Similar Documents at Fermi |
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired ML20212H4351999-09-24024 September 1999 Proposed Tech Specs Re Util Request for Enforcement Discretion with Respect to TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20211Q1841999-09-10010 September 1999 Proposed Tech Specs Revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement ML20211Q7351999-09-0303 September 1999 Proposed Its,Rev 15 ML20211G0921999-08-25025 August 1999 Rev 14 Proposed ITS Pages,Providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20196F4681999-06-24024 June 1999 Rev 7 to ITS Submittal of 980403 to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8 ML20212H5041999-06-0202 June 1999 Proposed Tech Specs Pages to Rev 6 of Fermi Unit 2 ITS ML20206M1121999-05-0707 May 1999 Proposed Tech Specs Section 3.6,converting to ITS ML20206H5521999-04-30030 April 1999 Proposed Rev 5 to Improved TS Pages ML20205T5361999-04-20020 April 1999 Marked-up & Typed Up Revised TS Pages Eliminating TS SR for Nitrogen Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex ML20196K6621999-04-0202 April 1999 Proposed Tech Specs Re Rev 4 to Fermi 2 ITS Submittal ML20205A3201999-03-23023 March 1999 Proposed Tech Specs SR 4.4.1.1.1,requiring Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 & Stating *Not Used ML20202D9551999-01-26026 January 1999 Rev 2 to Fermi 2 Its,Incorporating Operating License Amends 119,122,128 & 129,issued Since Initial ITS Submittal Was Finalized ML20155A7111998-10-22022 October 1998 Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose ML20154E5621998-09-28028 September 1998 Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS ML20237E8981998-08-26026 August 1998 Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a ML20236W4701998-07-31031 July 1998 Proposed Tech Specs 3.5.1 & 3.5.2 Re Footnote for Limiting Condition for Operation ML20236U4601998-07-23023 July 1998 Proposed Tech Specs Revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals ML20236U0421998-07-16016 July 1998 TS Insert Page & Associated Index Page Reflecting Withdrawal of Request for Extension of Surveillance Interval for TS 4.0.5,as Contained in Enclosure 20 of & Administrative Change ML20236F0671998-06-26026 June 1998 Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L8021998-06-0505 June 1998 Proposed Tech Specs Section 2.1.2,re Thermal Pressure,High Pressure & High Flow ML20248E4151998-05-28028 May 1998 Proposed Tech Specs Page 3/4 5-1,revised to Include Remaining Proposed Changes W/Applicability Restored to Reflect Original Notation Re Realignment of LPCI Sys ML20247Q1191998-05-20020 May 1998 Proposed Tech Specs Pages Revising TS 3.1.3.1,Action D to Apply to Valves Inoperable for Any Reason & Increase Time Allowed for Restoring SDV Vent or Drain Line W/One Valve Inoperable from Current 24 Hours to 7 Days ML20247A7401998-04-27027 April 1998 Proposed Tech Specs Pages,Adding Configuration Risk Mgt Program to TS Section 6.8.5 ML20216F6971998-04-0909 April 1998 Proposed Tech Specs,Withdrawing Previously Submitted Response Time Testing Requirement Clarification Re Neutron Monitoring Sys ML20216J7581998-04-0909 April 1998 Proposed Tech Specs 3.3.7.5,3.7.1.2 & 3.8.1.1 Re Alignment of Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation ML20216B3311998-04-0303 April 1998 Proposed Tech Specs,Extending EDG Allowed Times at Plant ML20217P0631998-04-0202 April 1998 Proposed Tech Specs Re Mod of Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433 Rev 1, Std Tech Specs GE Plants BWR/4 ML20217P5691998-04-0202 April 1998 Proposed Tech Specs Changing Requirements Associated W/ Containment Oxygen & Hydrogen Monitors ML20217J5441998-03-27027 March 1998 Proposed Tech Specs Eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray ML20217J5841998-03-27027 March 1998 Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned ML20199H9371998-01-28028 January 1998 Proposed Tech Specs Re thermal-hydraulic Stability,Idle Recirculation Loop Startup & Post Accident Monitoring ML20199H2611998-01-28028 January 1998 Proposed Tech Specs Re Access Control to Provide Flexibility While Maintaining Similar Control Over Access ML20199H2561998-01-28028 January 1998 Proposed Tech Specs,Modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Requirements Per 10CFR50.36a ML20199H2501998-01-28028 January 1998 Proposed Tech Specs 4.4.3.2.2.a,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements ML20199H2411998-01-28028 January 1998 Proposed Tech Specs,Revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch Can Be Performed ML20199H2141998-01-28028 January 1998 Proposed Tech Specs,Revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement ML20199H2281998-01-28028 January 1998 Proposed Marked Up & Retyped TS of Sheet 2,Table 3.3.6-2, Deleting RCS Recirculation Flow Trip Functions ML20203F1941997-12-10010 December 1997 Proposed Tech Specs Revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20202A7961997-11-26026 November 1997 Proposed Tech Specs Reflecting Alternative Wording for Surveillance Which Address Only Clarification to Situational Testing Requirement NRC-97-0089, Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested1997-09-29029 September 1997 Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested ML20216F3581997-09-0505 September 1997 Proposed Tech Specs,Adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing ML20141B8881997-06-20020 June 1997 Proposed Tech Specs Re Relocation of Reactor Recirculation Sys MG Set Scoop Tube Stop Setting Surveillance 1999-09-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212H4351999-09-24024 September 1999 Proposed Tech Specs Re Util Request for Enforcement Discretion with Respect to TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired ML20211Q1841999-09-10010 September 1999 Proposed Tech Specs Revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement ML20211Q7351999-09-0303 September 1999 Proposed Its,Rev 15 ML20211G0921999-08-25025 August 1999 Rev 14 Proposed ITS Pages,Providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal ML20211B9861999-08-13013 August 1999 Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval ML20211C2631999-08-13013 August 1999 Rev 2,change 0 to ISI-Nondestructive Exam (ISE-NDE) Program (Plan) for Fermi 2 Power Plant, for Second ten-year Interval ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20210A3031999-06-30030 June 1999 Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan ML20196F4681999-06-24024 June 1999 Rev 7 to ITS Submittal of 980403 to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8 ML20212H5041999-06-0202 June 1999 Proposed Tech Specs Pages to Rev 6 of Fermi Unit 2 ITS ML20206M1121999-05-0707 May 1999 Proposed Tech Specs Section 3.6,converting to ITS ML20206M8651999-05-0606 May 1999 Rev 30,Vol I to Technical Requirements Manual ML20206H5521999-04-30030 April 1999 Proposed Rev 5 to Improved TS Pages ML20205T5361999-04-20020 April 1999 Marked-up & Typed Up Revised TS Pages Eliminating TS SR for Nitrogen Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex ML20196K6621999-04-0202 April 1999 Proposed Tech Specs Re Rev 4 to Fermi 2 ITS Submittal ML20205A3201999-03-23023 March 1999 Proposed Tech Specs SR 4.4.1.1.1,requiring Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 & Stating *Not Used ML20202D9551999-01-26026 January 1999 Rev 2 to Fermi 2 Its,Incorporating Operating License Amends 119,122,128 & 129,issued Since Initial ITS Submittal Was Finalized ML20198D1391998-12-14014 December 1998 Rev 28 to Vol 1 of Technical Requirements Manual ML20198B8121998-12-10010 December 1998 Rev 27 to Fermi 2 Technical Requirements Manual,Vol I ML20155A7111998-10-22022 October 1998 Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose ML20154Q0771998-10-15015 October 1998 6 to Fermi 2, Technical Requirements Manual, Vol I ML20154M4611998-10-0909 October 1998 5 to Vol 1 of Fermi 2 Technical Requirements Manual ML20154H8931998-10-0808 October 1998 Rev 24 to Fermi 2 Technical Requirements Manual,Vol I ML20154E5621998-09-28028 September 1998 Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS ML20153F3931998-09-23023 September 1998 Rev 23 to Fermi 2 Technical Requirements Manual,Vol 1 ML20237E8981998-08-26026 August 1998 Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a ML20237D6311998-08-18018 August 1998 Rev 22 to Fermi 2 Technical Requirements Manual,Vol 1 ML20236W4701998-07-31031 July 1998 Proposed Tech Specs 3.5.1 & 3.5.2 Re Footnote for Limiting Condition for Operation ML20236U4601998-07-23023 July 1998 Proposed Tech Specs Revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals ML20236U0421998-07-16016 July 1998 TS Insert Page & Associated Index Page Reflecting Withdrawal of Request for Extension of Surveillance Interval for TS 4.0.5,as Contained in Enclosure 20 of & Administrative Change ML20236F0671998-06-26026 June 1998 Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20236P9241998-06-10010 June 1998 Rev 20 to Fermi 2 Technical Requirements Manual, Vol 1 ML20248L8021998-06-0505 June 1998 Proposed Tech Specs Section 2.1.2,re Thermal Pressure,High Pressure & High Flow ML20248H0901998-05-31031 May 1998 Vol 1,Rev 19 to Technical Requirements Manual for Fermi 2 ML20248E4151998-05-28028 May 1998 Proposed Tech Specs Page 3/4 5-1,revised to Include Remaining Proposed Changes W/Applicability Restored to Reflect Original Notation Re Realignment of LPCI Sys ML20247Q1191998-05-20020 May 1998 Proposed Tech Specs Pages Revising TS 3.1.3.1,Action D to Apply to Valves Inoperable for Any Reason & Increase Time Allowed for Restoring SDV Vent or Drain Line W/One Valve Inoperable from Current 24 Hours to 7 Days ML20247A7401998-04-27027 April 1998 Proposed Tech Specs Pages,Adding Configuration Risk Mgt Program to TS Section 6.8.5 ML20216F6971998-04-0909 April 1998 Proposed Tech Specs,Withdrawing Previously Submitted Response Time Testing Requirement Clarification Re Neutron Monitoring Sys ML20216J7581998-04-0909 April 1998 Proposed Tech Specs 3.3.7.5,3.7.1.2 & 3.8.1.1 Re Alignment of Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation ML20216B3311998-04-0303 April 1998 Proposed Tech Specs,Extending EDG Allowed Times at Plant ML20217P5691998-04-0202 April 1998 Proposed Tech Specs Changing Requirements Associated W/ Containment Oxygen & Hydrogen Monitors ML20217P0631998-04-0202 April 1998 Proposed Tech Specs Re Mod of Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433 Rev 1, Std Tech Specs GE Plants BWR/4 ML20217J5841998-03-27027 March 1998 Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned 1999-09-03
[Table view] |
Text
. _ . _ . . . . . _ . . _ __ __. ._.
POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal tc or greater than the MCPR limit shown in Figure 3.2.3-1 times the Ky shown in Figure 3.2.3-2, with:
,, (Iave I B)
T ~I A B where:
1 4 = 1.096 seconds, control rod average scram insertion time limit to notch 36 per Specification 3.1.3.3, vg = 0.852 + 1.65[ N.06, ,
n Ng I
i=1 n
I I
ave = i=1 Ng tj ,
n '
I Ng i=1 n = number of surveillance tests performed to date in cycle, th N g = number of active control rods measured in the i surveillance test, tj = average scram time to , notch 36 of all rods measured in the i th surveillance test, and N N total number of active rods measured in Specification y = 4.1.3.2.a.
APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of l RATED THERMAL POWER. '
ACTION
- a. With MCPR less than the applicable MCPR limit shown in Figures 3.2.3-1 and 3.2.3-2, initiate corrective action within 15 minutes and restore MCPR to within the required limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less i than 25% of RATED THERMAL POWER with n j g gu,rs I
- b. With the main turbine bypass sys e inoperable per Specification 3.7.9, operation may continue and the provisions of Specification 3.0.4 are not '
applicable provided that, within one hour, MCPR is detemined to be equal to or greater than the MCPR limit as shown in Figure 3.2.3-1 by the main ,
erable curvitGiess the a g showninFigure3.2.3-2.l '
turbine bypass tendinop/,orin.es4on Seeara$Reke*+*pplicable K !
F 8801290338 880127 3/4 1 6 j PDR ADOCK 05000341 P PDR
"*1 P'1 D
T.
e-o I **$ . _ _ . _ .
Z . . - _ , .
_,._-__....g
-4 n- f_ . -.__ ..
O . . .
N . . . p .VI g e a
1 3p .
I .
_ . ~ . . . . . . _ . _ _
- ' ' ' - ~ ~ - '
I ~ ~ -
_ . ~ ~ ---
CU pvt B . . -~' ___. -
p-_ . _ . _ _ . . _ _ . .
t g s.
. CUR v t a f-
~ . . a G _-_ -..
w a qgg -.
.- + _ . -
N _ .. .
p - . _ ~
N . . _ - - .
w .. ..
. .- -.. . . . . - - .l j q$ . -- . . . . . _
. . . . . . . - m .
1 10 -- - -
} _ ___ . _ . . _ . . _ _ _ . .
C7 08 09 10 01 02 03 C4 C' C6 0
coRvt A - MCPR t.tMIT WITH MAIN TUR0 TNT HYPASS M O/ &[Ok CURVE B - MCPR t tutT wifMOUT MAIN TURBINE HYPASS O_d IN/
T RoarATe g Ct:1tvE C - utPR orn:T wom ur Mase TuRBlaf evensi M w TseouT mos3TutE SEPAR A. OJt.
MINIMUM CRITICAL POWER' RATIO (MCPR) VERSUS r AT RATED FLOW FIGURE 3.2.3-1 W
1 POWER DISTRIBUTION LIMITS BASES l 3/4.2.3 MINIMUM CRITICAL POWER RATIO The required operating limit MCPRs at steady-state operating conditions as specified in Specification 3.2.3 are derived from the established fuel cladding integrity Safety Limit MCPR of 1.06, and an analysis of abnormal operational transients. For any abnormal operating transients analysis evaluation with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time during the transient assuming instrument trip setting given' in l Specification 2.2. J To assure that the fuel cladding integrity Safety Limit is not exceeded i during any anticipated abnormal operational transient, the most limiting i transients have been analyzed to determine which result in the largest reduction in, CRITICAL POWER RATIO (CPR). The type of transients evaluated y re loss of flow, increa n in pressure and power, positive reactivity insertion, ,
and coolant temperature decrease. The limiting transient yields the largest I
delta MCPR. When added to the Safety Limit MCPR of 1.06, the required minimum I cperating limit MCPR of Specification 3.2.3 is obtained and presented in o- Figure 3.2.3-1.
. .T annn -t 5.c - I Th( evaluation of a given transient begins with the system initial parameters shown in46AR Tabled"'.^ ; that are input to a GE-core dynamic .
behavior transient computer program. The code used to evaluate pressurization events is described in NEDO-24154(3) and the program used in nonpressurization events is described in NED0-10802(2) . The outputs of this program along with the initial MCPR form the input for further analyses of the thermally limiting bundle with the sir.gle channel transient thermal hydraulic TASC code described in NEDE-25149(4) The principal result of this evaluation is the reduction in MCPR caused by the transient.
y The purpose of the fK factor of Figure 3.2.3-2 is to define operating limits at other than rated core flow conditions. At less than 100% of rated flow the required MCPR is the product of the MCPR and the Kf factor. The K f factors assure that the Safety Limit MCPR will not be violated during a flow increase transient resulting from a motor generator speed control failure. The Kf factors may be applied to both manual and automatic flow control modes.
The Kf factor values shown in Figure 3.2.3-2 were developed generically and are applicable to all BWR/2, BWR/3, and BWR/4 reactors. The Kf factors were derived using the flow control line corresponding to RATED THERMAL POWER at rated core flow.
For the manual flow control mode, the Kf factors were calculated such that for the maximum flow rate, as limited by the pump scoop tube setpoint and the corresponding THERMAL POWER along the rated flow control line, the limiting bundle's relative power was adjusted until the MCPR changes with different core flows. The ratio of the MCPR calculated at a given point of core flow, divided by the operating limit MCPR, determines the Kf.
FERMI - UNIT 2 B 3/4 2-4
l
.s INSEIG' TO PAGE B 3/4 2-4 The !CPR curves illustrated in Figure 3.2.3-1 were derived as dercribed above for the.following assumed operating conditions:
Curve A - ICPR limit with the main turbine bypass system and moisture separator reheater available. This represents a total reactor steam flow bypass capability of approximately 36 percent.
Curve B - bCPR limit with the main turbine bypass system inoperative and moisture separator reheater available.
This represents a total reactor steam flow bypass capability of approximately 10 percent.
Curve C - FCPR limit with both the main turbine bypass system and moisture separator reheater inoperative. This represents no reactor steam flow bypass capability.
Curve A provides the FCPR limit assuming operation above 25 percent PATED THEBMAL POWER with both the moisture separator reheater and main turbine bypass system operable. The curve was developed based upon the operating ICPR limits for a Rod WitMrawal Error transient (UFSAR, Section 15.4.2) and a Main Turbine Trip with Turbine Bypass Failure transient (UFSAR, Section 15.2.3) . The analysis of the Main Wrbine Trip with Turbine Bypass Failure takes credit for the steam flow to the moisture separator reheater.
Curve B provides the ICPR limit assuming operation above 25 percent RATED WEPJfAL PWER with the moisture separator reheater operable and the main turbine bypass system inoperable. 'Ihe curve was developed based upon the operating FCPR limits for a Feedwater Controller Failure with Inoperable W rbine Bypass transient. The analysis of the Feedwater Controller Failure transient also takes credit for steam flow to the moisture separator reheater.
Operation with the main turbine bypass inoperable or with a moisture separator reheater inoperable results in a total reactor steam flow bypass capability of approxi;nately 10 percent and 26 percent, respectively. The inpact of operation with the moisture separator reheater inoperable but with bypass operable arxl utilization of curve E, is conservative because the 26 percent bypass capability 1a less limiting with regard to the existing analysis used to establish Curve B which assunes only 10 percent bypass capability (with the main turbine bypass system inoperable) . Therefore, the operation above 25 percent RATED THEPMAL PONER with either the moisture separator reheater inoperable or main turbine bypass system inoperable is bounded by the existing Curve B.
INSERI' 'IO PAGE B 3/4 2-4 (cont.)
Curve C provides the EPR limit asst lJning Operation above 25 percent RATFD THEREL PONER with both the moisture separator reheater. and main -
turbine bypass. system inoperable. The curve was developed based upon the operating MCPR limits for a Feodwater Controller Failure with Inoperable 'nirbine Bypass transient assuming no steam flow through the moisture separator. reheater.
There is no mode change restraint should the main turbine bypass or the moisture separator reheater te inoperable. However, should the main turbine bypass system or the moisture separator reheater be inoperable as 25 percent FATED THEINAL PGER is exceeded, the !CPR check nust be conpleted within one hour.
1
(
PLANT SYSTEMS 3/4.7.9 MAIN TURBINE BYPASS SYSTEM ;
LIMITING CONDITION FOR OPERATION a d Meistume formaama R h +.,
l 3.7.9 The main turbine bypass systemishall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
daa Madona So aawe Rehe.+.e ACTION: With the mair turbine bypass systeDinoperable, restore the system to l UTERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or take the ACTION required by Specification 3.2.3. .
SURVEILLANCE REQUIREMENTS 2
4.7.9 The main turbine bypass' system shall be demonstrated OPERABLE at least once per:
- a. 92 days and during each COLD SHUTDOWN, by cycling each turbine bypass valve through at least one complete cycle of full travel, and
- b. 18 months by: '
)
- 1. Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.
- 2. Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to 300 milliseconds.
/
4 l
FERMI - UNIT 2 3/4 7-40 _ __ .__
9 PLANT SYSTEMS l BASES s
3/4.7.9 MAIN TURBINE BYPASS SYSTEM noroanir ,.onete+.n+ ut+g vm. . u ...m u ,_u._... , ,_ _ .......
4,
...a
.. u__ _
...ia., lm 8-m E(8
,AL E_ J A A _11 __ E_21. _m gg,
..m...,. , . . . . . . .... ..... ... ...... ..... ... . _ . - _.._ . ,
bhmbam k( -
C Y
l I
! /
FERMI - UNIT 2 B 3/4 7-5
I A
INSEld' 70 PAGE B 3/4 7-5 3/4 7.9 MAIN 7URBINE BYPASS SYSTB1 ihe main turbine bypass. system is an active bypass system designed to
, open the bypass valves in the event of a turbine trip to decrease the severity of the pressure transient. Each valve is sized to pass a nominal 13 percent reactor steam flow in the full-open position for a controlled total bypass of approximately 26 percent resctor steam flow. The main turbine bypass system is required to be OPEPABLE consistent with the assunptions of the Feedwater Controller Failure with Inoperable Turbine Bypass analysis.
The primary purpose of the moisture separator reheater is to inprove cycle efficiency by using primary system steam to heat the high pressure turbine exhaust before it enters the low-pressure turbines.
In doing so, it also provides a passive steam bypass flow of about 10 percent that mitigates the early effects of over-pressure transients.
The moisture separator reheater is required to be OPEPABLE consistent with the assunptions of the Main ibrbine Trip with Turbine Bypass Failure analysis and the Fecdwater Controller Failure analysis.
The operation with one or both of the main turbine bypasses inoperable or the moisture separator reheater inoperable to perform preventive or corrective maintenance above 25 percent FATED THEINAL POVER, requires, after one hour, the evaluation of the MCPR in accordance with Specification 3.2.3. If the MCPR is within the bounds established by Specification 3.2.3, power increases to or operation above 25 percent PATED THEH4AL PGiER is allowed.
l
._, . , - _ _ . _ - _ _ _ . _. ___. - _ _ _ _ _ _ _.