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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Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends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
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- ENCLOSURE: 4 PLANT HATCH - UNITS 1, 2-NRC DOCKETS 50-321, 50-366 OPERATING LICENSES'DPR-57, NPF-5 RE00EST TO REVISE TECHNICAL SPECIFICATIONS:
SUPPRESSION POOL TEMPERATURE LIMIT PAGE CHANGE INSTRUCTIONS I I
' The proposed changes to the- Technical Specifications (Appendix A to ,
Operating Licenses DPR-57 and NPF-5) would be incorporated as follows: l Remove Paae- Insert Page UNIT 1:
3.7-1 3.7-1
]
UNIT 2: )
3/4 6-11, 3/4 6-11 3/4 6-12 3/4 6-12 1
1 l
8708240056 870814 PDR ADDCK 05000321 P PDR 1596C E4-1 8/14/87 SL-3040
1
~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j I
3.7. CONTAINMENT SYSTEMS 4.7. CONTAINMENT SYSTEMS Applicability Applicability The Limiting Conditions for Operation The Surveillance Requirements associated with containment systems associated with containment systems apply to the operating status of the apply to the primary and secondary primary and secondary containment containment integrity.
systems.
Objective Objective The objective of the Limiting Conditions The objective of the Surveillance Re-for Operation is to assure the integrity quirements is to verify the integrity of the primary and secondary containment of the primary and secondary contain-systems. ment.
Specifications Specifications A. Primary Containment A. Primary Containment
- 1. Pressure Suppression Chamber 1. Pressure Suppression Chamber i
At any time that irradiated a. The pressure suppression chamber fuel is in the reactor vessel, and water level, water temperature the nuclear system is pressurized and air temperature shall be above atmospheric pressure or measured and recorded daily.
work is being done which has the potential to drain the vessel, the pressure suppression chamber b. The interior painted surfaces water level and water temperature above the level one foot below shall be maintained within the the normal water line of the following limits except while per- pressure suppression chamber forming low power physics tests at shall be visually inspected atmospheric pressure at power levels once per operating cycle, not to exceed 5 Mwt. In addition,'the external surfaces of the pressure
- a. Minimum water level - 12 feet, suppression chamber shall 2 inches, be visually inspected on a routine basis for evidence
- b. Maximum water level - 12 feet, of corrosion or leakage.
6 inches.
- c. Whenever there is indication
- c. During normal power operation, the that a significant amount of suppression chamber water temperature heat is being added to the shall be maintained 595'F.* If this l pressure suppression pool, the temperature limit is exceeded, pool pool temperature shall be con-cooling shall be initiated imediately. tinually monitored and also observed and logged every S If the water temperature cannot be restored to $95'F* within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be shut down using l minutes until the heat add is terminated, normal shutdewi procedures.
- Suppression chamber water temperature will be maintained at $100*F during periods when the river temperature, as measured at the intake structure, is >B7'F. The river temperature will be measured on a daily basis while under this specification (valid 8/12/87 through 9/30/87 only).
HATCH - UNIT 1 3.7-1 Proposed TS/01460/223
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' CONTAINMENT SYSTEMS a
3/4.6.2 DEPRESSURIZATION SYSTEMS
' SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with the pool water:
a '. Volume between 87,3002 ft , and 90,550 ft', equivalent to a l l: level between 12'2" and 12'6", and a
- b. Maximum temperature of 95*F during OPERATIONAL CONDITION 1 or 2, except that the maximum temperature may be permitted to increase to:
1 105 F during testing which adds heat to the suppression 1.
chamber during OPERATIONAL CONDITION 1 or 2, ;
- 2. 120 F with the main steam line isolation valles closed following a scram from OPERATIONAL CONDITI0d 1 or 2.
- 3. 100"F during periods when the river temperature, as measured at the intake structure, is 2 87 F. The river temperature will be monitored on a daily basis while under this specification (valid 8/12/87 through 9/30/87 only).
- c. Level instrumentation channels alarms adjusted to actuate at: 1
- 1. High water. level of 5 12'6".
1
- 2. Low water level of 2 12'2".
APPLICABILITY: CONDITIONS 1, 2 and 3.
ACTION:
- a. With the suppression chamber water volume outside the above limits, restore the volume to within the limits within one hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in 4 COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
)
- b. In OPERATIONAL CONDITION 1 or 2 with the suppression chamber water temperature > 95 F, except as permitted above, initiate 1 suppression pool cooling and restore the, temperature to s 95*F I or to 6100*F, as allowed by Specification 3.6.2.1.b.3, l l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. In OPERATIONAL CONDITION 1 or 2 with the suppression chamber !
water temperature > 105 F during testing which adds heat to the suppression chamber, stop all testing, initiate suppres- :
sion pool cooling and restore the temperature to s 95 F or to 5100 F, as allowed by Specification 3.6.2.1.b.3, within l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
)
HATCH - UNIT 2 3/4 6-11 Proposed TS/0147q/223
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T" CONTAINMENT' SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) 4 ACTION: (Continued)
- d. In OPERATIONAL CONDITION 1 or 2 with THERMAL POWER > 1% of RATED THERMAL POWER and the suppression chamber water temperature
> 110 F, place the reactor mode switch in the Shutdown position.
- e. With the suppression chamber water temperature > 120 F and the main steam isolation valves closed'following a scram from OPERATIONAL CONDITION 1 or 2, depressurize the reactor pressure )
vessel to < 200 psig at normal cooldcwn rates.
- f. .With one suppression chamber water level instrumentation channel inoperabl), restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00W.'l within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- g. With.both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel to OPERABLE status within'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the follow-ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS ,
4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:
- a. By verifying the suppression chamber water volume to be between 12'2" and 12'6" at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber water temperature to be ,
s 95 F or as permitted by Specification 3.6.2.1.b.3, by verifying i the suppression chamber water temperature to be s 100 F.
- c. At least once per 5 minutes in OPERATIONAL CONDITION 1 or 2 i during testing which adds heat to the suppression chamber, by J verifying the suppression chamber water temperature s 105 F.
- d. At least once per 60 minutes when THERMAL POWER > 1% of RATED THERMAL POWER and suppression chamber water temperature > 95 F, by verifying suppression chamber water temperature < 110 F.
1 HATCH - UNIT 2 3/4 6-12 Proposed T/S/0147q/224 l
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