Core Spray Line Downcomer Repair Seismic Rept Summary for Peach Bottom Atomic Power Station,Unit 2,Mod P00335ML20129A430 |
Person / Time |
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Site: |
Peach Bottom ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
01/08/1996 |
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From: |
Gleason T GENERAL ELECTRIC CO. |
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To: |
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Shared Package |
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ML20129A406 |
List: |
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References |
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GENE-771-01-019, GENE-771-01-0196-R00, GENE-771-1-19, GENE-771-1-196-R, NUDOCS 9609180235 |
Download: ML20129A430 (4) |
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20199E8961997-10-31031 October 1997 Recirc Piping Reanalysis Uniform Support Motion (Reg Guide 1.60 Free-Field Motion & ASME Code Case N-411 Damping) ML20129A4301996-01-0808 January 1996 Core Spray Line Downcomer Repair Seismic Rept Summary for Peach Bottom Atomic Power Station,Unit 2,Mod P00335 ML20129A4101995-12-22022 December 1995 Core Spray Line Downcomer Repair Hardware Stress Assessment Rept for Peach Bottom Atomic Power Station Unit 2,Mod P000335 ML20069M6271994-06-30030 June 1994 End-Of-Cycle Recirculation Pump Trip Analysis for PBAPS Units 2 & 3 ML20128L4351992-11-30030 November 1992 Spent Fuel Storage K 00 Conversion Analyses ML20150E6371988-01-31031 January 1988 Errata to NEDO-24082, LOCA Analysis for Peach Bottom Atomic Power Station Unit 3 ML20151V7881988-01-31031 January 1988 Errata to NEDO-24081, LOCA Analysis for Peach Bottom Atomic Power Station,Unit 2, Replacing Page 4-14 ML20154C2111986-11-30030 November 1986 BWR Owners Group Assessment of ECCS Pressurization in Bwrs ML20137N6551985-11-30030 November 1985 Evaluation of Low Carbon Type 316 Stainless Steel Recirculation Outlet Safe Ends at Peach Bottom Unit 3 ML20112B1951984-11-30030 November 1984 Errata & Addenda 6 to LOCA Analysis for Peach Bottom Atomic Power Station,Unit 3 ML20096H1271984-06-30030 June 1984 Errata to NEDO-24081 LOCA Analysis for Peach Bottom Atomic Power Station Unit 2 ML20096H1141984-06-30030 June 1984 Errata to NEDO-24229-1, Peach Bottom Atomic Power Station Units 2 & 3 Single Loop Operation ML20091J9051984-03-31031 March 1984 Safety Review of Peach Bottom Unit 3 at Core Flow Conditions Above Rated Flow Throughout Cycle 6 ML20064B9971982-10-31031 October 1982 Errata & Addenda Sheet 5 to LOCA Analysis for Peach Bottom Atomic Power Station,Unit 3 ML20053E8921982-05-31031 May 1982 Core Spray Sparger Crack Analysis at Peach Bottom Atomic Power Station,Unit 2. ML20003E1501981-03-31031 March 1981 Errata 4 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 3. ML20003E1481981-02-28028 February 1981 Errata 3 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 3. ML19337B4631980-06-30030 June 1980 Errata & Addenda Sheet 2 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 3. ML19337B4641980-06-30030 June 1980 Addenda 6 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 2. ML19351F3581980-05-31031 May 1980 Single Loop Operation. ML19290E3151980-01-31031 January 1980 Proposed Alternate Absorber Control Blade Test Program, Revision 1,Class 1 ML19290E3221980-01-31031 January 1980 Errata & Addenda Sheet 5,revising Pages 4-11 & 4-12 ML19290E3181979-12-31031 December 1979 Errata & Addenda Sheet 4,revising Pages 4-10,4-11 & 4-12 ML19249D9081979-08-31031 August 1979 Proposed Alternate Absorber Control Blade Test Program. 1998-05-31
[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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.* ,0 GENE 77101-0196. REV. O DRF NO. B13-01800 SHEET 1 PB ECR h(-N77 REV ATTACHMENT PAGE ~51 oF 1 ,
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SHT* REV CORE SPRAY LINE DOWNCOMER REPAIR SEISMIC REPORT
SUMMARY
for PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 Modificadon P00335 f
Prepared by: /// Ash- M-Pr.
T. E. Gleason, Principal Engineer l Mechanical Design Engineering Verified bv:
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C. Lung, Consulting EngineerC/
Approved by: # -
7 D. W. Smith, ProgranrManager 1
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GENE 771-01-0196. REV. O DRF NO. B13-01800 ,
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- 1. INTRODUCTION #",^'",
o, MENT PAGE M OF ser a _ nu -
j 1.1 Background I
Peach Bottom Atomic Power Station L' nit 2 has avo Core Spray Lines ( SC L) which ,
l enter the reactor pressure vessel (RPV) at the 120' and 240 azimuth locations.
The CSL entering at 120' splits at its T-box with the downcomers at 7.5* and at ,
172.5' locations. The CLS entering at 240* splits at its T-box with the downcomers j
at 187.5' and at 352.5' locations. The weldedjoints in the CSL downcomers near the shroud penetration may be cracked and will require reinforcement if the
! cracks are found. The reinforcement is required to maintain the pipe alignment and to prevent a crackedjoint for separating. This modification is of a bolted l' design utilizing clamps for attachment to the CSL. j i
The same type modification was used on Peach Bottom Atomic Power Station Unit f 3 at the 172.5' downcomer location.- The design and analysis used for the Peach Bottom 3 modification has been reviewed and the results are utilized where applicable. ,
j 1.2 Scope i'
The analysis covers the CSL from the thermal sleeve at the RPV to the CSL shroud penetration including the 90* elbow, but excluding the penetration sleeve. Two 9
different cases were evaluated, one assuming the downcomer integrity was intact i and the other assuming the propagation of the crack to 360 degrees which a!! owed rotational freedom at the crack location.
I This report transmits the results of the CSL design stress analysis which assesses the effects of the proposed modification on the CSL. The purpose of the analysis l
j is to demonstrate the seismic structural adequacy of the CSL with the downcomer modification installed at Peach Bottom Unit 2.. The analysis is contained in Design Record Files (DRF) B13-01800, B13-01732 and B11-00642.
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- 2. CORE SPRAY LINE EVALUATION j
2.1 Assumptions The following assumptions are used in the CSL structural analysis.
- 1. The CSL downcomer sleeve / spigot assembly near the shroud penetration is assumed to have one or more 360* through wall cracks. No credit is taken for any 9
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DRF SO. B13-01800 SHT # REV l SHEET 3 (
remaining ligament at the postulated crack location. Cracks may exist at one, two,
- three or all four downcomers. ]
- 2. The seismic analysis shall take into account both partial and complete cracking of the shroud welds. The degree of cracking assumed shall be the l l
maximum crack length permitted without requiring shroud repair and complete j
)
, cracking with the tie rod repair installed.
I 2.2 Seismic Evaluation l
! The seismic evaluation for the Peach Bottom 2 downcomer repair utilizes analyses from i the shroud repair work and from previous downcomer repair work.. The applicable l
- analysis are summarized below and can be found in DRF's B13-01800, B13-01732 and B1100649 ;
f
- a. The shroud repair seismic analysis predicts 1.2 inches for the maximum CLS l
anchor point displacements. The analysis assumes the shroud with 360' through l wall cracks and with the tie rod repair installed.
j l
- b. Seismic analysis which assumes the shroud cracked to the maximum extent without requiring the tie rods installed predicts the maximum CSL anchor point to l
a be 0.4 inches.
$ c. Confirming seismic analysis using Peach Bottom 2 fbel loads validate the used of the previous analysis for Peach Bottom 2 application.
1
$ 2.3 CLS Stress Evaluation I
A CSL structural analysis has been completed for the previous shroud repair work and additional analysis prepared for the previous downcomer repair. The Peach Bottom 3 i
analysis accounts for the repair brackets welded to T-box near the vessel inlet nozzle.
1 The analysis applicable the Peach Bottom 2 downcomer repair are summarized below.
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- a. Core spray line analysis show acceptability of CSL in the non cracked condition.
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- b. Core spray line analysis shows acceptability assuming 360* through wall crack and with the downcomer repair hardware installed. The analytic model includes a j pinned joint (no moment carrying ability) to represent the cracked pipe and additional mass to represent the repair hardware.
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- 2.4 Summary or nomm 1 4
The analyses summarized above show the piping stresses satisfy the requirements of Article NB-3600 of ASME Section III. A summary of the maximum stresses obtained by solution of Subarticle NB-3650 equations is shown in Table 1. Table 1 i also includes the allowable stresses for each senice level.
- The analysis model used to calculate these stresses assumes a 360' through wall
] crack in one downcomer and no cracks in the other downcomer. With the
. exception of the thermal case, the higher stresses are found in the uncracked branch of the CSL. A cracked pipe section is unable to carry a moment and helps reduce the bending stresses. Cracks assumed in both branches of the CSL is not expected to increase the stresses in either branch.
The main contribution of the fatigue usage is due to the relative Operating Base Earthquake anchor displacements between the shroud penetration and the RPV .
nozzle (OBED). The value of relative displacement is 1.20' 0-peak. 2.4" peak to j peak. This is the worst displacement condition calculated for 360' through wall cracks in the shroud with the tie rod repair installed. Twenty total cycles are assumed for this load condition.
Table 1 Maximum Stress Summary Pipe Elbows and Components Senice Level Calculated Stress Intensity Allowable Stress (ksi)
(ksi)
Normal / Upset (Priman') 10.5 l 1.5Sm = 25.4 Normal / Upset (Primary + 5.5 3.0Sm = 50.8 Sec. excluding thermal bending)
Normal / Upset (Primary + 286.0 N/A Secondary)
Service Level C 10.6 l 2.25Sm = 38.14 __
Service Level D 13.9 l 3.0Sm = 50.8 Max. Cumulative Usage 0.71 l1.0 Thermal Exo. (Ea 12) l 21.4 13.0Sm = 50.8