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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS ML20115J0181996-07-18018 July 1996 Proposed Tech Specs 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20107H3931996-04-17017 April 1996 Proposed Tech Specs 3/4.3 Re Adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2 & Revising Table 3.3-3 by Adding Action Statements 27a & 34a ML20107F0791996-04-12012 April 1996 Proposed Tech Specs 3/4.4 Re Changing TS, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant SGs ML20107E3251996-04-12012 April 1996 Proposed Tech Specs 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases,Addressing Installation of Laser Welded Tube Sleeves in Plant SGs ML20101R4211996-04-0909 April 1996 Revised TS Pages That Adhere to Testing Methods of ASTM Std D2276-78,Method a for Diesel Fuel Oil Particulate Concentration ML20101J0381996-03-22022 March 1996 Proposed Tech Specs,Implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4351996-02-28028 February 1996 Proposed TS 3/4.8.1,ac Sources ML20106G4131996-02-23023 February 1996 Proposed Tech Specs Paragraph 1.A. Re Operating License Change to Reflect Union Electric as wholly-owned Subsidiary of Ameren Corp ML20097D5801996-02-0909 February 1996 Proposed Tech Specs Allowing Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6151996-02-0909 February 1996 Proposed Tech Specs & Bases Re Containment Systems ML20097D6341996-02-0909 February 1996 Proposed Tech Specs Re AFW Sys ML20097F8991996-02-0404 February 1996 Proposed Tech Specs 4.6.1.2.a Re Containment Sys ML20097C2791996-02-0202 February 1996 Proposed Tech Spec 3/4.6.3, Containment Isolation Valves ML20096B1891996-01-0202 January 1996 Proposed Tech Specs 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ML20094A1721995-10-23023 October 1995 Proposed Tech Specs,Relocating Audit Frequencies in Former TS 6.5.2.9 to Operational QA Manual 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20135E7351996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt One H Replacement Matl ML20135E7391996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt Three H Replacement Matl ML20135E7431996-12-11011 December 1996 Test to Determine Ampacity Derating Factor for Electrical Conductors Installed in 600mm X 101mm X 3650mm Long Cable Tray Encapsulated by KM1 Darmatt Three H Replacement Matl ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS 1999-09-08
[Table view] |
Text
- ._. - . _ - _ . - . _ - -
~
ULNRC- 14 76 Attachment 1-PROPOSED TECHNICAL' SPECIFICATION' CHANGES 8704070074 870327 PDR ADOCK 05000483 P PDR l
i I.
IABLE 3.3-3 (Crntinu d)
['p ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
? .;
, g, MINIMUM t
s j.
TOTAL NO.
CHANNELS CHANNELS APPLICA8tE '
[ % FUNCTIONAL UNIT OF CHANNELS TO TRIP DPERABLE M00E5
c 6. Auxiliary Feedwater (Conti'nued)
{ d. Steam Generator Water Level-Low-Low (Continued) it
- 2) Start Turbine- {
I Driven Pump 4/sta gen. 2/sta. gen. 3/sta gen.
i 1, 2, 3 19*
in any in each 2 operating operating sim. gen.
sim. gen. ,
- e. Safety Injection j .
Start Motor-Driven Pumps 'See Item 1. above for all Safety Injection initiating functions and I
4 requirements. {I-4
- f. Loss-of-Of fsite Power- ~
{ 5 tart Turbine-Oriven Pump 2 1 2 1, 2, 3
.22 3
i Y g. Trip of All Mah, M Feedwater Pumps - f Start Motor-Oriven Pumps 4-(2/ pump)** 2-(1/ pump 3 1, 2 ### 19 in same *.
separation)
- h. Auxiliary Feed- D l-water Pump Suction b Pressure-Low j (Transfer to E5W)
- 7. Automatic Switchover to 3 2 2 1,2,3 15*
k} ! b I Containment Sump gy, g f.
- a. Automatic Actuation
j Logic and Actuation 1 2 1,2,3,4 14 (4 J '
Relays (55PS) 8 y n b.
g 4 t g
RWST Level - Low-Low 4 2 3 .
1, 2, 3, 4 16 Coincident With M 4T i Safety injection a See Item 1. above for Safety injection initiating functions and -
a requirements. i i
t
~( I Q ._
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. . ,e m, ees.. -eay- * " * * ' ' '
, , , .._n_.y~, -,.----~~-:~-~~~~r'-~~ ,
,,,.4,,
a ,
~~
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. ~ . . - , . , . . .x .: - - ~ ~ _.=. _.. . . . ..
- - --.a _ w :-- -
hl kJhe thtk hlW ;
~
, REVISION 1 TABLE 3.3-3 (Continued) m, TABLE NOTATION . , ,
- Trip f unction may be blocked in this MODE below the P-11 (Pressurizer
- h' Pressure Interlock) Setpoint.
- Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked. .
H* ZNMRT A '
- lhe provisions of Specification 3.0.4 are not applicable.
""One in Separation Group 1 and one in Separation Group 4 ,
ACTION STATEMENTS ACTION 14.- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE. .
ACTION 15 - With the number of OPERA'BLE channels one less than the Total Number of Channels, operation may proceed until performance of ,
the next required ANALOG CHANNEL OPERATIONAL TEST provided the '.
inoperable channel is placed in the tripped condition within i U
~
I hour. . [,
V:
ACTION LG - With the number of OPERABLE channels one less than the Total '
Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum i Channels OPERABLE requirement is set. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per b};
Specification 4.3.2.1. ,
ACil0N 17 - With less than the Minimum Channels OPERABLE requirement, !
operation may continue provided the containment purge supply ;-
and exhaust valves are maintained closed. ,
AC110N 18 - With the number of OPERABLE channels one less than the Minimum !.I Channels OPERABLE requirement, restore the inoperable channel l Lo OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANOBY ,
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hourt,. -
1<
ACTION 19 - With the number of OPERABLE channels one less than the Total
N' umber of Channels, STARTUP and/or POWER OPERATION may proceed ..,
provided the following conditions are satisfied: [
- a. The inoperable channel is placed in the tripped condition within i hour, and .l
\ >
1 -
f CAllAWAY - UNIT I 3/4 3-20 "
i
.- .j . - - -, ., . . - . . . . ...
l l
~
ULNRC- 14 76 Attachment 1-INSERT A Trip function may be blocked just before shutdown of the last operating main feedwater pump and restored just after the first main feedwater pump is put into service (following.its startup trip test).
l
. ULNRC 1476 Attachment 2 SAFETY EVALUA,TI,OJ{
This amendment application requests that the applicable modes for Item 6.g of Technical Specification Table 3.3-3 be clarified regarding the blocking of auxiliary feedwater (AFW) start signals during normal plant startups and shutdowns. A note would be added to clarify the use of switches in mode 2 that block the automatic signal which starts the motor-driven auxiliary feedwater pumps (A and B) upon the trip of both main feedwater pumps. This note would allow the blocking of this signal just before shutdown of the last operating main feedwater pump during plant shutdowns and would require the restoration of this function just after the first main feedwater pump is placed into service during plant startups. This change would not affect the other AFW start signals (i.e., safety injection signal, loss of offsite power, low-low level in 2 out of 4 channels in any one steam generator) which will be operable at all times during their applicable modes, as given by Table 3.3-3, and available to respond to accident situations.
This amendment application would render the Technical Specifications consistent with NUREG-0830, SER related to the operation of Callaway Plant, and with the FSAR. Section 7.3.2.7 of the former notes that the signal to initiate AFW when the main feedwater pumps are tripped is considered to be an " anticipatory signal" for which no credit is taken in the accident analyses.
In the accident analyses for Cycle 2 (and future cycles), AFW is assumed to be actuated by the low-low steam generator water level signal. Further, the SER states that " bloc <ing will be permitted just before shutdown of the last operating main feedwater pump and removed just after the first main feedwater pump is put into service." The SER concludes that, with bypass indication of the block and operating procedures that appropriately constrain the use of the block switches, the design is acceptable. FSAR Section 7.3.6.1.1.a is consistent with the SER, as follows:
" Manual block of the main feed pump trip signals is provided at the main control board, and is indicated on the ESFAS status panel. This block permits startup and shutdown of the plant without automatic start of the AFPs, while allowing the AFPs to remain available to respond to a demand from any other source."
Since this amendment application does not affect any assumptions made in the safety analyses (i.e., no effect on low-low S/G level signals) nor does it change any of the licensing (
bases for the plant (i.e., SER and FSAR), the change discussed herein would not adversely affect or endanger the health of the general public and does not involve an unreviewed safety question. ,
l
\
~ ULNRC- 14 76 Attachment 3 SIGNIFICANT HAZARDS CONSIDERATIONS This amendment application requests that the applicable modes for Item 6.g of Technical Specification Table 3.3-3 be clarified regarding the blocking, during normal plant startups and shutdowns, of auxiliary feedwater (AFW) start signals which are automatically generated upon the trip of both main feedwater pumps. This clarification would be in the form of a note that would allow the blocking of this start signal to the motor-driven AFW pumps just before shutdown of the last operating main feedwater pump during plant shutdowns and would require the restoration of this function just after the first main feedwater pump is placed into service during plant startups. The following discussions address significant hazards evaluations associated with this change.
This change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
No credit is taken for this start signal in the accident analyses which assume that AFN actuation is generated by the low-low steam generator water level signal. This change has no effect on this or other start signals (i.e., safety injection signal, loss of offsite power) which remain available to respond to accident situations. The use of the block switches precludes the undesired ESF actuation during plant startups and shutdowns under conditions where the motor-driven startup feedwater pump provides the necessary feedwater source.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. This is based on the fact that the method and manner of plant operation is being clarified to achieve consistency with those documents establishing the licensing bases for Callaway Plant (i.e., NUREG-0830, SER related to the operation of Callaway Plant, Section 7.3.2.7 and FSAR Sections 7.3.6.1.1.a, 15.2.6, and 15.2.7).
This change does not involve a significant reduction in a margin of safety. This is based on the fact that no design changes are involved and the change to clarify mode applicability ,
is consistent with NRC's safety evaluation of the auxiliary l feedwater system actuation design. j The Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain examples (48FR14870). This change request is similar to the example of a change involving no significant hazards which relates to a change that is administrative in nature. The change
t ULNRC-14 76 4 - Attachmsnt 3 provides-consistency between the Technical Specifications and the Safety Evaluation Report (NUREG-0830) and'the FSAR. As such, the requested amendment.does not present a significant. hazard.
t-I
4 ULNRC- 14 76 Attachment 4 4
Application Fee CHECX NUMBER 80 0245 m
UNION ELECTluC COMPANY sr.ums.wssoum 219756 10 ceNicaat eANx or xtNNeTr. uissouai 4591 oa'r ^"aa' PAY .
$ ** * * ** 150 00 U S NUCLEAR REGULATORY 03 24 87 TO THE ORDER OF CDMMISSION l CHECK $ OVER Isiset REQUIRE COUNTERSIGNATURE l 1717 H ST NW WASHINGTON DC gqA , " ;;.,g. g
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THIS CHECK 20555 h*a ta 4 a :
VOID AFTER h '$,\iihlh5}thMvirdu f AufMOAtZ13 $4NAlUAE 90 DAYS .
co attas*aaruas n'2L97SE2n* l'OB L 50 24 59t* 84 035 & n' L.
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