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MONTHYEARML20204A2801982-08-18018 August 1982
Instructions for Calculation of Offsite Dose from Limiting Primary Sys Break Which Does Not Isolate Primary Containment Vent & Purge Valves
Project stage: Other
ML20076J5441983-08-31031 August 1983
Comments on 810629 Generic Evaluation of NUREG-0737,Item II.E.4.2 Containment Purge & Vent Valve High Radiation Isolation. Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Unnecessary
Project stage: Other
ML20084P5971984-04-10010 April 1984
Forwards Final Design Criteria for Resolution of NUREG-0737, Item II.E.4.2(7), Purge & Vent Valve Isolation, Requiring Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation
Project stage: Other
ML20084L3701984-05-0707 May 1984
Forwards Figures 1 & 2,inadvertently Omitted from 840410 Submittal,Providing Description of Mods Planned to Satisfy Purge & Vent Valve Isolation Requirements of TMI Item II.E.4.2
Project stage: Other
ML20097A7211984-09-0505 September 1984
Proposed Amend to Tech Specs,Reflecting Implementation of NUREG-0737,Item II.E.4.2(7) Re Automatic Closure of Containment Purge & Vent Valves on High Containment Radiation Signal
Project stage: Other
ML20097A7121984-09-0505 September 1984
Application to Amend License NPF-5,changing Tech Specs to Reflect Implementation of NUREG-0737,Item II.E.4.2(7) Re Containment Purge & Vent Valves.Change Adds Limiting Conditions for Operation & Surveillance Requirements
Project stage: Request
ML20128A0331985-06-25025 June 1985
Forwards Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981, Effective 860101. Interim Relief Requested in Event That Final Review/Approval Not Provided by Program Effective Date.Fee Paid
Project stage: Request
PNO-II-85-071, on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed1985-07-25025 July 1985
PNO-II-85-071:on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed
Project stage: Request
ML20137F9931985-08-20020 August 1985
Proposed Revs to Tech Spec Tables 3.2-1 & 4.2-1 Re Purge/Vent Valve Isolation
Project stage: Other
ML20137F9761985-08-20020 August 1985
Application for Amend to License DPR-57,reflecting Addition of High Radiation Isolation Signal for Containment Purge & Vent Valves.Fee Paid
Project stage: Request
ML20138B2331985-10-0404 October 1985
Informs That Util on Purge & Vent Mods Contained Proposed Tech Spec Requirements More Restrictive than Those Reviewed by Plant Review Board.Board Will Review Requirements by 851010
Project stage: Other
ML20136A7651985-12-23023 December 1985
Forwards Request for Addl Info Re Inservice Insp Program for Second 10-yr Interval.Response Requested within 30 Days of Ltr Receipt
Project stage: RAI
ML20137E9761986-01-0707 January 1986
Application for Amend to License DPR-57,changing Tech Specs to Add High Radiation Isolation Signal to Containment Purge & Vent Valves.Thirty Days Requested Between Dates of Issue & Effectiveness to Allow Time for Procedure Rev
Project stage: Request
ML20244D7371986-03-11011 March 1986
Forwards Safety Evaluation Accepting BWR Owners Group 850620 Request for Review of Offsite Radiological Consequences for Accidental Releases Not Meeting NUREG-0737, Item II.E.4.2(7).Regulatory Analysis Also Encl
Project stage: Approval
ML20204A2781986-04-28028 April 1986
Forwards Request for Addl Info Re Request for Rev to Tech Specs to Reflect Addition of Closure of Containment Purge & Vent Valves on High Containment Radiation Signal.Response Requested within 60 Days
Project stage: RAI
ML20199K5171986-06-26026 June 1986
Forwards Response to 860428 Request for Info Re Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Signal.Procedures for Venting Containment Have Separate Sections for Drywell & Torus
Project stage: Request
ML20235L7161987-07-14014 July 1987
Amends 143 & 78 to Licenses DPR-57 & NPF-5,respectively, Modifying Tech Specs by Adding Limiting Conditions for Operation,Trip Setpoints & Surveillance Requirements for Monitors
Project stage: Other
ML20235L7221987-07-14014 July 1987
Safety Evaluation Supporting Amends 143 & 78 to Licenses DPR-57 & NPF-5,respectively
Project stage: Approval
1985-06-25
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Similar Documents at Hatch |
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ENCLOSURE 4 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS
. PURGE / VENT ISOLATION The proposed change to the Hatch Unit 1 Technical Specifications 7 -
(Appendix A to-Operating License DPR-57) would be incorporated as follows:
Remove-Page Insert Page 3.2-3 3.2-3 3.2-25 3.2-25 t
4 1
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8508270143 850820 PDR-ADOCK 05000321 P
PDR g,
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Table 3.2-1 (Cont.)
Req.lired Operable Action to be taken if Ref.
Trip Channels rumber of channels is No, Condition per Trip not met for both trip (c) Instrument Nomenclature System (b) Trip Setting systems (c)
Remarks (d)
__825 psig Initiate an orderly load Initiates Group 1 isolation.
5 Main Steam Line Iow 2
Presaire re&ction and close Only realired in RUN mode, MSIVs within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
therefore activated when Mode Switch is in RUN position.
6 Main Steam Line High 2
1 140% rated flow Initiate an orderly load Initiates Group 1 isolation.
Flow
( 1120 psid) re&ction and close MSIVs within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
7 Main Steam Line High 2
12000F Initiate an orderly load Initiates Group 1 isolation.
'Illnnel Tenperature re&ction and close MSIVs within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Fy8 Reactor Water High 1
20-80 gpm Isolate reactor water Final trip setting will be Cleamp System cleamp system.
determined during startup u
Differential Flow test program.
9 Reactor Water High 2
100-1500F Isolate reactor water Final trip setting will be Cleamp F41ipnent cleamp system.
determined & ring startup Room Temperature test program.
10 Reactor Water High 2
0-1000F Isolate reactor water Final trip setting will be Clearup F41ipment cleamp system determined durirn startup Room Differential test program.
Temperature 11 Condenser Vacuum Iow 2
17" Hg. vacuum Initiate an orderly load Initiate Group 1 isolation.
re&ction and close MSIVs within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
12 Drywell Radiation High 1
1138 RAIR.
Close the affected Isolates containment purge isolation valves within and vent valves 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in Hot Shitdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shitdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Table 4.2-1 (Cont'd)
Ref.
Instmment Oeck Instmment Rinctional Test Instrument Calibration No.
Instrument Minim 1m Freq1ency Minim 1m Freq2ency Mininum Freolency Ja)_
(b)
(c) 10 Reactor Water Cleanup None (d)
Every 3 months Eolipment Room Differential Tenperature 11 Condenser vacuum None (d)
D>ery 3 months 12 Drywell Radiation Once/ Day Once/ Month Once/ Operating Cycle Notes for Table 4.2-1 a.
The column entitled "Ref.
No."
is only for convenience so that a one-to-one relationship can be established between items in Table 4.2-1 and items in Table 3.2-1.
b.
Instrument functional tests are not req 11 red when the instruments are not reglired to be operable or are h
tripped.
However, if functional tests are missed, they shall be performed prior to retu rning the instrument to an operable status, c.
Calibrations are not realired when the instruments are not realired to be operable.
However if calibrations are missed, they shall be performed prior to returning the instrument to an operable status, d.
Initially once per month or according to Figure 4.1-1 with an interval of not less than one month nor more than three months. 'Ihe conpilation of instrument failure rate date may include data obtained
-.
