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Category:CONSTRUCTION PERMITS-APPLICATION & AMENDMENTS TO APP
MONTHYEARML20138A0061985-09-25025 September 1985 Application for Amends to CPPR-131,CPPR-132 & CPPR-133, Incorporating Partial Exemption from GDC 4 to Allow Implementation of leak-before-break Concept on RCS Primary Loops.Fee Paid ML20070N4221983-01-21021 January 1983 Application to Amend Cps,Extending CPs Until 870901 ML20098D0901983-01-11011 January 1983 Application for Amend to Cp,To Include Listed Earliest & Latest Completion Dates ML20027A9231982-09-0202 September 1982 Application for Amend to CPs & Ols,Consisting of Amend 39 to FSAR ML20050B8231982-03-31031 March 1982 Application to Amend CPs & OLs Consisting of Amend 37 to Fsar.Amend Consists of Responses to Questions from Various Branches within NRR ML20098C7121977-04-22022 April 1977 Amend 39 to Application for Cps,Providing Updated Cost Estimate & Correcting Error in Scheduled Fuel Loading Date for WPPSS 5 ML20028D9841976-07-0101 July 1976 Application to Amend CPPR-83 & CPPR-84,extending Time for Const Completion Until 780801 & 790801,respectively,due to Increased Delivery Time of Matls & Components ML20098C7471976-02-26026 February 1976 Amend 32 to Application for Cps,Providing Addl Info Re Financial Qualification,Per 750926 Request ML20028D9821975-12-30030 December 1975 Application to Amend CPPR-83 & CPPR-84,extending Time for Const Completion to 760201 & 0301,respectively,due to Increased Delivery Time of Matls & Components ML20028D9671975-05-19019 May 1975 Application to Amend CPPR-39 & CPPR-69 Extending Const Completion Date to 760701 & 770731,respectively ML20098C6701975-02-19019 February 1975 Amend 1 to Application for Cps,Providing Updated Cost Estimate & Correcting Error in Scheduled Fuel Loading Date for WPPSS 5 ML20098C6441974-07-30030 July 1974 Application for CPs to Construct Two PWRs W/Core Power Level of 3,800 MW ML20235B8121973-11-0101 November 1973 Application for Amend 13 to Application for Cp,Per AEC .Units Renamed as Hope Creek Generating Station, Units 1 & 2 ML20098C9981973-10-15015 October 1973 Application for CP ML20098D2741972-09-14014 September 1972 Amend 13 to Application for CP ML20098C8371972-09-14014 September 1972 Amend 13 to Application for Cp,Consisting of Const Cost Summary ML20098D2941972-08-21021 August 1972 Amend 10 to Application for Cp,Consisting of Response to AEC 720728 Questions ML20098D3441971-08-10010 August 1971 Application for CP ML20235B7181967-11-10010 November 1967 Application for Amend to CPPR-23 & CPPR-24,deleting or Omitting Baffles from Design of Primary Containment,Per Encl Rept.Baffles Not Required to Prevent Fluid Perturbation ML20235B8571964-09-16016 September 1964 Application for Amend 9 to Cp,Answering Questions Set Forth in AEC to Util ML20235B8281964-07-20020 July 1964 Application for Amend 8 to Cp,Setting Forth Addl Data Re Movement of Granitic Rock at Site ML20234E1871964-03-31031 March 1964 Amend 7 to Application,Further Detailing Plant Design & New Geological & Seismological Data That Indicates Vertical Movements of Up to 2 Ft Will Not Damage Reactor Containment Structure ML20234E1371964-03-16016 March 1964 Amend 6 to Application,Further Detailing Earthquake Design Criteria for All Critical Structures,Equipment & Sys of Proposed Facility ML20235B2941964-01-22022 January 1964 Application for Amend 5 to CP ML20234B7671963-08-0909 August 1963 Amend 4 to Application for License,Adding Details Re Facility Earthquake Design Criteria & Superseding Matl in Preliminary Hazards Summary Rept of Amend 2 & Paragraphs 2 & 3a of Part III of Amend 3 to Application ML20235B2871963-06-13013 June 1963 Application for Amend 3 to CP ML20234C8701963-04-0505 April 1963 Amend 2 to Application for License,Detailing Dry Well & Suppression Chamber Integrity Tests,Dry Well Cooling Sys, Containment Design Criteria & Refueling Bldg Vent Sys ML20234D0041963-03-0404 March 1963 Amend 1 to Application for License,Consisting of Response to AEC 630226 Questions Re R&D Programs Bearing on Safety of Plant ML20235B2601962-12-28028 December 1962 Application for License to Const & Operate Nuclear Reactor at Bodega Bay Atomic Park 1985-09-25
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20006A4171990-01-17017 January 1990 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,removing cycle-specific Parameter Limits from Tech Specs for Relocation to Core Operating Limits Rept,Per Generic Ltr 88-16 ML20011D3121989-12-21021 December 1989 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,removing Limit on Extending Surveillance Intervals in STS 4.0.2,per Generic Ltr 89-14 ML20005G4171989-11-17017 November 1989 Application for Amend to License NPF-66,changing Heatup & Cooldown Curves,Pressure Operated Relief Valve low-temp Overpressure Protection Setpoints & Bases,Per Generic Ltr 88-11.Westinghouse Ltr Rept MT/SMART-078(89) Encl ML19327B3971989-10-19019 October 1989 Application for Amends to Licenses NPF-72 & NPF-77, Authorizing Use of Vantage 5 Fuel & Combination of Vantage 5 Fuel & Present Optimized Fuel Assembly Core at Plant ML19325C6051989-10-0303 October 1989 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Spec 3/4.8.3.1, Onsite Power Distribution. ML20247K2291989-09-11011 September 1989 Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively, Allowing Licensees to Inspect Steam Generator Tubes by Insertion of Ultrasonic Test Probe from Cold Leg Side of Steam Generator Tube ML20247E3691989-09-0707 September 1989 Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Lifetime Records Retention for Radiological Effluent Monitoring & ODCM ML18153B8351989-07-24024 July 1989 Application for Amend to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,revising Tech Specs to Reflect Composition of Station Nuclear Safety & Operating Committee Following Recent Assignment of Superintendent Engineering Position ML20245L2401989-06-29029 June 1989 Application for Amends to Licenses DPR-61 & NPF-49, Clarifying Tech Specs Re Steam Generator Tube Insp Criteria. Change Would Add Cold Leg Side as Alternate Point of Entry ML20246L2501989-06-26026 June 1989 Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,deleting Tech Spec Figures 6.2-1 & 6.2-2 by Replacing Figures W/Narrative Description of Offsite & Onsite Organizations Functional Requirements ML20247N2651989-05-25025 May 1989 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & DPR-49,simplifying Administrative Controls for Changes in Radiological Effluent Monitoring Manual in Tech Specs,Per Generic Ltr 89-01 ML20247H2691989-05-22022 May 1989 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Tech Spec 5.3.2 to Allow Use of Either Hafnium or silver-indium-cadmium,or Combination of Both,As Absorber Matl in Rod Control Cluster Assemblies B13155, Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Revising Tech Spec Re Admin Controls in High Radiation Area1989-04-25025 April 1989 Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Revising Tech Spec Re Admin Controls in High Radiation Area ML20245J0691989-04-25025 April 1989 Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,modifying Tech Specs of Four Units to Be Consistent W/Plant Restart Provision in 10CFR50.36 If Safety Limit Exceeded ML20248F9851989-04-0303 April 1989 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Tech Spec Tables 3.3-1 & 4.3-1,per Generic Ltr 85-09 for Reactor Trip Sys Automatic Actuation Using Shunt Coil Trip Attachments ML20246N0911989-03-13013 March 1989 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,changing Tech Specs Re Administrative Controls & Organizational Charts,Per Generic Ltr 88-06 ML20246D2571989-03-0606 March 1989 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Amends Change Tech Specs to Incorporate Revised Ventilation Flowrates & Heater Dissipation Rate & Clarify Testing Method ML20235J0561989-02-17017 February 1989 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Administrative Section 6.0 to Include Removal of Organizational Figures,Per Generic Ltr 88-06 ML20196B7601988-11-28028 November 1988 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,clarifying Tech Spec 6.2.3 Re Safety Review Group.Fee Paid ML20205M5591988-10-26026 October 1988 Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively,modifying Tech Spec to Mofify Qualifications & Conduct of Nuclear Review Board for All Units ML20155F0441988-10-0404 October 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,revising Tech Spec 4.6.1.3a to Be Consistent W/ NUREG-0452,Rev 5, Std Tech Specs for Westinghouse Pwrs. Fee Paid ML20155C1531988-09-28028 September 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,revising Action Statement in Tech Spec 3.1.3.1 to Restrict Control Rod Movement & Thermal Power in Event of Inoperable Control Rods.Fee Paid ML20155G4751988-09-28028 September 1988 Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,modifying Tech Specs to Provide for Uniform Addresses for Listed Classes of Repts for Plants B12958, Revised Application for Amends to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,changing Tech Specs Number of Members & Time as Member of Nuclear Review Board1988-07-21021 July 1988 Revised Application for Amends to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,changing Tech Specs Number of Members & Time as Member of Nuclear Review Board ML20151B6721988-07-11011 July 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,removing Fixed Fxy Limits in Tech Spec 4.2.2.2.e. Fee Paid ML20154S5701988-05-31031 May 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,revising Tech Spec Surveillance Requirement 4.8.1.1.2.f.2 Re Rejecting Largest Single Load from Diesel Generator.Fee Paid ML20154P0851988-05-25025 May 1988 Application for Amends to Licenses DPR-61,DPR-21,DPR-67 & NPF-49,revising Tech Specs Re Administrative Controls. Changes Eliminate Conflicting Submittal Directions for Correspondence W/Nrc.Fee Paid ML20154D4371988-05-0606 May 1988 Application to Amend Licenses NPF-37,NPF-66,NPF-70 & NPF-75, Changing Tech Spec 3/4.4.6.1 Re RCS Leakage Detection Sys. Fee Paid ML20153E9401988-05-0404 May 1988 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,changing Tech Spec 3.3.3.6 & Tables 3.3.10 & 4.3-7 to Reflect Reg Guide 1.97 Reviews.Fee Paid ML20151Y6761988-05-0202 May 1988 Application for Amends to Licenses NPF-3 & NPF-58 Suspending Antitrust Conditions B12859, Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,revising Tech Specs Re Administrative Controls, Nuclear Review Board.Fee Paid1988-04-29029 April 1988 Application for Amends to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,revising Tech Specs Re Administrative Controls, Nuclear Review Board.Fee Paid ML20151U5411988-04-22022 April 1988 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,deleting Requirement to Provide Complete Listing of All Individual Results of All Radiological Environ Samples & All Environ Radiation Measurements.Fee Paid ML20151F9121988-04-0707 April 1988 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,changing Required Surveillance Interval for Ice Condenser Lower Inlet Doors from Current Frequencies to 100% Insp Every 18 Months ML20151D1301988-04-0101 April 1988 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,changing Tech Specs to Allow Credit to Be Taken for Radiation Monitor EMF-36 If EMF-39 Inoperable Below Mode 4 (Hot Shutdown).Fee Paid ML20151K2701988-04-0101 April 1988 Revised Application for Amends to Licenses NPF-9,NPF-17, NPF-35 & NPF-52 Re Fuel Assemblies.Proposed Amends Broaden Scope of Mods Allowed to Fuel Assemblies Involving Fuel Rod Locations & Delete Max Fuel Rod U Limit ML18152A8731988-03-17017 March 1988 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Tech Spec Section 6 to Delete Organization Charts & Replace Charts W/More General Description of Requirements & Replacing Certain Titles.Fees Paid ML20150A9951988-03-10010 March 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75 Revising Tech Specs Governing Operation of 8-inch Containment Purge Supply & Exhaust Isolation Valves to Allow Simultaneous Opening of Valves for Limited Reasons.Fee Paid ML20196J1971988-03-0202 March 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,reducing Containment Tendon Design Stresses to Incorporate Addl Design Margin.Fee Paid ML20147E8591988-02-23023 February 1988 Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively,amending Tech Specs to Identify Nuclear Review Board Minutes as Acceptable Means to Forward Certain Repts & Having Max of 12 H Continuous Planned Inoperability ML20149L4451988-02-17017 February 1988 Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Changing Table 6.2-1 of Tech Specs to Recognize Acceptability of Qualified Individuals in Dual Role of Senior Reactor Operator (SRO) & Shift Technical Advisor ML20149H2011988-02-0505 February 1988 Application for Amends to Licenses NPF-9,NPF-17,NPF-35 & NPF-52,changing Tech Specs to Broaden Scope of Mods Allowed to Fuel Assemblies Involving Fuel Rod Locations & Deleting Specified Max Total Fuel Rod U Weight Limit.Fee Paid ML20195H9301988-01-12012 January 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,changing Tech Spec Tables 3.3-12 & 4.3-8 to Allow More Accurate Measurement of Lower Effluent Discharge Flow Rates.Fee Paid ML20147E0481988-01-12012 January 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,revising Tech Specs 3.3-13 & 4.3-9 to Separate Gaseous Waste Mgt Sys Oxygen Analyzer Into Two Major Components.Fee Paid ML20147B7211988-01-11011 January 1988 Application for Amends to Licenses NPF-35,NPF-52,NPF-9 & NPF-17,incorporating Into Tech Specs Recommendations of NRC Generic Ltr 87-09 Re Sections 3.0 & 4.0.Fee Paid ML20149E5201988-01-0505 January 1988 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,removing Two Tables Listing Reactor Trip Sys Instrumentation & ESF Response Times from Tech Specs.Tables Will Be Placed in Chapter 16 of Fsar.Fee Paid ML20234C0551987-12-23023 December 1987 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-75,revising Tech Spec Tables 3.3-1 & 4.3-1,per Generic Ltr 85-09.Fee Paid ML20237C3321987-12-0404 December 1987 Application for Amends to Licenses NPF-37,NPF-66 & NPF-72, Modifying Tech Spec Figure 3.2-2 Re Normalized Heat Flux Hot Channel Factor.W/Rev 2 to WCAP-11387 & WCAP-11386.Fee Paid. Proprietary Rev 2 to WCAP-11386 Withheld (Ref 10CFR2.790) ML20236P3621987-11-0606 November 1987 Application for Amends to Licenses NPF-37,NPF-66 & NPF-72, Revising Tech Spec Tables 3.3-6 & 4.3-3 to Allow Control Room Ventilation Sys to Remain in Operation,Provided That Radiation Monitors Operable on Ventilation Train.Fee Paid ML20235P5501987-09-30030 September 1987 Application for Amends to Licenses NPF-37,NPF-66 & NPF-72, Increasing Setpoint for Enabling Anticipatory Reactor Trip Upon Turbine Trip from Greater than 10% Reactor Power to Greater than 30% Reactor Power.Fee Paid ML20235N8171987-09-29029 September 1987 Application for Amend to Licenses NPF-37,NPF-66 & NPF-72, Extending Allowable Outage Time for Listed Sys & Subsystems 1990-01-17
[Table view] |
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BEFORE THE UNITED STATES ATOMIC ENERGY COMMISSION g 7lkh ~a copg _ .
..o
[ %f;?l% l. hChlati:"
er 7 In the Matter of PACIFIC OAS Docket No. 50-205r !
d? .
AND ELECTRIC COMPANY Amendment No. 4 jg 6 l cd
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n
, Now comes PACIFIC GAS AND ELECTRIC COMPANY (the Company) and amends its above-numbered application by submitting herewith Amendment No. 4. This amendment sets forth further i
.i details with regard to the earthquake design criteria for Unit j No.1 of the Company's Bodega Bay Atomic Park and supersedes j the material set forth on page 8 of Section V of the Preliminary .
Hazards Summary Report (PHSR), paragraph 21 of Amendment No. 2 'l 4
i t
to the application, and paragraphs 2 and 3a of Part III of Amend- {
ment No. 3 to the application.
e !
The Company has established earthquake design criteria {
l for the Unit based upon the recommendations of Dr. George W.
Housner. In general, the usual methods of earthquake resistant design will be followed except that the lateral force factor which will be assumed as a basis for designing each critical structure, equipment or system will vary with the natural period and damping characteristics of the particular structure, equip-ment, or system.
The earthquhke design criteria for all critical structures, equipment and systems are based on the maximum credible earthquake ground motion on the granite at Bodega Head.
t SG09 8709210072 851217 1 '
PDR FOI A- ,
FIRESTOB5-665 PDR)
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- e I C As set forth in the PHSR, this is equal in intensity to the ground motion recorded on deep alluvium at El Centro, California, on May 18, 1940, which had a maximum acceleration of 33% of
, gravity. This is estimated to be one and one-half times the '
intensity of the 1906 San Francisco earthquake at Bodega Head.
The specific earthquake ground motions upon which the design of critical structures, equipment, and systems will be based are, for acceleration,, the r,uctra shown in Figure 10, Appendix V, of the PHSR, con?crted for the maximum credible earthquake ground motion at Bodega Head by multiplying by 2.7. l The corresponding velocity and displacement spectra are obtained by multiplying the acceleration spectra by T/2 pi and T2/4p12 , l m
respectively. (T : natural period.) Stress levels to be used I i - in design will conform, where applicable, to the ASME Boiler I
and Pressure Vessel Code,Section VIII, including applicable nuclear code cases, the ASA Code for Pressure Piping, and the Uniform Building Code of the International Conference of Build-ing Officials, 1961 Edition (except that the usual one-third allowable over-stress for structures during earthquakes will not be applied).
The abode design will be based on the following s
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A damping factors:
Structure % of Critical Damping i
Steel frame structures 25
- Reinforced concrete frame structures 4. 5 Reactor structure (See attached curve)
In i he event of earthquake ground motion equivalent to 66% of gravity critical equipment and systems will be capable of bringing the Unit to a safe shutdown. For example, particular items of equipment important to safety shall be designed to withstand such earthquake ground motion without deflection or distortion which would impair their functioning.
Critical structures (referred to as Class 1 Struc-l tures in Appendix V to the PHSR) include the reactor containment l structure, reactor refusling building, control building, and ventilation stack. Critical equipment and systems include the nuclear steam supply system inside containment, isolation l valves, liquid poison system, emergency cooling systems, emergency electrical power system, and the necessary associated instrumentation.'and controls. '
1
! All noncritical structures, equipment, and systems l ,
will be designed.in accordance with applicable Company seismic l 3 q j
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design practices.
Subscribed in San Francisco, California, this 9th day of August, 1963.
Respectfully submitted, PACIFIC GAS AND ELECTRIC COMPANY By i d
Robe'rt L 'Gerdes a
President RICHARD H. PETERSON FREDERICK W. MIELKE, JR.
PHILIP A. CRANE, JR. .,
Attorneys for Pacific Gas !
and Electric Company
! By . ,dh '
l l Philip'A. Crane,'Jr.
Subscribed and sworn to before me this 9th day of August, 1963.
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, ,\ ',. . ,
4 . (SEAL)/,'-
Rita J. Greepy Notary Public in l and for the City and County /or: ,,,
San Francisco, State of Cali.f,ornia; .,.
- My Commission Expires July 16,.'1987.1S.
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