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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20095F5891995-12-12012 December 1995 Proposed Tech Specs Re Containment Sys ML20094D0611995-10-31031 October 1995 Proposed TS Page 6-18,deleting TS 6.9.2.d, Seismic Event Analysis ML20098C5181995-10-0202 October 1995 Proposed Tech Specs,Revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C4111995-09-29029 September 1995 Proposed TS 3/4.1.2.8 Re Reactivity Control Sys - Borated Water Sources - Shutdown TS 3/4.1.2.8 Re Reactivity Control Sys - Operating & TS 3/4.5.1 Re ECCS - Core Flooding Tanks ML20098C1121995-09-29029 September 1995 Proposed TS 3.4.3 & Associated Bases,Modifying Lift Setting of Pressurizer Code Safety Valves to Greater than or Equal to 2,575 Psig,Corresponding to Lift Setting Tolerance of +3% of Nominal Lift Pressure 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] |
Text
-
. l a
KFACTOR COOV. ANT SYSTEM lilC11 POINT [ENTS ,
J LIMITING CONDITION FOR OPERATION 3.4.11 The Feactor Coolant System will have two high point vents installed on it', one in each loop. One of these vents shall be OPERABLE.
For the vent to be OPERABLE, both valves in the vent will have to be OPERABLE. Each vent will have the following valves installed on it:
Reactor Coolant System Loop 1 RC4608A, RC4608B a.
Reactor Coolant System Loop 2 RC4610A, RC4610B b.
APPLICABILITY: MODES 1, 2 and 3 ACTION
- a. With both of the high point vents not OPERABLE, restore one vent to OPERABLE status within 30 days, or be in 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 />.
- b. The provisions of Specification 3.0.4 are not applicable.
r e
SURVEILLANCE REQUIREMENTS 4.4.11 No additional Surveillance Requirements other than ,those required by Specification 4.0.5, except that the Surveillance will be performed or.ce per 18 months during the COLD SHUTDOWN or REFUELING MODE.
n , . : . . n .. . c . p., ; , i 8205170 9 a
3 TABLE 3.3-10 (Continued) c POST-ACCIDENT MONITORING INSTROMENTATION ,
E -
MINIMUM CHANNELS INSTRUMENT . OPERABLE
- 15. Low Pressure Injection (OHR) Flow 1/ Channel .. ,
- 16. HPI System Pump and Valve Status 1/ System .
17.. LPI System Pump and Valve Status 1/Syste'm
$ l'8. Containment Spray Pump and Valve Status 1/ System
- 19. Core Flood Valve Status ,
1/ System i
- 20. BWST Valve Status -
1/ System
- 21. Containment Emergency Sump Valve Status 1/ Valve P2. Containment Air Recirculation Fan Status
. 1/ Fan
- 23. Containment Air Cooling Fan Status 1/ Fan
- 24. EVS Fan and Damper Status '
1/ System -
l
[ 25. . Auxiliary Feedwater Flow Rate 1/ Steam Generator i o ,
}
- 26. RC System Subcooling Margin Monitor -
1 .
u
, _ 27. PORV position Indicator , 1 6 *
- 20. PORY Block Valve Position Indicator -
1 h y .
- 29. Safety Valve Position Indicator 1/ Valve
- 30. BW',T Level -
.3
- 31. CONTAINMENT NORMAL SUM P LEVEL 1
- 32. CONTAINMEN_ T WIDE RANGE LEVEL 3
_ RR *2fdMR%UlMWMJKT_wmR_R Aur-;r__2RESSURE - - -- - --
~ - - - - .--
TABLE 4.3-10 (Continued)_ ,,
- c. POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS '
3 .
CHANNEL
~
G .
CHANNEL .
m INSTRUMENT CHECK , CAL *8 RATION .
M 15. Low Pressure Injection (DHR) Flow ,
H R i HPI System Pump and Valve Status M NA
- 16. .,
.E.
LPI System Pump and Valve Status M NA
, 17.
1 18. Containment Spray Pump and Valve Status M
. , y NA ,
^
i
- 19. Core Flood Valve Status M NA[
BWST Valve Status ,M NA
- 20. ,
Containment Emergency Sump Valve Status M NA 21.
s" NA Contair. ment Air Recirculation Fan Status M
. 22. .-
w . ,,
Containment Air Cooling Fan Status M NA 8 23. ,
EVS Fan and Damper Status M NA -
24.
~
Auxiliary Feedwater Flow Rate -
11 . R 25.
M R
- 26. RC System Subcooling Margiil Ibnitor ,
R 27 PORV Position Indicator 11
?j*
- 28. PORV Block Valve Posit. ion Indicator ,
il R
- 29. Pressurizer Safety Valve Position Indicator M , R .
- 30. BWST Level S R E
- 31. CONTAINMENT NORMAL SUMP LEVEL M '
g g- 32. CONTAINMENT WlDE RANGE LEVEL M R m 33. CONTAIN MENT WIDE RANGE PRESSURE M R g
N -6W w e , y,,,g pg , , , ,q
____ J
BASES r
3/4 _.4.11 HIGH POINT VENTS The operability of the high point vents ensures availability of a path to vent noncondensible gases frora the reactor coolant system which may inhibit natural circulation.
h e
s e
l i
a, .n..s- .e !
l 1
A Docket No. 50-346 i License No. NPF-3 Serial No. 803 May 5, 1982 4
Attachment 2 I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A, Technical Specifications and Table 3-7-1 and Bases.
A. Time Required to Implement This change is to be effective upon NRC approval.
B. Reason for' Change (Facility Change Request 79-177, Rev. A)
To allow credit for excess flow relieving capacity and permit higher power operatica in the event of inoperable safety valves.
C. Safety Evaluation (See attached) r 4
t i
+
- .. . - . 1
l 1
l SAFETY EVALUATION The safety function of the main steam safety valves is to provide over-pressure protection for the steam generator secondary side. There are 18 safety valves (9 per steam generator) which were designed in accordance with ASME Section-III, Article 9, 1968 Edition. The specified valve lift settings and relief capacities are in accordance with the 1968 Edition but, as these values are more conservative, they meet the requirements of the ASME code for Class II components, 1971 Edition, (as referenced in Technical Specifications B 3/4 7.1.1) specifically:
Relieving Capacity of Pressure-Relief Devices (NC-7411)
The total rated relieving capacity of the pressure relief devices intended for overpressure protection of a nuclear power system whose components are within the scope of subsection NC shall be sufficient to prevent a rise in pressure of more than ten percent above system design pressure (at design temperature) within the protected boundary of the system under any pressure transients anticipated to arise.
Set Pressure Limitations (NC-7511)
The set pressure of at least one of the pressure-relief devices connected to tha system shall not be greater than the maximum allow-able working pressure of the system (at design temperature) which it protects. Additional pressure-relief devices, other than safety-relief and liquid-relief valves, may have higher set pressures but in no case shall the set pressures be such that the total accumulated pressure exceeds 110 percent of the system design pressure.
The proposed change to the Davis-Besse Technical Specifications specifically addresses the equation for deriving the reduced high flux trip setpoint as a function of inoperable main steam line code safety valves (Section B 3/4.7.1.1). The safety function of this Technical Specification is to assure that adequate secondary side steam relieving capacity is maintained in the event of inoperability of one or more main steam safety valves.
This is accomplished by reducing The Reactor Protection System high flux trip setpoint which is calculated using the equation referred above.
In the present form, the equation uses the total relieving capacity as the installed capacity. When examined closely, this disallows credit for the excess installed capacity of the safety valves at Davis-Besse. This l excess is calculated to be the installed minus the required capacity, 120%
- 112% = 8%.
The proposed change to the equation is to use the required relieving
! capacity as the base line value. This means that reductions from the required relieving capacity would necessitate a corresponding reduction in I
l l
I
power. This would allow credit for excess flow relieving capacity and permit higher power operation in the event of inoperable safety valves. l The proposed equation is: .
(X) - (Y)(V)
SP = Z x 104.9
}
where:
SP = Reduced trip setpoint in percent of RATED THERMAL POWER *.
(not to exceed 104.9)
V = Maximum number of inope'.ible safety valves per steam
104.9 = High flux trip setpoint specified in Table 2.2.1.
X = Total relieving capacity of all safety valves (installed) per steam generator in pounds per hour, 7,087,500 lbs/ hour.
Y = Maximum relieving capacity of.any one safety valve in pounds per hour, 845,759 lbs/ hour.
Z = Required relieving capacity per steam generator in pounds per hour, 6,585,600 lbs/ hour.
i This modified equation is a more accurate representation of flow relieving capacity installed at Davis-Besse. The change wop 1d allow greater permis-sible power generation in the event of inoperable code safety valves without degradation of any safety factors or violation of the requirements
] of Section III of the ASME Boiler and Pressure Vessel Code, 1971 edition (as outlined above). Further, this proposed change would have no detri--
mental effect on the station's ability to prevent er mitigate the conse-quence(s) of an accident and the safety function of tre Technical Specification remains unaltered.
, Pursuant to the above, it is concluded that the technical specification change does not constitute an unreviewed safety question.
U
- Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of 2772 MW .
o b
, --Y', -
.me . -cy_'; . ,w - ,
7, 4 .e -
DESIGN DATA AND CALCULATIONS f
The following design data has been established on a per steam generator basis:
Secondary Side Design Pressure, psig 1050 Design Temperature, *F 600 6
Steam Flow (outlet), lbs/hr 5.99 x 10 .
The to*.al rated relieving capacity for the 18 installed safety relieve valves has been established as:
14 (6" x 10") valves at 845,759 lbs/hr = 11,840,6'26
- 4 (6" x 8") valves at 583,574 lbs/hr = 2,334,296 14,174,922 lbs/hr This is equivalent to 120% of the total secondary steam flow at 100% rated thermal power.
The maximum design reactor power operation has been established at 112%.*
- The maximum reactor power operation is 112% - 7.1 = 104.9% where 7.1% is the nuclear instrumentation (NI) error. 104.9% is the reactor protection system maximum high flux trip setpoint in Technical Specifications Table 2.2.1.
Therefore,.the total required relieving capacity is calculated to be:
0 112% [2(5.88 x 10 lbs/hr)] = 13,171,200 lbs/hr jh b/4 6
m, 3/4.7 PLANT SYSTEMS
- r BASES- ,
. 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% its design pressure of 1050 psig during the most severe anticipated syst'em operational transient. The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with-an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Vessel Code,1971 Edition. The total relieving capacity for all.
valves on all of the steam is 14,175,000 lbs/hr which is 120 percent of the total secondary steam flow of 11,760,000 lbs/hr at 100% RAfE0 THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7~-1.
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the High Flux channels. The reactor trip setpoint reductions are derived on the following bases:
SP , (X) - (Y)(V) x
,nc e
,us.a j o .y. 9
,y where:
SP = reduced Trip Setpoint in percent of RATED THERMAL POWERt (pod z o ExcEEc//of.9.7 V = maximum number of inoperable safety valves per steam generator
/M.9 465:5- = High Flux Trip Setpoint specified in Table 2.2.1 X = Total relieving capacity of all safety valves per steam generator in lbs/ hour, 7,087,500 lbs/ hour Y = Maximum relieving capacity of any one safety valve in lbs/ hour, 845,759 lbs/ hour E = /Ya. wired eclk&M c/ pac /h ps n :Wemt _
Ccwe-/M:'s /2 ir/ pdudeb pCA he u.C, 6,J YsG 600 ~b .h< .
DAVIS-BESSE, UNIT 1 B 3/4 7-1
(
g TABLE 3.7-1 2
i,n m MAXIMUM ALLOWABLE HIGH FLUX TRIP:SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES N - -
c E Maximum humoer of Inoperable Safety Maximum Allowable.
- Valves on Any Steam Generator High Flux Trip Setpoint .
- (Percent of RATED THERMAL POWER!
{ l P 4
02.01 97.92 2
S0. 32- Rf. 95 3
E?.73 '7 2 *Y 8 a
% 4 55,14 g9, of a
5 -
^2.55 4/S.5Y 6
, 20.00- 3 2 . o f s 7
17.25 /8.59 O
e Oe e n
__ _.___ _ _ _ . _ ._