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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212J2721999-10-0101 October 1999 Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20210A4041999-07-15015 July 1999 Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 ML20204J6031999-03-19019 March 1999 Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 181998-02-17017 February 1998 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29
[Table view] |
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I ATTACHMENT 1 NRC DOCKET 50-321 OPERATING' LICENSE DPR-57 EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 PROPOSED TEMPORARY CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10CFR170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License DPR-57 and has determined that: 4
- a. The proposed amendment does not require evaluation of.a new.
Safety Analysis Report and rewrite of the facility license;
- b. The proposed amendment does not require evaluation of several.
1 complex issues, involve ACRS review, or require an environmental impact statement;
- c. The proposed ame'ndment does not involve a complex issue or more than one environmental or safety issue;
- d. The proposed amendment does involve a single safety issue, namely, the addition of limiting conditions of operation and surveillance requirements for a temporary change to the Unit 1 secondary containment boundary. The proposed change would allow the opening of both railroad airlock doors simultaneously in the Unit 1 reactor building to facilitate movement of material and personnel during the Unit 1 1982 refueling outage Mk.I torus modifications;
- e. The proposed change to Operating License DPR-57 is therefore a Class III amendment.
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ATTACIIMENT 2 1
NRC DOCKET 50-321- ,
OPERATING LICENSE DPR-57 EDWIN-I. HATCH NUCLEAR PLANT UNIT 1 i
PROPOSED TEMPORARY CHANGES TO TECHNICAL SPECIFICATIONS
, The proposed temporary changes to the Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows: !
Remove Page Insert Page 3.7-12 3.7-12 3.7-12a 3.7-13 3.7-13 l
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIHLMtN15 C. Secondary Containment
- 1. Secondary Containment Integrity 1. Surveillance While Integrity Maintained
- a. Integrity of the secondary con-
.tainment shall be maintained Secondary containmert surveillance during all modes of Unit 1 plant shall be performed as indicated operation except when all of the below:
following conditions are met:
(1) The reactor is subcritical and Specification 3.3.A is met. a. A Preoperational secondary contain-ment capability test shall be (2) The reactor water temperature is conducted after isolating the below 2120F and the reactor secondary containment and placing coolant system is vented. the standby gas treatment system filter trains in operation. Such (3) No activity is being performed tests shall demonstrate the capa-which can reduce the shutdown bility to maintain a minimum margin below that stated in .
1/4-inch of water vacuum under Specification 3.3.A. calm wind ( 5 mph) conditions with each filter train flow rate not (4) The fuel cask or irradiated fuel more than 4000 cfm.
is not being moved in the re-actor building. b. Secondary containment capability to maintain a minimum 1/4-inch (5) All hatches between Unit 1 of water vacuum under calm wind secondary contairment and ( 5 mph) conditions with each Unit 2 secondary containment filter train flow rate not more are closed and sealed. than 4000 cfm shall be demonstrated at each refueling outage, prior to (6) At least one door in each refueling.
access path between Unit 1
. secondary containment and Unit 2 secondary containment is closed.
- b. Integrity of the Unit 1 secondary containment shall be maintained during all modes of Unit 2 plant operations except Operational Condition 4 as defined in the Unit 2 Technical Specifications.
Amendment No. 3.7-12
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2 Secondary Containment Integrity 2. Surveillance While Integrity Maintained During 1982 Refueling Outage Only
- a. Unit 1 secondary containment Secondary containment surveillance shall below the refueling floor is be performed as indicated below:
not required provided all of the following conditions are met: a, A preoperational secondary contain-ment capability test shall be per-(1) The reactor is subcritical and formed after isolating the Unit 1 Specification 3.3.A is ret. secondary containment above the re-fueling floor and placing the (2) The reactor water temperature is standby gas treatment system filter below 2120F and the reactor trains in operation. Such tests coolant system is vented. shall demonstrate the capability to maintain a minimum 1/4-inch of (3) All hatenes between Unit 1 second- water vacuum under calm wind dary containment and Unit 2 secon- ( 5 mph) conditions with each fil-dary containment are closed and ter train flow rate not more than sealed. 4000 cfm.
(4) At least one door in each access b. If secondary containment integrity path between Unit 1 secondary shoud be required as stated in containment and Unit 2 secondary Specification 3.7.C.1 perform sur-containment is closed. veillance as stated in Specifica-tion 4.7.C.l.a. If secondary con-(5) All hatches sepwating Unit 1 tainment is subsequently required secondary containment above the as stated in Specification 3.7.C.2 refueling floor from Unit 1 perform surveillance as stated in secondary containment below the Specification 4.7.C.2.a.
refueling floor _are closed and sealed.
(6) At least one door in each access path separating Unit 1 secondary ,
containment above the refueling floor from Unit 1 secondary con-tainment below the refueling floor is closed.
- b. Integrity of the Unit 1 secondary containment above the refueling floor shall be maintained during all modes of Unit 2 plant opera-tions except Operatioaal Condition 4 as defined in the Unit 2 Tech-nical Specifications.
- c. Refueling operations may continue in Unit I secondary containment (above the refueling floor) provided all conditions in Specification 3.7.C.2.a are met.
Am:ndment No. 3.7-12a
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C.3 Violation of Secondary 4.7.C.3 Surveillance After Integrity Violated Containment Integrity After a secondary containment vio-If Specification 3.7.C.1 cannot lation is determined the standby be met, procedures shall be gas treatment system will be operated initiated to establish conditions immediately after the affected zones listed in Specification 3.7.C.l.a are isolated from the remainder of through 3.7.C.l.d. the secondary containment. The ability to maintain the remainder of the secondary containment at 1/4-inch of water vacuum pressure under calm ( 5 mph) wind conditions shall be confirmed.
D. Primary Containment Isolation Valves D. Primary Containment Isolation Valves
- 1. Valves Required to be Operable 1. Surveillance of Operable Valves During reactor power operation, Surveillance of the primary con-all primary containment isolation tainment isolation valves shall be valves listed in Table 3.7-1. and performed as follows:
all reactor coolant system instru-ment line excess flow check valves a. At least once per operating shall be operable except as stated cycle the operable isolation in Specification 3.7.D.2. valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and the closure times specified in Table 3.7-l.
Amendment No. 3.7-13 d
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Endr rsement of accorppanying check is considered a receipt in full settlement of the following s' ems I ,
Vendor Number 921900 Check Number 923165 Voucher Number (
' Dist Date intnice Date Your Number Our No Gross Amount Discount Net Amount ,
10-82 10-04-82 100482400000 4,000.00 .00 4,000.00
) e 1 Totals l 4,000.00 .00 l 4,000.00 Note-If Ints does MOI agree witn your reCOfdS. p' ease return witn cheGM espid'ning dppdreht error
?lsi'gP y?,C5 ;"" "Y " n.= 362169 q;_ GeorgiaPower A Atlanta, Georgia 30302 Voucher Number Date (Mt p NdMri H 10-05-82 923165 Amount Pay .$4.000 and 00/100 Dollars $4,000.00
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