Letter Sequence Other |
---|
|
|
MONTHYEARML20235W6451987-07-13013 July 1987 Proposed Tech Specs Re Definition of Surveillance Frequency Project stage: Other ML20235W6311987-07-13013 July 1987 Application for Amend to License DPR-57,revising Tech Specs Re Definition of Surveillance Frequency.Fee Paid Project stage: Request 1987-07-13
[Table View] |
Similar Documents at Hatch |
---|
Category:TECHNICAL SPECIFICATIONS
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 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 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Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends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% ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys 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 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 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 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 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 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 ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria 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 ML20073G9631994-09-23023 September 1994 Proposed Improved Ts,Rev E ML20073D3231994-09-20020 September 1994 Proposed Tech Specs Change to Unit 1 TSs Re EDG Operability Requirements During Reactor Shut Down Conditions ML20072V3641994-08-31031 August 1994 Proposed Tech Specs Re Improved Standard Ts,Rev D ML20072H0571994-08-16016 August 1994 Proposed TS 3.9.C,allowing Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys ML20072E4021994-08-0808 August 1994 Proposed Tech Specs Re Rev Insertion Instructions Rev C ML20072B7541994-08-0404 August 1994 Proposed Tech Specs Re Traversing Incore Probe Operability Requirements ML20071H8381994-07-19019 July 1994 Proposed TS 3.3.6.6,allowing Less than Four Traversing in- Core Probe Machines to Be Operable ML20071H6851994-07-0808 July 1994 Proposed Tech Specs Re Improved Std Insertion Instructions, Consistent w/NUREG-1433 ML20069J3101994-06-0707 June 1994 Proposed Tech Specs Allowing Planned Testing at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt ML20059E9231994-01-0606 January 1994 Revised Proposed TS Pages for Increase in Allowable MSIV Leakage Rate & Deletion of MSIV Leakage Control Sys ML20059L2051993-11-0909 November 1993 Proposed Tech Specs Changing Unit 1,Section 4.9 & Unit 2, Section 4.8 Re Diesel Generator Testing Under Hot Initial Conditions ML20058P8881993-10-19019 October 1993 Proposed Tech Specs Re Time Delay for RPS Electric Power Monitoring Sys Trips ML20046B6061993-07-30030 July 1993 Proposed Tech Specs for Implementation of New 10CFR20 Requirements ML20046B5561993-07-27027 July 1993 Proposed Tech Specs Showing Original & Unrelated Changes Re Removal of Main Steam Line Radiation Monitor Trips ML20045E7281993-06-28028 June 1993 Proposed TS 3.7.A.4 & 3.6.4.1 for Units 1 & 2,respectively, Allowing One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing 1999-07-29
[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] |
Text
- _ _ _ - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -
i l
l ENCLOSURE 1 1
PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
DEFINITION OF SURVEILLANCE FREQUENCY BASIS FOR CHANGE RE0 VEST The definition of " Surveillance Frequency" as provided in Section 1.0 of the current Plant Hatch Unit 1 Technical Specifications, is as follows:
Periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance l
intervals. These intervals may be adjusted plus or minus 25%.
The operating cycle interval es pertaining to instrument and electrical surveillance shall never exceed 15 months. In the case where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
The Plant Hatch Unit i Technical Specifications, which are in " custom" format, do not contain a " Surveillance Frequency Notation" table, as is provided in Table 1.1 of Standard Technical Specifications (STS). This STS table defines the operating cycle interval as being equal to 18 months Moreover, Specification 4.0.2 of STS provides that all surveillance, including those performed on a once per cycle (18 month) basis, may be performed with a maximum allowable extension not to exceed 25% of the surveillance interval.
The present Plant Hatch Unit 1 definition, as provided above, is thus restrictive with respect to the NRC approved STS, in that; 1) The operating cycle interval is restrained to 15, rather than 18, months, and; 2) The current wording can be interpreted to imply that the 25%
grace period is not applicable to once per cycle surveillance. '
In order to provide requirements consistent with STS and Plant Hatch Unit 2, a change is proposed to the above definition. The proposed change would replace the sentence "The operating cycle interval as pertaining to instrument and electrical surveillance shall never exceed 15 months."
with the sentence "The operating cycle interval is defined as 18 months." This proposed change accomplishes two purposes: 1) It removes the restrictions with respect to STS; and, 2) It provides a definition of the time interval which equals an operating cycle. This second purpose is necessary because the Plant Hatch Unit 1 Technical Specifications do not define this interval elsewhere.
Actual plant trip setpoints for instruments and electrical equipment are set conservative with respect to Technical Specification allowable values, and are calculated such that the allowable values will not be 8707230630 e70713' PDR ADOCK 05000321 P pyg 1474C El-1 7/13/87 SL-2813
{ . _. _ _ _ _ - - _ _ _ _ _ - - - - - - - _ _ - - - - - - - - - _ __ - - - - - - - - - - - _ - - - - _ - - - - - - - -
ENCLOSURE 1 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
DEFINITION OF SURVEILLANCE FREQUENCY BASIS FOR CHANGE RE00EST i
compromised by instrument drift during the operating cycle, as this would result in a violation of Technical Specifications. The actual setpoints must be adjusted appropriately to accommodate longer cycles. Thus, application of the longer surveillance interval for instruments and electrical equipment will not result in increased probability that a Technical Specifications allowable value could be exceeded.
This change is requested to accommodate the potential that the current cycle 11 will exceed 15 months in duration. In order to preclude a potential shutdown solely for the performance of surveillance, it is requested that the proposed change be approved on a timely basis.
1 l
l 1474C El-2 7/13/87 1 SL-2813 ;
l ENCLOSURE 2 PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE NO. DPR-57 L
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
DEFINITION OF SURVEILLANCE FREQUENCY 10 CFR 50.92 EVALUATION Pursuant to' the requirements of 10 CFR 50.92, Georgia Power Company has -
evaluated the. proposed amendments for Plant Hatch Unit 1 and has determined that its adoption would not involve a significant hazards
. consideration. The basis for this determination is as follows:
' Prooosed Chance:
The definition ot "S"rvaillance Frequency" as provided in Section 1.0. of the current Plant Hatch Unit 1 Technical Specifications, is as follows.:
Periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals. These intervals may be adjusted plus or minus :25%.
The operating cycle interval as pertaining to instrument 'and electrical surveillance shall never exceed 15 months. In the case where the elapsed ' interval has exceeded 100% of the specified interval, 'the next surveillance interval shall commente at the end of the original specified interval.
The Plant Hatch Unit 1 Technical Specifications, which are in " custom" format, do not contain a " Surveillance Frequency Notation" table, as is provided in Table 1.1' of Standard Technical Specifications (STS). This STS . table defines the operating cycle interval as being equal to 18
. months. Moreover, Specification 4.0.2 of STS provides that all surveillance, including those performed on a once per cycle (18 month) basis, may be performed with a maximum allowable extension not to exceed' 25% of the surveillance interval.
The present Plant Hatch Unit. I definition, as provided above, is thus restrictive with respect to the NRC approved STS, in that; 1) The operating. cycle interval is restrained to .15, rather than 18, months, and; 2) The current wording can be interpreted to imply that the 25%
grace period is not applicable to once per cycle surveillance.
In order to provide requirements consistent with STS and Plant Hatch Unit 2, a change is proposed to the above definition. The proposed change would replace the sentence "The operating cycle interval as pertaining to instrument and electrical surveillance shall never exceed 15 months."
with the sentence "The operating cycle interval is defined as 18 months." This proposed change accomplishes two purposes: 1) It removes 1474C E2-1 7/13/87
'SL-2813
r ENCLOSURE 2 (Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
DEFINITION OF SURVEILLANCE FREQUENCY 10 CFR 50.92 EVALUATION the restrictions with respect to STS; and, 2) It provides a definition of the time interval which equals an operating cycle. This second purpose is necessary because the Plant Hatch Unit 1 Technical Specifications do not define this interval elsewhere.
Basis:
This proposed change implements requirements presently contained in NRC approved Standard Technical Specifications, including the Plant Hatch Unit 2 Technical Specifications.
Actual plant trip setpoints for instruments and electrical equipment are set conservative with respect to Technical Specification allowable values, and are calculated such that the allowable values will not be compromised by instrument drift during the operating cycle, as this would result in a violation of Technical Specifications. The actual setpoints must be adjusted appropriately to accommodate longer cycles. Thus, application of the longer surveillance interval for instruments and electrical equipment will not result in increased probability that a Technical Specifications allowable value could be exceeded.
The proposed change does not involve a significant increase in the probability or consequences of an accident because the same level of assurance will be provided that equipment setpoints remain within Technical Specification limits.
The possibility of a different kind of accident from those analyzed previously is not created by this change, since the design function of systems, as described in the FSAR, is not affected.
Margins of safety are not significantly reduced by this change. This change only provides for a definition of operating cycle interval which is consistent with NRC approved requirements contained in Standard Technical Specifications.
l l
1474C E2-2 7/13/87 SL-2813
l ENCLOSURE 3 PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 REQUEST TO REVISE. TECHNICAL SPECIFICATIONS:
DEFINITION OF SURVEILLANCE FREQUENCY PAGE CHANGE INSTRUCTIONS The proposed change to the Technical Specifications (Appendix A to Operating Licenso DPR-57) would be incorporated as follows:
Remove Page Insert Page ,
1.0-6 1.0-6 1474C E3-1 7/13/87 SL-2813
... s '.
I GG.
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
HH. Start & Hot Standby Mode The reactor is in the Start & Hot Stendby Mode when the Mode Switch is in the START & HOT STANDBY position. In this mode the reactor protection system is energized with IRM and APRM 1
(Start & Hot Standby Mode) neutron monitoring system trips and control l- rod withdrawal inter-locks in service.
II.
Surveillance Freauency - Periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals. These intervals may be adjusted plus or minus 25%. The operating cycle interval is defined as 18 months. In the case where l
the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
JJ. Surveillance Requirements - The surveillance requirements are requirements established to ensure that the Limiting Conditions for Operation as stated in Section 3 of these Technical Specifications are met. Surveil- .
lance requirements are not required on systems or parts of systems that are not required to be operable or are tripped. If tests are missed on parts not required to be operable or are tripped, then they shall be perforn:ed prior to returning the system to an operable status.
KK. Total Peakina Factor (TPF) - The total peaking factor is the highest product of radial, axial, and local peaking factors simultaneously operative at any segment of fuel rod.
LL. Transition Boiling - Transition boiling is the boiling that occurs between nucleate and film boiling. Transitirin boiling is manifested by an unstable fuel cladding surface temperature, rising suddenly as steam blanketing of the heat transfer surface occurs, then dropping as the steam blanket is swept away by the coolant flow, inen rising again.
I i
)
HATCH - UNIT 1 1.0-6 Proposed TS/0126q/84-31 R1 1