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| | document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS | | | document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS |
| | page count = 3 | | | page count = 3 |
| | | project = TAC:56049, TAC:59542 |
| | | stage = Other |
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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 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 1985-12-23
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Text
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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 _
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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) 5 Main Steam Line Iow 2 __825
> psig Initiate an orderly load Initiates Group 1 isolation.
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 />.
F y8 Reactor Water High 1 20-80 gpm Isolate reactor water Final trip setting will be u Cleamp System cleamp system. determined during startup 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
- 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
- _ - _ _ - _