Criteria for Determining Justification for Continued Operation When Encountering Major Discrepancies in As-Built Safety Related Piping| ML20117G800 |
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Point Beach  |
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| Issue date: |
08/28/1996 |
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| From: |
WISCONSIN ELECTRIC POWER CO. |
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| Shared Package |
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| ML20117G782 |
List: |
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| References |
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| DG-M10, NUDOCS 9609050337 |
| Download: ML20117G800 (5) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999
Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs
ML20210M6171999-08-0404 August 1999
Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys
ML20210B5121999-07-15015 July 1999
Pbnp Simulator Four-Yr Rept
ML20209C1831999-07-0101 July 1999
Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS
ML20205R6741999-04-12012 April 1999
Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR
ML20203A2261999-02-0202 February 1999
Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design
ML20202F6521999-01-29029 January 1999
Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes
ML20154G5601998-10-0707 October 1998
Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility
ML20154H4231998-10-0505 October 1998
Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis
ML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20154C1941998-09-28028 September 1998
Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels
ML20153G7361998-09-23023 September 1998
Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers)
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20236W7861998-07-30030 July 1998
Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability
ML20249C3811998-06-22022 June 1998
Proposed Corrected Tech Specs Pages Re Radiological Effluents
ML20248C6651998-05-28028 May 1998
Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses
ML20248G1671998-05-27027 May 1998
Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1
ML20203K9571998-02-26026 February 1998
Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12
ML20203K2981997-12-15015 December 1997
Proposed Tech Specs Re Administrative Controls
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20247P2681997-09-23023 September 1997
Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles
ML20210M5151997-08-14014 August 1997
Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test
ML20210J0331997-08-0707 August 1997
Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording
ML20140C9111997-06-0303 June 1997
Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1
ML20141C5931997-05-0909 May 1997
Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140D7251997-04-14014 April 1997
Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c
ML20140D7091997-04-14014 April 1997
Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20137N6451997-04-0202 April 1997
Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20137C8331997-03-20020 March 1997
Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
1999-08-04
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
ML20137P8441997-02-14014 February 1997
Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews)
ML20140G9351997-02-14014 February 1997
Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling)
ML20140G8921997-02-14014 February 1997
Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown)
ML20140G9401997-02-0707 February 1997
Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing
ML20138K2991997-01-31031 January 1997
Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory
ML20138K2031997-01-31031 January 1997
Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1
ML20138K2551997-01-31031 January 1997
Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1
ML20138K2411997-01-31031 January 1997
Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1
ML20138K3231997-01-31031 January 1997
Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode)
ML20137P8551997-01-31031 January 1997
Brine Tank Standpipe Mod
ML20138K3071997-01-31031 January 1997
Rev 38 to OP 9C, Containment Venting & Purging
ML20138K2901997-01-31031 January 1997
Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2
ML20138K2641997-01-31031 January 1997
Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2
ML20138K4991997-01-31031 January 1997
Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2
ML20138K3181997-01-31031 January 1997
Rev 33 to RP 1B, Recovery from Refueling
ML20138K3031997-01-31031 January 1997
Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes
ML20138K2251997-01-31031 January 1997
Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2
ML20138K4791997-01-31031 January 1997
Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1
ML20138K4701997-01-31031 January 1997
Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1
ML20138K5041997-01-31031 January 1997
Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2
ML20138K5161997-01-31031 January 1997
Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2
ML20138K4751997-01-31031 January 1997
Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1
ML20138K5231997-01-31031 January 1997
Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2
ML20138K7311997-01-31031 January 1997
Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly)
ML20138K7171997-01-31031 January 1997
Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1
ML20138K3121997-01-31031 January 1997
Rev 43 to RP 1A, Preparation for Refueling
1998-09-30
[Table view] |
Text
i WISCONSIN ELECTRIC DG-M10
, NUCLEAR POWER DEPARTMENT Revision 1 DESIGN AND INSTALLATION GUIDELINES Pace 4 of 9 Accendix 8 PIPE SUPPORT GUIDELINES #A
- t. ..,
. CRITERIA TOR DETERMINING JUSTITICATION.,
l l
FOR CONTINUED OPERATION WHEN ENCOUNTERING f
MAJOR DISCREPANCIES IN *AS-BUILT" SAJETY RELATED PIPING )
l l
l I
WISCONSIN ELECTRIC POhT.R COMPANY Point Beach Nuclear Plant 9609050337 960828 DR ADOCK 05000266 PDR l
1 . .
WlSCONSIN ELECTRIC DG-M10 NUCLEAR POWER DEPARTMENT Revision 1
. . DESIGN AND INSTALLATION GUIDELINES Pace 5 of 9 PlPE SUPPORT GUIDELINES ll ll l
?
TAstr er cos Es:s s
Pace 3
1.o :N:Rosucrzes a scort . . . . . . . . . .... ...
3 2.0 CRITERIA . . . . . .................
5 3.0 c0N"Lus!C:3 . . . . . . . . . . . . . . . ..... . .
5 4.0 FITERENCIs . . . . . . . . . . . . . . . . . . . . .
2-
.'.)
3 l -
l l
. . 1
. WISCONSIN ELECTRIC DG-MS O
. NUCLEAR POWER DEPARTMENT Brision 1 DESIGN AND INSTALLATION GUIDELINES Pace 6 of 9 Accendix B PIPE SUPPORT GUIDELINES f.:
.1. 0 INTP03UCT:CN & SCCPE These. criteria are intended to assure the operabil-ity require- -
ments of safety related piping and associated supports af at as
' determined that stresses exceed allowables presented in the PoAnt Beaca Nu: lear Plant TSAR. These crateria permit cperation for an interim period only. Modifications will be made wnach return the system to within TSAR allowables by the next refueling outage or sooner if operation permits.
These criteria are intended to expeditiously perform necessary evaluations to determine interim operability and not to delay appropriate actions.
For cases involving components classified as ASH code class I where TSAA allowables are exceeded, WE shall be notified upon dascovery and WE shall evaluate reportability requirements per 10CTR50.
! 2.0 CRITERIA 2.1 Paping Operability Criteria w
The piping enalysis shall be in accordance with AS..E.
Sectier. Ill NC-J600 servace level D limits (Pef. 1). The
- des:;n leading conditions to be applied in the analysis 4
shall include the CBE earthquake.
4 To11owing is the pipe stress criteria for gustifying
, contanued operation of the plant:
(Fef. I equation 9)
(5 7+S.+SD3E g < 2.0 Sy)
Where: S gp = Longitudinal Pressure Stress S g7 = Dead Weight Stress Stresses Resulting Tzom Design Basis 4
Sogg
5 I
= Material Yield Stress (Reference 1 Appendices) code Case N-411 allows for increated damping values.
independent of pipe diameter, for seismic analysis.
Therefore, increased damping values, in accordance with reference 2, will be acceptable when performing these analyses to meet operability. Should the piping stress analysis exceed the value of 2.0 Sy, or pipe supports do
] not meet their operable limits (see Section 2.2. then ,
additional iterative analysis of the piping may es required. The iterative analysis may use the knowledge
' that a support is not capable of withstanding the leads, and can be removed from the analysis. Where feasible, the actual suppert stiffness may be included in the iterative analysis, along with other refinements.
. J-l
WISCONSIN ELECTRIC DG-M10 NUCLEAR POWER DEPARTMENT Revision 1
, DESIGN AND INSTALLATION GUIDELINES Pace 7 of 9 Accendix B PlPE SUPPORT GUIDELINES Tor cases where piping secondary stresses are determined to l
exceed TS AR allowable s, a specific case by case approm=h
~
Vill be used to determine interi,m operability.
2.2 Pape Support & Hanger operability Criteria As a first step in evaluating the suppert, a linear elastic f analysis method will be used to determine the stress an the '
support members. In addition to the loading in Section include pipe thermal leads and i 2.1, the support loads must results from free end displacement and an= hor motion.
Supports will be analyzed using the allowables listed below
. to meet operability requirements.
Structural Steel I
Tg = 1.20 Sy but Tension
< 0.70 Su Bending T = 1.20 Sy but b
0.70 Su Shear Ty = 0.72 Sy but
< 0.42 Su
- Compression T, < T gbut not to exceed l 2/3 Per I
Cembined Stress Tor axial compression and bending i er axial tensson and bending, use I!SC 1.6., (Ref. 6)
Web Crippling = 1.0 Sy Weld Stress Ty = 0.42 Su (cf weld material)
Anchor Bolts Use Ta ter of Safety of 2 against ultimate tension and ahear values I l
Snubbers l l
Hydraulics Lead < manufacturers one time load l capacity. l Movement < total travel Springs Load within catalog range withe 9:
bottoming out 5: ruts TS = 2 and < 2/3 Per 14
WISCONSIN ELECTRIC DG.M10 NUCLEAR POWER DEPARTMENT Revision 1
'OESIGN AND INSTALLATION GUIDELINES Pace 8 of 9 Accendix B PIPE SUPPORT GUIDELINES r"a s .. - -
All remaining use manufacturers published faulted ,
Catalog Items load rating. Where level D allow-
- ables are not given, and the factor . .
of safety is specified in the catalog, use design allowables but with T5 = 2. (Typical catalog TS = 5, therefore use 2.5 x catalog capacity.
' Where: Tg = Allowable Tensile stress r = Allowable Bending Stress b
Ty = Allevable Shear Stress
= Allowable Axial compressive stress T, )
)
Ty = Allowable Weld Stress J
Per = Maximum Strength of Axially Loafed ,
Coepression Member l at Sy = 5pecified Minimum Yield Strength Temperature (See Note 1)
Su = 5pecified Minimum Tensile Terength Temperature TS = Tactor of Safety Note is Actual yield strength may be used where CMTR's 4
are avaalable for the material.
If a support fails using the linear elastic method, then a more refined analysis may be performed using plastae analysis techniques. The plastic analysis will(Fef. follow the 1) design rules of ASME Section III, Appendix T.
i 3.0 CCNCLUSION If the above criteria cannot be met, reportability per ICCTR53 must be evaluated and system operability reqairements per Plant Technical Specifications must be evaluated and appropriate actions taken. l 1
4.0 PETERENCES
- 1. American Society of Mechanical Engineers, Boiler and Pressure vessel Codes,Section III, 1983 Edation, through Winter 1985 Addenda.
- 2. American Society of Mechanical Engineers, Boiler and Pressure vessel Codes, Case N-411, Cated 9/17/54.
l WISCONSIN ELECTRIC DG-M10 Revision 1 NUCLEAR POWER DEPARTMENT DESIGN AND INSTALLATION GUIDELINES Pace 9 of 9 PIPE SUPPORT GUIDELINES
_ .mmmmmme.
), H80 !E B.13etan 79 02. 'F4pe Swppert Base Paste De'. ages I Usang Concrete Espansion Ancher Solts, Peva s s en t o. 2 18.;plement No. 11. Dated 8/20/79.
- 4. USAS 831.1.0-1967 Power F1 ping Code.
5, ' Manual of steel Construction,* American Institute of Steel Constructaan, Inc., Eagnth Edition, 1980.
f
. 6-
.