Letter Sequence Other |
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MONTHYEARML20214T3081986-09-24024 September 1986 Proposed Tech Spec Pages 5.6-1 & 5.6-2,changing Frequency of Standby Diesel Generator Surveillance.Safety Evaluation & Significant Hazards Consideration Encl Project stage: Other ML20214T3001986-09-24024 September 1986 Application for Amend to License DPR-34,changing Tech Specs for SR 53.6.1, Standby Diesel Generator Surveillance, Re Testing Frequency for safety-related Bus Voltage Sensing Circuit & Auto Sequencing of Safe Shutdown Loads Project stage: Request ML20214T2801986-09-24024 September 1986 Forwards Application for Amend to License DPR-34,changing Tech Specs for Standby Diesel Generator Surveillance.Diesel auto-start Capability on Simulated Loss of Bus Voltage Proposed to Be Tested Every 6 Months.Fee Paid Project stage: Request ML20215K7161986-10-21021 October 1986 Ack Receipt of Re Proposed Tech Spec Change to Standby Diesel Generator Surveillance.Item Being Reviewed Under TAC 63029 W/Target Completion Date of 870415 Project stage: Other ML20205F7891987-03-25025 March 1987 Confirms That Util Normally Loads Each Standby Diesel Generator at Facility to Approx Full Load During Weekly Testing,Per 870318 Telcon & Util 860924 Request to Change Tech Spec Surveillance Requirement 5.6.1 Project stage: Other ML20205M3271987-03-30030 March 1987 Requests Fr Publication of Notice of Consideration of Issuance of Amend to License DPR-34 & Proposed NSHC Determination & Opportunity for Hearing Re 860924 Request Concerning Loss of Offsite Power Test Project stage: Other ML20214M4681987-05-20020 May 1987 Safety Evaluation Supporting Amend 54 to License DPR-34 Project stage: Approval ML20214M4401987-05-20020 May 1987 Amend 54 to License DPR-34,modifying Surveillance Requirements for Standby Diesel Generator Project stage: Other ML20214M4151987-05-20020 May 1987 Forwards Amend 54 to License DPR-34 & Safety Evaluation. Amend Modifies Surveillance Requirements for Standby Diesel Generators Project stage: Approval 1987-03-25
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7811989-09-14014 September 1989 Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation ML20247L1721989-09-14014 September 1989 Proposed Tech Specs Re Reactivity Control ML20247J2371989-09-14014 September 1989 Proposed Tech Specs Re Fuel Handling & Storage ML20247G7341989-09-14014 September 1989 Proposed Tech Specs Deleting Fire Protection Limiting Condition of Operation & Surveillance Requirements from Tech Specs ML20246K9921989-07-14014 July 1989 Proposed Tech Specs Documenting Improvements to Battery Surveillance Procedures ML20246L0231989-07-14014 July 1989 Proposed Tech Specs,Rewording Basis for Limiting Condition for Operation 4.2.2 Re Operable Circulator ML20244B3771989-06-0909 June 1989 Proposed Tech Specs Re Early Shutdown of Plant ML20245B3211989-04-14014 April 1989 Proposed Tech Specs Re Radiation Monitors & Noble Gas Monitors ML20155J6281988-10-14014 October 1988 Proposed Tech Specs Concerning Administrative Controls ML20155J6111988-10-14014 October 1988 Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E8171988-10-13013 October 1988 Proposed Tech Specs Re Linear channel-high Neutron Flux Trip Setpoints ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries ML20155J7181988-06-14014 June 1988 Revised Draft Tech Specs 3/4.6.5.2,deleting Charcoal Filter Test Exceptions After Painting W/Low Solvent paints,6.5.1.2 & 6.2.3.3,reflecting Recent Util Reorganization & 3/4.7.1.5 & 3/4.7.1.6,requiring One Operable Valve Per Loop ML20151R8191988-04-20020 April 1988 Proposed Tech Specs,Deleting 10CFR51.5(b)2 ML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery ML20148N2751988-03-29029 March 1988 Proposed Tech Specs,Deleting Requirement to Monitor Ambient Temp in Instrument Penetrations Housing Flow Sensors for Dewpoint Moisture Monitoring Sys ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements ML20149N0391988-02-0505 February 1988 Proposed Tech Specs Re Changes to Administrative Controls to Reflect Organizational Changes in Util & NRC ML20238C3481987-12-23023 December 1987 Proposed re-drafted Tech Specs,Upgrading Sections Re safety- Related Cooling Sys.Related Info Encl ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements ML20235W8611987-10-0101 October 1987 Proposed Tech Specs,Clarifying Actions on Inoperable Halogen or Particulate Monitors & Conditions Requiring Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp ML20210B7081987-04-23023 April 1987 Proposed Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys Parameters ML20206P3931987-04-0808 April 1987 Proposed Tech Specs,Revising 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserve Shutdown Sys,Per Rev 4 to FSAR, Section 3.5.3.3 ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs ML20207D2421986-12-23023 December 1986 Proposed Tech Specs Deleting Snubber Tables & Correcting Typos ML20212A0661986-12-19019 December 1986 Proposed Tech Specs Re Steam Line Rupture Detection/ Isolation Sys 1996-02-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
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- Fort St. Vrain #1 Technical Sp:cifications Amendment Page 5.6-1 5.6 EMERGENCY POWER SYSTEMS - SURVEILLANCE REQUIREMENTS A_pplicability Applies to the surveillance of the equipment supplying electrical power to the essential plant services.
Objective To establish the minimum frequency and type of surveillance for equipment supplying electric power to the olant auxiliaries to ensure that the motive power sources required to safely shut down the plant are available.
Specification SR 5.6.1 - Standby Diesel Generator Surveillance The surveillance of the standby diesel generators shall be as follows:
a) Each standby generator set will be started and loaded to at least 50". of rated full load capacity once per week.
The test shall continue for at least two hours to enable the engine (s) and the generator to Ettain their normal operating temperatures.
b) A loss of outside source of power and turbine trip shall be simulated to demonstrate that the standby generators and automatic cont: ol s are operable. This Surveillance Requirement shall be performed at least once per 6 months with a maximum allowable extension of 2 months per surveillance interval such that the maximum combined time interval for 3 consecutive surveillance intervals shall not exceed 20 months.
c) The diesel engine protection functions shall be calibrated annually.
, d) The diesel engine exhaust temperature " shutdown" and i
"declutch" shall be functionally tested monthly and calibrated annually.
8609300257 860924 PDR P ADOCK 05000267 pyg
Fort St. Vrain #1 Technical Sp;cifications Amendment Page 5.6-2 e) A loss of outside source of power and turbine trip shall be sinulated at least once per refueling cycle, not to exceed eighteen (18) months, to demonstrate that the stancby generators, automatic controls and load sequencers are operable. This surveillance may be performed in lieu of SR 5.6.1.b above.
Basis for Specification SR 5.6.1 The purpose of the weekly test of the standby diesel generator is to exercise the engine by operating at design temperature and to demonstrate operating capability. These tests will allow for '
detection of deterioration and failure of equipment.
The purpose of the loss of outside source of power and turbine trip test (SR 5.6.1.b), performed twice annually is to verify that the standby generator (s) are capable of starting automatically upon a simulated loss of outside power and turbine trip. SR 5.6.1.e, performed at refueling intervals, verifies the same features as SR 5.6.1.b but, additionally, verifies that the load sequencers automatically pick up required loads in the event of a loss of voltage on the 480V essential buses.
Specification SR 5.6.2 - Station Battery Surveillance The surveillance of the station and PPS batteries shall be as follows:
a) The specific gravity and voltage of the pilot cell and tamperature of adjacent cells and overall battery voltage shall be measured every week.
b) The specific gravity and voltage to the nearest 0.01
/ volt, temperature of every fif th cell and height of electrolyte shal! be measured every three months.
s c) The station and PPS batteries shall be load-tested to partial discharge once a year during plant shutdown.
Basis for Specification SR 5.6.2 The type of battery surveillance called for in this specification has been demonstrated through experience to provide a reliable indication of a battery cell initial breakdown well before it becomes unserviceable. Since batteries will deteriorate with time, these periodic tests will avoid precipitious failure.
The marufacturer's recommendation for equalizing charge is vital to maintenance of the ampere-hour capacity of the battery. As a check upon the effectiveness of this charge, each battery will be load tested to determine its ampere-hour capacity. In addition, its voltage shall be monitored as a function of time. If a cell has deteriorated or if a connection is locse, the voltage under load will drop excessively, indicating need for replacement er maintenance.
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Attachment 3 I f i
! SAFETY EVAL.UATION t
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Attachment 3 to P-86549 Safety Evaluation The surveillance requirements for the standby generators incorporate periodic testing and surveillance to verify the capability of the standby generators to perform as an emergency power source for essential loads. On a weekly test basis, the standby generators are started from ambient conditions and manually loaded to at least 50%
rated full load capacity for at least two hours. Diesel engine protective functions are calibrated annually. Diesel engine exhaust temperature " shutdown" and "declutch" functions are tested monthly and calibrated annually.
In addition to the above tests, the standby generators are tested twice annually with respect to their " system design function" as
. verification of the overall electrical system reliability for the Fort St. Vrain nuclear generating station.
That is, the standby generators function as an emergency source of electrical power to essential loads in the event of a loss of power to the essential buses.
Public Service Company of Colorado proposes to verify the operability of the standby generators while minimizing unnecessary surveillance shutdowns between refueling intervals.
Reliability of the electrical system and loads on the electrical system are enhanced by minimizing electrical system disturbances ac j maintaining steady state electrical system parameters. Additionally, minimizing reactor plant startups and shutdowns enhances overall plant reliability by maintaining steady state conditions and avoiding thermal cycling of the PCRV, piping and other high energy systems.
At present, a severe electrical disturbance to the electrical system is deliberately induced twice annually to verify that the standby generators will automatically start and pick up essential loads. The probability of electrical malfunctions and/or system upsets is increased due to loss of voltage and subsequent reenergization of dead buses. While it is desirable to veri fy that capability periodically, system upsets should be minimized. The standby generators can be verified as a reliable emergency power source with a high degree of confidence by observing that they start automatically upon a simulated loss of power to the buses at least once per 6 months as presently prescribed by the Technical Specifications with some allowance for operations scheduling.
Additionally, to provide that extra degree of confidence, the load sequencers would be verified operable at least once per refueling cycle when the plant is shutdown. The overall confidence in the emergency power source function of the standby generators is not- in question. The potential consequences of a severe power disruption are, however, minimized.
Verification that the standby generators respond automatically to a simulated loss of power signal using installed and normally operating circuits provides high confidence that the system will perform as designed. Thus, the twice annual performance of.the loss of outside source of power and turbine trip without stripping essential buses of their normal loads and sequencing on of essential loads maintains the desired high confidence level that the standby generators start in response to the low voltage condition.
However, the refueling cycle surveillance test will verify overall electrical system operability but with minimal impact to plant systems and components due to its less frequent system perturbation.
Overall system reliability is expected to be enhanced as potential failure mechanisms associated with power disruptions are reduced.
Consideration of the proposed changes to standby diesel surveillance involves evaluation of accidents or equipment functions previously 4
evaluated in the FSAR. As required by 10CFR50.59, the following questions are addressed:
- 1) Has the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR been increased?
As the direct result of reducing the frequency of load shedding and reenergizing essential loads with the standby.
generators, no abnormal modes of plant operation are required. Potential failure mechanisms associated with power disruption are- in fact, reduced. Thus, the probability of occurrence or consequences of an accident or
~ ' equipment malfunction previously evaluated in the FSAR has not been increased.
- 2) Has che possibility of an accident or malfunction of a different type than any evaluated previously in the FSAR been created?-
No. As discussed above, the surveillance test presently performed twice annually will be rescheduled to a refueling cycle interval. The standby generators will still be l started twice annually to verify automatic start capability i upon simulated loss of outside power and turbine trip. No j new tests or tests of a different type are proposed.
- 3) Has the margin of safety, as defined in the basis for any Technical Specification been reduced?
(
No. The emergency power source system (standby generators
, and associated circuits) is not changed as a result of the i proposed Technical Specification change.
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Public Service Company of Colorado concludes that the operability of the standby generators is verified by the proposed surveillance j testing. The severe power disruption caused by stripping essential l buses of loads and reenergizing these loads with the standby l generators is reduced to one-half to one-third of the the previous license interval in these proposed Technical Specifications changes. :
PSC considers these changes to be an improvement in overall plant l reliability as the result of minimizing electrical power disruptions j
.and plant startups and shutdowns. Thus, these proposed changes to :
the Fort St. Vrain Technical Specifications do not result in an unreviewed safety question. l
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> l l SIGNIFICANT HAZARDS CONSIDERATION 1
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Attachment 4 to P-86549 SIGNIFICANT HAZARDS CONSIDERATION I. Evaluation Based upon the safety evaluation provided as Attachment 3 to this i
Technical Specification change, it is concluded that the change in frequency of testing the standby generators involving actual load I shedding and reenergizing loads taken together with the total
- proposed surveillance testing verifies standby generator operability.
'It is further concluded that the proposed changes do not result in- ,
- an unreviewed safety question.
- 1. Neither the probability nor consequences of accidents previously evaluated have been affected by this proposed Technical Specification change. The frequency of performing a surveillance presently required is reduced. from twice annually to once per refueling cycle. An emergency diesel generator surveillance verifying automatic start and run features but not requiring load shedding _and subsequent a
reenergization of loads is still proposed to be performed ;
! twice annually. Thus, standby generator operability is
! affirmed semiannually.by proper operation of the loss of power sensing circuits and auto-start capabilities of the standby generators.
- 2. The possibility of a new or oifferent kind of accident from those previously evaluated has not been introduced. The
, proposed testing still verifies diesel generator operability using previously used and understood tests but reduces the frequency of power disruptions to essential loads.
- 3. No margins of safety have been reduced as a result of the proposed surveillance changes. The proposed changes in surveillance testing involve testing already performed with plant effects well understood.
II. Conclusion d
Based on the evaluation provided above, it is concluded that operation of Fort St. Vrain in accordance with the proposed changes
- will not (1) involve a significant inci9ase in the probability or consequences of an accident previously eva'uated, (2) create the possibility of a new or different~ kind of actident from any accident previously evaluated, or (3) involve a significant reduction in any margin of safety._ Therefore this change will ne
- ther create an undue risk to the health and safety of the public nor involve any significant hazards consideration.
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