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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] Category:TEST REPORT
MONTHYEARML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20096B4311995-12-31031 December 1995 Cycle 11 Startup Rept ML20078S9501994-12-16016 December 1994 PBAPS Cycle 11 Startup Rept for Unit 2 ML20063J9191994-02-10010 February 1994 Cycle 10 Startup Rept ML20101S9401991-12-31031 December 1991 PBAPS Unit 2 Vessel Surveillance Matls Testing & Fracture Toughness Analysis ML20090L8131991-12-24024 December 1991 Reactor Containment Bldg Integrated Leak Rate Test Rept ML20082B9391991-07-17017 July 1991 Rept of Plant Start-Up Following Eighth Refueling Outage on 910112-0412.W/undated Ltr ML20079C9511991-03-29029 March 1991 Reactor Containment Bldg Integrated Leak Rate Test Rept ML19332C8201989-11-17017 November 1989 Rept of Plant Startup Following Seventh Refueling Outage, 870315-891010. W/891117 Ltr ML20244C2571989-01-31031 January 1989 Reactor Containment Bldg Integrated Leak Rate Test ML20155G1931988-10-31031 October 1988 Rept on Restart Review Panel Assessment of Readiness for Restart ML20155J8451988-05-27027 May 1988 App R Multiple High Impedance Cable Fault Flame Test Rept ML20154C7101988-05-0606 May 1988 Vessel Surveillance Matls Testing & Fracture Toughness Analysis ML20138Q9771985-10-28028 October 1985 Rept of Plant Startup Following Sixth Refueling Outage, 840428-850713 ML20135D5431985-06-11011 June 1985 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20126J8401985-05-30030 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 51,Unit 2,3,Turbine Bldg El 135 Ft Corridor to Switchgear Rooms,Fire Area 78A ML20126J9901985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 97,Unit 2,3,Turbine Bldg El 116 Ft Janitor Room,Fire Area 116 ML20126J9761985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 96,Unit 2,3,Turbine Bldg El 116 Ft Toilet Area,Fire Area 115 ML20126J9521985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 95,Unit 2,3,Turbine Bldg El 116 Ft Clean Clothes Room,Fire Area 114 ML20126J9261985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 94,Unit 2,3,Turbine Bldg El 116 Ft Counting Room,Fire Area 78E ML20126J9091985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 93,Unit 2,3,Turbine Bldg El 116 Ft Health Physics Util Room,Fire Area 82 ML20126J8861985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 92,Unit 2,3,Turbine Bldg El 116 Ft Conventional Chemistry Lab,Fire Area 78D ML20126J8581985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 91,Unit 2,3,Turbine Bldg El 118 Ft Radiation Chemistry Lab,Fire Area 78C ML20126J8251985-05-20020 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 24,Unit 2,3,Turbine Bldg El 116 Ft Common Equipment Area (Beneath Switchgear Rooms),Fire Area 78B ML20238D8651985-02-28028 February 1985 Hydrogen Water Chemistry Mini Test Final Rept. W/Two Oversize Drawings.Related Info Encl ML20092D7071984-06-20020 June 1984 Ultrasonic Indications in Jet Pump Instrumentation Penetrations of Peach Bottom Atomic Power Station,Unit 3 ML20084R3001984-03-14014 March 1984 Fire Endurance & Hose Stream Tests on Floor Penetration Fire Stops Design Fc 350 ML20084R2921984-02-16016 February 1984 Fire Endurance & Hose Stream Tests on Wall Penetration Fire Stops Design Wp 713 ML20082N3381983-12-31031 December 1983 HVAC Damper Program Penetration Seal Test Results & Exemption Requests ML20084R2881983-11-0404 November 1983 Fire Endurance & Hose Stream Tests on Wall Penetration Fire Stops Design WP694 ML20082G1231983-08-23023 August 1983 Reactor Containment Bldg Integrated Leakage Rate Test Rept, Conducted During Aug 1983 ML20080F9801983-02-14014 February 1983 Rept of Plant Startup Following Fifth Refueling Outage, Feb 1983 ML20027C3241982-02-28028 February 1982 Rept of Plant Startup Following Fifth Refueling Outage, 820219 ML20039B6801981-09-0606 September 1981 Primary Reactor Containment Integrated Leakage Rate Test Rept. ML20041C8071981-03-0707 March 1981 Rept of Plant Startup Following Fourth Refueling Outage, 810307. ML20062K2481980-07-28028 July 1980 Primary Reactor Containment Integrated Leak Rate Test ML19345A8241980-03-31031 March 1980 Rept of Plant Startup Following Fourth Refueling Outage, Mar 1980. ML19344D2631980-03-0505 March 1980 Rept of Startup Following Third Refueling Outage,Sept 1979. ML19274D3301978-10-31031 October 1978 Rept of Plant Start-up Following Third Refueling Outage Sept-Oct 1978. Assures That Unit 2 Refueling Outage Caused No Conditions or Sys Characteristics to Diminish Safe Operation ML20081B9871977-04-0404 April 1977 Reactor Containment Bldg:Integrated Leakage Rate Test Rept ML20072N7491975-07-22022 July 1975 Noise Level Measurements Surveillance Test Results ML20072N7551975-04-30030 April 1975 Noise Level Measurements Surveillance Test Results ML20072N7781974-10-29029 October 1974 Noise Level Measurements Surveillance Test Results ML20072N7611974-07-25025 July 1974 Noise Level Instruments Surveillance Test Results ML20072N7701974-02-24024 February 1974 Noise Level Measurements Surveillance Test Results 1998-12-31
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STRUCTURAL STEEL ANALYSIS for PEACH BOTTOM GENERATING STATION Calculation No. 94 Unit 2,3 '
Turbine Building El. 116'-O" Counting Room Fire Area 78E Prepared byt ___ __ , Date: _8" (Y_~_8_(_
Reviewed by: h _ Revision: O A kl 7 1922 West Chester Pike
- Upper Darby, Pa.19082 e (216) 853 1700
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PEACH BOTTOM GENERATING STATION 1- eBE6_QEggBIEIlgM The area under consideration is the Counting Room on the 116'-O" elevation of the Turbine Building (Fire Area 78E). The bounding walls are constructed of reinforced concrete with an average thickness of 1 ft. The total surface area for heat transfer la 1,242 ft2 (see Attachment A for a sketch of the area under consideration). .
- 2. gggggSIlg(E_(Q6plHQ There are no combustible liquida or cable traya located in this area. ,
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- 3. MEHII(6IlON_E686HEIEgg /
There is one door khich enters this area.
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119 3'-O"x7'-O" East Wall
- 4. C6gEg_gX6HIHgg Since there are no exposed fixed combustibles in this area, no cases were examined for a general room fire.
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- 15. Eg@ybIf No general room fire was postulated because of the lack of exposed fixed combustibles in the area.
There are no cable traya in this area to preacnt a localized heating exposure to the structural steel.
- 6. EEEE9I!_9E_IBAHEIEMI_995aEDIIDLE!
This area contains no exposed fixed combustibles. The table below lista the maximum heat release rate for transient
-combustibles for different fire durations which result in an area temperature less than 1100 0F.
Eire _gurntien 926_1hWlm21 91hW1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 10.5 1212 2 hourd 8.0 923 3 houra 6.5 750 The distance between the floor and the deepeat beams supporting the ceiling in 16*-8 1/2". The heat release rates required of floor level transient combustible fires to produce plume temperatures of 1100 0F, 13OOO.e and 15000 F at the bottom flange of the beam have been determined and tabulated below. For the temperatures greater than 1100 F the time 2
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.s hofeesional1.aen Courel,ine.
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required to heat the sizes of the beams supporting the ceiling have also been determined.
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'1100 7,257 -
1300 9,549 38 1500 12,042 26 t
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Q..i Unit 2,3 Turbine Building, Elevation 116'-0" Counting Room Surface Area Calculation Walls North wall (11' x 18') 198 ft 22 East wall 18' x 18') 324 ft 2 South wall 11' x 18') 198 ft West wall 18' x 18') 324 ft 2 j 2
1,044 ft l 2
Ceiling (11' x 18') 198 ft Total Surface Area Calculation 1,242 ft 2
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ATTACHMENT A