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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20199J6981997-11-11011 November 1997 Rev 2 to 10CFR50.59 Review for Jet Pump Thermal Sleeve Cracking ML20202H1231997-09-30030 September 1997 Small Project Joint Permit Application & Attachments for PECO Energy Co,Peach Bottom Atomic Power Station,Rock Run Creek Low Flow Crossing, to Satisfy PA Dept of Environ Protection & Us Army Corps of Engineers ML20129E8711996-09-26026 September 1996 Rev 0 to 10CFR50.59 Review for Ncr Pb 96-03414,Core Spray T-Box Cracks for Peach Bottom Atomic Power Station,Unit 2 ML20117E6251996-05-31031 May 1996 Seismic Safe Shutdown Equipment List for PBAPS Units 2 & 3 ML20117E6321996-05-31031 May 1996 USI A-46 Relay Evaluation Rept for PBAPS Units 2 & 3 ML20117E6351996-05-31031 May 1996 Seismic Evaluation Rept for Pbaps ML20129A4511996-01-11011 January 1996 Core Spray Sparger Downcomer Modification ML20129A4731995-12-11011 December 1995 Fabrication of Core Spray Line Downcomer Clamp ML20098B1211995-09-30030 September 1995 Residual Stress Analysis of Peach Bottom Unit 3 Core Spray Pipe to Sleeve Fillet Weld ML20098B1141995-09-30030 September 1995 Evaluation of Peach Bottom Unit 3 Core Spray Line ML20092M8921995-09-30030 September 1995 Shroud Vertical Team Weld Evaluation ML20092J8151995-09-15015 September 1995 Core Spray Line Tee-Box Analysis Rept for Peach Bottom Atomic Power Station Unit 3 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20092K9871995-06-13013 June 1995 Rev 3 to Shroud Stabilizer Hardware ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20077M0951995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Pbaps,Units 2 & 3 ML20077M0861995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for RPS for PBAPS, Units 2 & 3 ML20073J7501994-09-30030 September 1994 Shroud Mechnical Repair Program,Peach Bottom Shroud & Shroud Repair Hardware Stress Analysis ML20079S0911994-09-29029 September 1994 Rev 0 to Application of Screening Criteria ML20073J7411994-09-24024 September 1994 Rev 0 to Stress Rept 25A5607, Shroud Stabilizers ML20072P5791994-08-26026 August 1994 Power System Harmonic Study for Peach Bottom Nuclear Power Plant, Final Rept ML20072L9631993-12-13013 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit-2 Shroud ML20064K4291993-12-0303 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit 3 Shroud Indications ML20059L1391993-11-30030 November 1993 Core Spray Crack Analysis for Peach Bottom Unit 3 ML20059G0901993-10-27027 October 1993 Evaluation & Screening Criteria for Peach Bottom Unit-3 Shroud Indications ML20149G0401993-05-30030 May 1993 Fatigue Evaluation of Peach Bottom II & III Reactor Vessels ML20073D0221991-04-30030 April 1991 Full Structural Weld Overlay Design for Peach Bottom Unit 2 RWCU Weld 12-I-1D ML20073E5881991-04-30030 April 1991 Revised Station Blackout Analysis ML20055J3231990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3271990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co. ML20044H3281990-02-23023 February 1990 Rev a to 30-Month Stability Spec for Rosemount Models 1152, 1153 & 1154 Pressure Transmitters. ML20247N3951989-05-16016 May 1989 Methods for Performing BWR Reload Safety Evaluations ML20236A8501989-01-31031 January 1989 Voltage Regulation Study ML20236A8351989-01-31031 January 1989 Rev 1 to Peach Bottom Atomic Power Station Units 2 & 3, Verification of Calculated Auxiliary Distribution Sys Voltages by Test ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20151M5501988-07-15015 July 1988 Security Problem Root Cause Assessment ML20147A7971988-02-23023 February 1988 Root Cause Investigation of Shutdown Cooling Isolations Peach Bottom Atomic Power Station ML20148H1211988-01-15015 January 1988 Rev 0 to Peach Bottom Atomic Power Station,Units 2 & 3, Response to IE Bulletin 85-003 ML20149D6981988-01-13013 January 1988 Methods for Performing BWR Steady-State Reactor Physics Analyses ML20196K0311987-12-31031 December 1987 1987 Annual Plant Mod Rept,Per 10CFR50.59 ML20236V3311987-11-20020 November 1987 SAR for Peach Bottom Atomic Power Station Spds ML20236J7141987-10-28028 October 1987 Commitment to Exellence Action Plan Status Rept ML20235H5601987-09-0909 September 1987 Methods for Performing BWR Sys Transient Analysis ML20236D1271987-09-0303 September 1987 Rev 0 to Safety Evaluation for Mod 2085,Peach Bottom Unit 3 ML20236K6081987-07-15015 July 1987 Rev 1 to Evaluation of Insulated Blind Barrel Splices on Dual Voltage Motors in Limitorque Actuators 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
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AN AI,Y T;I 5 nF FEFD AND rnNDFNSATE 7YSTEM: PEACHDOTTON May 20, 1987 Pumpcom 1: fluidic stress-monitoring (
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- f. e e d - wa t e r The purpose o f. thid study was to model the system of Peacht>ottom 2, ut ili si ng a Pumpcoin 1 modeling cyatem, and analyze normal and abnor ma l f low phe nomena , and any other generic issues which may become apparent, that could compromise plant uafety. Pumpcom 1 was utilised i because, it is the only system currently available that can i study " secondary flow events" in real-time. Because l Peachbottom 2 is a BWR, not a PWR, the pressures and I temperatures are different, hence, the matter-energy matrix ( I the primary element of a Pumpcom model) was considerably (
different. However; in those areas of the feed-water system )
where the matter-energy matrix approximated that of a PWR, similar flow-patterns were identified. Fortunately, all of these areas are defined by pumps, where they can be phys wally isolated from the system using valves, or monitored with simple instrumentation.
Method:
Pumpcom models are constructed in such a way as to i measure fluid-stress. By this we mean the concentration of {
energy per un!t mass & volume. The proper execution of a l Pumpcom model, requires the entry of the physical / energy characteristics and cross-section of the entire fluid path.
By necessity, the linear interval must be extremely small if l the report is to be useful. For this model, the intervals ranged from one foot for straight pipe, to one thousandth of ;
an inch, in pump interiors. This model assumes a regular j gecmetric structure to the fluid, developed from principles !
of synergetic-energetic geometry. The technique requires us j to compare the known physical dimensions of the containment, ;
to a measured input of energy, either thermal or mechanical.
The comparison is achieved by normalizing the energy-density per unit-volume to a reference source, then normalizing the ;
mass-density to the same reference source. In the final j step, the two ratios are compared to each other, giving a ratio-of-ratios (RAT). The closer that this ratio (RAT) is to unity, the more stable the system. Ratios greater than 1 normally indicate turbulent c o nd i t i o ns or cavitiation, while ratios less than 1 signify re-circulation or stratifled-flow.
MAJOR SYSTEMS:
870911002807%77 ADOCK g
PDR PDR P
velocitieu through out the drain-coolers were below
- 10. f eel-per -uecond under all normal operating conditions.
The m.itter-energy ratio was also low. When we compared the mass normallned ( ha rd mode 1) to t. h e energy normalized ( soft model) w. - ,4 c h t e v e d .i r..itto (RAT) of 1.04. This represents a stable system. The maximum RAT occurred at the cooler inlet and is not significant. For this flow to be destructive, we would have to see a RAT of 1.6 or greater. This would occur if flows increased approximately 40% or the temperature rose by 86%, above the maximum design limits. This would also-occur if flows were at 33% of full-load and the temperature was less than 250 degrees F.
B. FEEDWATER HEATERS:
During normal to maximum flow conditions, the feed-water heaters have stable flow, including the inlat and discharge flanges. However, during partial load ( flow = %40 normal) we indicate a RAT of 1.7 to 1. 8 3 a t the first 15 degrees of are of the tube bends, and the last 30 degrees. This is cavitation, although not destructive unless sustained for long periods, such as 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or longer. Because of tube geometry and the local temperature and velocity, this came close to the RAT of 4.66 that occurred at Surrey. If velocity increases 130 above normal, while temperatures remain sub-normal, an exaggerated flow pattern that we call a
wo r m" would result. This is a convoluted, triple vortex tuat is of sufficient strength to remove substantial amounts of pipe-wall, as happened at Surrey [ opinion of author]
This could occur if the system runs at low-load wl.h high-condensate flows, such as occurs during an increase in load, but it is seen as an intermittent phenomenon.
FEEDWATER PUMP:
These pumps are Byron-Jackson 14 x 14 x 17 DVSR, double-suction single stage pumps. The PUMPCOM model divided these pumps into 150 parts. As we said earlier, as a SYSTEM, Peachbottom 2 has a lower matter-energy density than a PWR, and consequently, exhibits different micro-flow patterns.
However, the pumps, internally, have the same matter-energy density as a PWR and exhibit the same micro-flow patterns. ,
In our opinion, an analysis of this regime, in general, is in order.
The pumps were stressed to three modes of operation.
These are:
- 1. low flow- defined as %30 of Best-Efficiency-Point: 2700 GPM
- 2. Normal flow- defined as 195 of BEP: 9000 GPM
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I T. high flow- defined a6 't.12 0 O f DEP : 10000 GPM 1.OW FLOW:
At Lh1s f1aw, the pump experienced blgh leve.u of inlet-eye recirculation, with a RAT of 3.88 to S.70. The RAT's. oscillated at a frequency of 3 hert and an amplitude of 13 mils. This is a sufficiently strong axial motion.to 3 cause premature bearing failure. The pump is equipped with fluid-film bearings which are.more tolerant of this condition .
than rolling-element bearings.
As a consequence of the inlet-eye recirculation, there is )
cavitation. This is concentrated along the vane / shroud l I
Junction on the top 4 inches of the vane tip.
NORMAL FLOW:
This pump was well-designed for this application. It shows no abnormal or destructive flow patterns at all. There is however; a vortex which forms in the inlet cavity during flow or temperature transients. This is not harmful by ,
itself. But, if the bearings are already damaged, this can cause seizure.
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HIGH FLOW:
This pump ebould never be run at high flow. Cavitation occurs over 165 of the vane area. More importantly, there is an alternating area of cavitation in the area defined by the outer surface of the shroud and the casing wall. This In addition, a imposes axial pulse-loads on the bearings. I precessing vortex forms near the vane-tips and imposes a radial load. .i l
I CONDENSATE PUMP:
This pump is an Ingersoll-Rand Model APKD, seven-stage vertical can pump. These pumps have mixed-flow impellers, stacked and hung vertically inside a scaled can. This is done to insure adequate submergence and NPSH. These pumps operate in a specific speed range best served by radial-flow impellers. Because their impellers have a substantial axial-flow component, they are more prone to damage at low flows. This-pump was also tested in low, normal and high
- flow conditions,and the results were similar in all cases.
This pump requires an increasc in NPSHA of 15 feet.
Swirling of the water entering the first stage distorts the entrance angle 15 degrees, resulting in a pre-mature flow u__.___._m_ ____
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1 ueparation. The dlhedral of the impeller causes high i velocities along the impeller outer edge and deceleration I j
along the inner edge This causes a flow reversal in the first stage The consequence of this is a small (about 112) I teduction in flow that causes cavitation in the following I stages At low flow, this pump cavitates in stages 2,3, and I
- 4. At normal flow there is inild, intermittent cavitation in stage 3 or 4. At high flow there is cavitation in stages 1, 6 and 7. Since a vertical can pump is not hydraulicly balanced, cavitation always results in radial loads and intermittent up-thrusts. The up-thrusts occur during flow or temperature changes, and always cause bearing wear / damage / seizure. Periodic visual inspection of the top bearing would be in order. f I
MAJOR VALVES A!iD PIPING:
No significant flow phenomena were produced at any power level. The maximum RAT recorded was 2.1 at high flow in a check valve on the feed and condensate discharge lines. This is not abnormal, nor damaging. No "Surry-type" worm was evident in any of the elbows. Particular attention was given to elbows following a "T" junction. RAT't did not exceed 1.35.
CONCLUSION: Iopinion1 The Peachbottom 2 condensate and feed system does not show any flow patterns that would be expected to lead to catastrophic-type failures, in general, nor any characteristics that could cause a surry type of failure.
While such micro-flow patterns were observed, they were inside pumps, where they manifest themselves as excessive bearing wear. This is readily observable and easily monitored with vibration or temperature probes.
Pampcom Inc. is grateful for this opportunity, and we ,
hope we will be informed of the results of any field testing of this plant.
RUDOLPH BEHRENS, president
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