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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp ML20137B9371997-03-18018 March 1997 Proposed Tech Specs,Revising TS Section 5.3.1,fuel Assemblies to Allow Use of Alternate Zr-based Fuel Cladding Matl ZIRLO ML20137B9141997-03-18018 March 1997 Proposed Tech Specs,Revising TS SR 4.5.2.c to Clarify When Containment Entry Visual Insp Is Required ML20134Q0811997-02-17017 February 1997 Proposed Tech Specs,Revising TS 1.7, Containment Integrity, TS 3/4.6.1, Containment Integrity & TS 3/4.6.3, Containment Isolation Valves 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20207J9621998-12-18018 December 1998 Rev 1 to TRM for Wolf Creek Generating Station,Unit 1 ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20195E7671998-11-10010 November 1998 Rev 0 to EPP 01-2.4, Core Damage Assessment Guidance ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20138F3371997-04-30030 April 1997 Rev 0 to Offsite Dose Calculation Manual ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp 1999-09-02
[Table view] |
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. ,7 l-I L At 'tachriient' III to WM 89-0264_ <
'( LPage;i: of 8~ .
f REFUELING OPERATIONS
-{
3/4.9.8 RESIOUAL HEAT REl10 VAL AND COOLANT CIRCULATION HIGH WATER LEVEL g
LIMITING CONDITION FOR OPERATION i
y.
3.9.8.1 At least one residual heat removal (RHR) loop shall be OPERABLE and
- in operation.*
1 APPLICABILITY: MODE 6 when the water level above the top of the reactor vessel flange is greater than or equal to'23 feet.
t ACTION:
With no RHR loop OPERABLE and in operation, suspend all- operations involving an increase in the reactor decay heat load or' a reduction in boron concentra-tion of the Reactor Coolant System and immediately initiate corrective action tg return the required RHR loop to OPERABLE and operating status as soon as possible.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours.
-(,
SURVEILLANCE REQUIREMENTS 4.9.8.1 At leest one R: R loop sh-li bc verified ir Operation cM circukting rcactcr cocisr.t et e fle.i retc of grcatcr then er cqual to 2000 ;;a at leest l' ence per 12~ hours.
At least once per twelve hours, one RHR loop shall be verified in operation and circulating coolant at a flow rate of:
a) greater than or equal to 1000gpm, and
-l b) sufficient to maintain the RCS temperature at less than or equal to 140"F "The RHR loop may be removed f rom operat ion for up to I hour p -hour period curing the. performance of CORE At 11 RAll0HS in t he vic ini t ; c. ..a c t v vessel not legs.
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!~. . l Page Attachment 2 of 8- 111 to WMl89-0264 , -
e A
3 REFUELING OPERATIONS
, LOW WATER LEVEL
-t LIMITING CONDITION FOR OPERATION ll 3.9.8.2 ..
and at k. Two independent residual heat removal (RHR) loops shall be OPERABLE, east one RHR loop shall be in operation."
APPLICABILITY:
MODE 6 when the water level above the top of the reactor vessel flange is less than 23 feet, i
ACT. ION:
a.
With less than the required RHR loops OPERABLE, immediately initiate
- corrective action to return the required RHR loops to OPERABLE status, or to establish greater than or equal to 23 feet of water L above the reactor vessel flange, as soon as possible.
b.
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
direct access from the containment atmosphere to the outsideClose (
atmosphere within 4 hours.
SURVEILLANCE REQUIREMENTS 4.9.8.2 rec ter cochnt St ic=tatone M4eop a ficw rat shel' be scrified-4n-opeeation cnd c4wk: ting cacs par 12 h0ers. cf grcetar than er equal tc 2000 ga st leest At,least once per twelve hours, one RHR loop shall be verified in operation and circulating coolant at a flow rate of :
a). greater -than or equal to 1000 gpm, and b) 7 7 7
- sufficient h to maintain the RCS temperature at less than or equal to 140 r -
,,rior to initial criticality, the RHR loop may be removed f rom x.: ation for uo to.1 hour per 2-hour period during the performance of CORE M.TUU!O: 15 in
*ne vicinity of the reactor vessel hot legs.
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" UAttachment IIItto WM 89-0264 4 -Page 3 of_8
{ REACTOR COOLANT SYSTEM
(-
COLD SHUTDOWN -~ LOOPS NOT FILLED -
U LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE # and at least one RHR loop shall be in operation.*
APPLICABILITY: MODE 5 with Reactor Coolant loops not filled.
ACTION:
a.
With less than the~above required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible, b.
With no RHR loop in operation, suspend all operations involving a i reduction in boron concentration of the Rdactor Coolant System and '
immediately initiate corrective action to return the required RHR loop to operation.
. SURVEILLANCE REQUIREMENTS
'(
d 4.4.1.4.2 At least one RHR loop shall be determined to be in operation and d
circulating reactor coolant at least once per 12 hours, i
#0ne RHR loop may be inoperable for up to 2 hours for surveillance testing
-provided the other RHR loop is OPERABLE and in operation.
*The RHR pump may be deenergized for up to 1 hour provided: (1) no operations 1 are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2)-core outlet temperature is maintained at least 10 F l below saturation temperature w~~
and (3) vessel the reactor flange. vessel water levelj is above the ,
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l' WOLI CREEP UNil 1 3/4 4-6 l .
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s, E . ,19ttpchinent 111 to-WM 89-0264 ,
f 'l p .-
Page;4Lof,8 -
f EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 ECCS SUBSYSTEMS - T < 200'F avo
_LINITING CONDITION FOR OPERATION 3.5.4 All Safety Infection pumps shall be inoperable.
APPLICABILITY: NO{ 0 end M000 0 with the reecter vessel head car i ACTION:
3 ,.
i I
With a Safety Injection pump OPERABLE, restore all Safety Injection pumps to an inoperable status within 4 hours.
SURVEILLANCE REQUIREMENTS 4.5.4 All Safety Injection pumps shall be demonstrated inoperable
(.
verifying that the motor circuit breakers are secured in the open position I
at least once per 31 days.
h '
9 the top of the Reactor Vessel flange, and
-MODE 6 with the Reactor Vessel head on and with the water level above the. top of the Reactor Vessel flange.
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*An inoperable purnp may be energized ior testinq or ior fil1in: crumulator, provid"d the disch,irge at Llui pump h.U. he"o isolated from t h.- by a i l o ,.
- ,olation valve with power removed f r om tin- v.t i ve ope ra ti: .i 6 :.inu a !
1,olat, son valve *otored in t f u c lusori po , i t io i b'Ol I CPIl K Util i l 1/ /; *, y
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. - .NtachmentIIItoWM 89-0264 , -
Page 5 of 8 '
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
----T imitation for a maximum of one centrifugal charging pump to b -
and the Survei. nt to verify all chargin ety Injec-tion pumps except the require '
o be inoperable in MODES 4 and 5 and in MODE 6 with tha -__. vessel inwvi
~
ssurance that a mass a'ddit m.; y.e~TrEstent can be relieved by the opera HR suction relief valve.
INSERT A ,
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITf is maintained. Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration,
, (2) rirovide the proper flow split between injection points in accordance with l
the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable I level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. The Surveillance Requirements for leakage testing of ECCS check valves ensures that a failure of one valve will not cause an intersystem LOCA. The Surveillance Requiren.ents to vent the ECCS pump casings ,
,a and , accessible, i.e.i can be reached without personnel hazard or high radiation f dose, discharge piping ensures against inoperable pumps caused by gas binding (
e or water hammer in ECCS piping.
1 .
3/4.5.S REFUELING WATER STORAGE TANK The OP$RABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits. on RWST minimum volume and boron concentration ensure that: (1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes assuming all the control rods are out of the core. These assumptions l are consistent with the LOCA analyses.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment af ter a LOCA. This pH band minimizes the evolution of iodine and minimizes the ef fect of chloride and caustic stress corrosion on mechanica l systems and components.
W>ll CRf:K UN!! l B 1/4 5 ? , w.t E
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... Attachment III to WM 89-0264 Mr,. Page 6 Of 8 ;
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1 INSERT A l-l The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirements to verify all charging pumps except the !
! required OPERABLE charging pump to be inoperable in MODES 4 and 5 and in i
MODE 6 with the reactor vessel head on, provides assurance that a mess addition pressure transient can be relieved by the operation of a single PORV or,RHR suction relief valve. In addition, the requirement to verify all Safety Injection pumps to be inoperable in MODE 4 in MODE 5 with the water level above the top of the reactor vessel flange, and in MODE 6 with the reactor vessel head on and with water level above the top of the reactor vessel flange, provides assurance that the mass addition can be relieved by a single PORV or RHR suction relief valve.
With the water level not above the top of the reactor vessel flange and with' the vessel head on, Safety Injection pumps may be available to mitigate the '
affects of a loss of decay heat removal during a reduced RCS intentory condition. 1 l
l L
MAttachment Ill to WM 89-0264
, .-* e Rage 7 of 8 '
, REFUELING OPERATIONS BASES
,- (,
3 /4. 9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine and auxiliary hoist ensure that: (1) manipulator cranes will be used for uovement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations. '
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool areas ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a r, ingle fuel assembly, and (2) any possible distortion of fuel in the storage racks will.not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that: (1) sufficient cooling capacity is available to remove I decay heat and maintain the water in the reactor vessel below 140'F as required during the FJ. FUELING MODE, and (2) sufficient coolant circulation is maintained through the core,ta minimize the.cL( of a boron dilution incident and prevent boron stratification.- INSERT B The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of RHR capability.
With the reactor vessel head removed and at least 23 feet of water above the J reactor vessel flange, a large heat sink is available for core cooling. Thus, L in the event of a f ailure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
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3/4. 9. 9 CONTAINMENT VENTILAT10N' SYSTEM The OPERABILITY of this system ensures that the containment Durge penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABilllY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
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.AttachmentIIItoWM 89-0264 , ,
_ Page C-7 8 -
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