceptable. As noted on the
~
ft;ure, tne current length of the crack 15 41.4%. This indicates that the l Crack is currently stable, even based on the Section XI methodnicgy which 'I
-conservatively includes the factors of safety mentioned above. m_
m.
Using the results from figure 1, the amount of crack growth restaining before the conservative criteria of Section XI is exceeded is;
(!1.4% + 41.4%) = 10.0f. cf the inside circumference
= 1.20 inches e
.cract powt,_ siculations
- Tne crack growth evaluation will be cased on data available for pipe (i.e.,
cylindrical) geometry. The appilcable relationship for the stress Intensity y
- fattor (K) 1s as folicws:
K=(5t)(Ft)8a; 5t = Tensile stress f t = Yariable cylindrical correction factor
- 2.5 for a crack length of 40% _
- 3.4 for a crack length of 50%-
For the present calculations it is conserva-tive to use a valua of M gw l
3[
l v.
I l-22.1/, - 402. - 002,o o @
m tyle!0c lit-II-it 110tii M i At!!:ti!0ta 09AMTRig 4th fdOHis 4 l
a
- d. .,
a = 1/2 the crack arciength. To tre conservative the cr&Ck length will be t&kan 48 the maxi.
fru'l stable length which was calculated aboyt ,
= ($1.4f.)/2 .
r=l3.535+1.471)(3.4)/i[TTiI)
= .4.1 kst/la The crack growth relatiership will be trAen from NURCC.0313. Figure 2. This I expressior and the resulting crack growth rate are as follows: i (da/dt)=3.59x10'x(X8.888) inch / hour a .000200 Irch/ hour since the crack can be expected to grew from both ends, the total extension of tre crack will be taken as twice the rate detennined above. L' sing'the l.a. 1.t lea;th available allo'=able operating for stable tiine (18)crac< can growth as computed te determined. above (latio,n is ), an This calcu provided belows ,
Ta . Allowable operating time -
= Javailable crack lengt /2(ds/<it)
- dt.2 in.)/(2 x .000200 ) Y ( # ^'* f )
= 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> = 17.9 week ,
This result is a conserystive estimation for the time the piping can be operated before the Section XI crack stability criteria are exceeded.
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. t ATTACHMENT 3 .
Page 1 of 1 l Regl For . i
.5 Valve Approx.(4) Motor Required Factor TST (2) Stall 801 Operator j Valve Size . Type- aP :or NRC Test Avaliable Voltace Max (3) OR/S.E.:S.F. (.2) !
r f
i 1201-2 Gate 6" Flex 1135 12000(1) 11515 14900 16800 52.2/.5/.0168 ;
Halworth-(AC) Hedge SMB-00-15 3
1201-5 Gate 6"- Flex 1135 21000(1) 17300 24800 28800 43.69/.5/.0210 l Anchor / Darling Hedge ;
(DC)'SMB-0-25 -
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{- (1) Approximate from USNRC (INEL) Tests, other valves not tested J
(2) Torque Switch is bypassed for 987. of closed stroke. The thrust values do not include VOTES error band MOV Users Group i -- (Draft) report shows 4.37. average at torque switch trip.
(3) Design + 207. F r
(4) AC is 0.64 x Stall. DC is 0.8 x. Stall
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