NSD-NRC-97-5236, Forwards Ssar Section of short-term Availability Controls for Listed Systems/Functions Under Specified Conditions of Operations

Forwards Ssar Section of short-term Availability Controls for Listed Systems/Functions Under Specified Conditions of Operations

ML20141H126
Person / Time
Site:	05200003
Issue date:	07/16/1997
From:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Slosson M NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NSD-NRC-97-5236, NUDOCS 9707220016
Download: ML20141H126 (50)

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Westinghouse Energy Systems Ba 355 - ,

Pmsbur@ Pennsylvania 15230-0355 Electric Corporation ,

DCP/NRC0957 NSD-NRC-97-5236 Docket No.: 52-003 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Attention: M. M. Slosson

Subject:

AP600 SHORT TERM AVAILIBILITY CONTROLS

References:

} 1. NRC letter, Marylee Slosson to Nicholas Liparulo, Regtuatory Treatment of Nonsafety Related Systems, dated June 9,1997

2. NRC letter, Marylee Slosson to Nicholas Liparulo, AP600 Design Changes j to Address Post-72 Hour Actions, dated June 5,1997 l l

Dear Ms. Slosson:

i The importance of AP600 nonsafety related systems, structures and components has been systematically evaluated as a part of the process agreed to between the Industry and the NRC and approved by the Commission in SECY-94-084, as a part of expediting the staff's review of issues related to the focused probabilistic risk assessment and thermal-hydraulic uncertainties as described in reference 1 and as a part of the resolution of the post-72 hour actions key AP600 licensing issue as described in Reference 2. The attachment presents an SSAR section of short-term availability controls for the following systems / functions under specified conditions of operation:

Diverse actuation Normal residual heat removal Component cooling water 1 Service water Passive containment cooling Main control room cooling l&C room cooling Hydrogen igniters AC power supplies DC power supplies k _

9707220016 970716 PDR ADOCK 05200003.

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. As presented during the May 6,1997 NRC meeting with NRC management, these availability controls are in a format similar to technical specifications to aid in communicating with plant operations personnel.

As committed during the May 6,1997 meeting with NRC management, these short-term availability controls will be included in Revision 15 to the AP600 SSAR.

This submittal closes from a Westinghouse perspective the following open items:

Key Issue 2f 224 t 233 503 945 1090 2024

• 2300 2454 ,

4985 4986 4988 4989 The NRC should inform Westinghouse of the status to be designated in the "NRC Status" field of OITS. We suggest either " Resolved" or " Closed".

Please do not hesitate to contact me if you have any questions conceming this information.

hhBrian A McIntyre, a er Advanced Plant Safety and Licensing cc: T. R. Quay - NRC/NRR/DRPM N. J. Liparulo - Westinghouse 1

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ATTACHMENT TO NSD-NRC-97-5236 (DCP/NRC0957) ,

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,- 16. Technical Specifications I

l 16.3 Investment Protection 16.3.1 Investment Protection Short-Term Availability Controls )

The importance of nonsafety-related systems, stmetures and components in the AP600 has been evaluated. The evaluation uses PRA insights to identify systems, structures and components that are important in protecting the utilities investment and for preventing severe accidents. To provide reasonable assurance that these systems, structures and components are operable during anticipated events shon-tenn availability controls are provided. These investment protection systems, structures and components are also included in the D-RAP /

O-RAP (refer to table 16.2-1), which provides confidence that availability is designed into the plant and that availability is maintained throughout plant life. Technical Specifications are ,

not required for these systems, stmetures and components because they do not meet the l selection criteria applied to the AP600 (refer to !6.1.1).

Table 16.3-1 lists nonsafety-related systems, structures and components that have investment i protection short-tenn availability controls. This table also lists the number of trains that should be operable and the plant operating MODES when they should be operable. Table 16.3-2 contains the investment protection short-tenn availability controls. These shon-tenn availability controls define:

Equipment that should be operable  :

Operational MODES when the equipment should be operable Testing and inspections that should be used to demonstrate the equipment's operability Operational MODES that should be used for planned maintenance operations Remedial actions that should be taken if the equipment is not operable Tables 16.3-1 and 16.3-2 contain defined terms that appear in capitalized type. These tenns are defined below.

ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

CH ANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known input. The CHANNEL CALIBRATION shall encompass the entire chamiel, including the required sensor, alann, interhick, display, and trip functions. Calibration of instmment channels with resistance temperature detector (RTD) or themlocouple sensors may consist of an inplace qualitative assessment of sensor behavior and nonnal calibration of the remaining adjustable devices in the charuiel. Whenever a sensing element is replaced, the next required CHANNEL CALIBRATION shall include an inplace cross calibration that compares the other sensing elements with the recently installed sensing element. The CHANNEL Revision: Prel.

[ W85tiligh00Se .luly 11,1997 16.3-1

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16. Technical Specifications CALIBRATION may be perfonned by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. Titis determinatit-shall include, where possible, comparison of the channel indication and  ;

status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or TEST (COT) actual TEST signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alann, interlock, display, and trip functions.

The COT shall include adjustment as necessary, of the required alann, interh>ck, and trip setpoints so that the setpoints are within the required range and accuracy.

MODE A MODE shall corTespond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified below with fuel in the reactor vessel.

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Resision: Prel.  ;

.luly 11,1997 Westilighouse i

16.3-2

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16. Technical Specifications MODES AVERAGE

% RATED REACTOR REACTIVITY THERMAL COOLANT MODES TITLE CONDITION POWER (a) TEMPERATURE

( K,,,) ( F) 1 Power Operation 2 0.99 >5 NA 2 Startup 2 0.99 s5 NA 3 Hot Standby < 0.99 NA > 420 4 Safe Shutdown (b) < 0.99 NA 420 2 T.,, > 200 5 Cold Shutdown (b) < 0.99 NA s 200 6 Refueling (c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

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Revision: Prei.

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I 16. Technical Specifications 1

I OPERABLE-OPERABILITY A system, subsystem, train, component, or device is OPERABLE or has l OPERABILITY when it is capable of perfonning its specified safety function (s) and when all necessary attendant instrumentation, controls. l nonnal or emergency electrical power, cooling and seal water, l lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perfonn its specified safety function (s) are also capable of performing their related support I function (s). l 16.3.2 Combined License Information Combined License applicants referencing the AP600 design will develop a procedures to control the operability of investment protection systems, structures and components in accordance with Table 16.3-2.

Revision: Prel.

.luly 11,1997 Westirighouse 16.3-4

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16. Technical Specifications Table 16.3-1 LIST OF INVESTMENT PROTECTION SIIORT-TERM AVAILAllILITY CONTROLS Systems, Structures, Components Number MODES Trains (a) Operation (b) 1.0 Instmmentation Systems l.1 DAS ATWS Mitigation 2 1 1.2 DAS ESF Actuation 2 1,2,3,4.5,6 (3) 2.0 Plant Systems 2.1 RNS 1 1,2,3 2.2 RNS - Reduced Inventory 2 5,6 (2,3) 2.3 CCS - Reduced Inventory 2 5,6 (2,3) 2.4 SWS - Reduced Inventory 2 5,6(2,3) 2.5 PCS Water Makeup - Long Tenn Shutdown 1 1,2,3,4,5,6 (4) 2.6 MCR Cooling - Long Temi Shutdown i 1.2.3,4,5,6 2.7 l&C Room Cooling - Long Tenn Shutdown 1 1.2.3.4.5,6 2.S Hydrogen Ignitors 1 1,2,5,6(2,3) 3.0 Electrical Power Systems 3.1 AC Power Supplies 1 1,2,3,4,5 -

3.2 AC Power Supplies - Reduced Inventory (1) 5,6 (2,3) 3.3 AC Power Supplies - Long Temi Shutdown i 1.2.3,4,5,6 )

3.4 DC Power Supplies - DAS 2 1.2.3,4,5,6(3) l l

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l Alpha Notes:

(a) Refers to the number of trains covered by the availability controls.

(b) Refers to the MODES of plant operation where the availability controls apply.

Notes:

(1) 2 of 3 AC power supplies (2 standby diesel generators and I offsite power supply).

(2) MODE 5 with RCS open and levd not visible in pressurizer.

(3) MODE 6 with upper intemals ir. place and cavity level less than full.

(4) MODES 5 and 6 with the c:dcolated core decay heat greater than 6 MWt.

Revision: Prel.

W Westinghouse .luly 11,1997 16.3-5

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- l TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 1.0 Instrumentation Systems 1.1 Diverse Actuation System (DAS) ATWS Mit!gation J OPERABILITY: DAS ATWS mitigation function listed in Table 1.1-1 should be operable APPLICABILITY: MODE 1 i

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DAS ATWS Function A.! Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l with one or more required [on-call alternate].

charuiels inoperable; AND A.2 Restore required channels to 14 days operable status.  ;

B. Required Action and B.1 Submit report to [ chief nuclear i day associated Completion officer] or [on-call attemate]

Time of Condition A not detailing interim compensatory met, measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND B.2 Document the justification for the I month actions taken and input provided to 0-RAP in plant records.

Revision: Prel. 3 Westinghouse

.luly 11,1997 16,3-6

TABLE 16.3-2 t

INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS

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SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 1.1.1 Perfonn CHANNEL CHECK on each required channel. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> SR 1.1.2 Perfonn CHANNEL OPERATIONAL TEST on each 92 days required channel.

SR 1.1.3 Perfonn CHANNEL CALIBRATION on each required 24 months channel.

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. Table 1.1 1, DAS ATWS Functions 1

l DAS Initiating Number Channels Setpoint )

Function Signal Installed Required Rod Drive MG SG Wide 2 per SG 1 per SG > [25,000 lb]

Set Trip, Turbine Range Level i

Trip and PRHR HX Actuation x

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, .luly 11,1997 16.3-7

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. INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 1.0 lustrumentation Systems 1.1_ DAS ATWS Mitigation BASES:

The DAS ATWS mitigation function of reactor trip, turbine trip and passive residual heat removal heat exchanger (PRHR HX) actuation should be available to provide ATWS mitigation capability.

This function is imponant based on 10 CFR 50.62 (ATWS Rule) and because it provides margin in the PRA sensitivity perfonned assuming no credit for nonsafety-related SSCs to mitigate at-power and .

shutdown events. ' The margin provided in the PRA study assumes a minimum availability of 75% for this function.

The DAS uses a 2 out of 2 logic to actuate automatic functions. When a required channel is unavailable the automatic DAS function is unavailable. SSAR section 7.7.1.11 provides additional infonnation. The DAS channels listed in Table 1.1-1 should be available.

Automated operator aids may be used to facilitate perfonnance of the CHANNEL CHECK. An automated tester may be used to facilitate performance of the CHANNEL OPERATIONAL TEST.

The DAS ATWS mitigation function should be available during MODE 1 when ATWS is a limiting event. Plamied maintenance affecting this DAS function should be perfonned MODES 3,4. 5,6;-

these MODES are selected because the reactor is tripped in these MODES and ATWS can not occur.

l Revision: Prel. W85tingh00S8

.luly 11,1997 i

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TABLE 16.3 2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 1.0 Instrumentation Systems 1.2 DAS Engineering Safeguards Features Actuation (ESFA)

OPERABILITY: DAS ESFA functions listed in Table 1.2-1 should be operable APPLICABILITY: MODE 1, 2, 3, 4, 5.

MODE 6 with upper intemals in place and cavity level less than full ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

. A. DAS ESFA Functions A.1 Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with one or more required [on-call attematel.

charuiels inoperable.

AND A.2 Restore required channels to 14 days operable status.

B. Required Action and B.I Submit report to [ chief nuclear Iday associated Completion ofncer] or [on-call altemate]

Time of Condition A not detailing interim compensatory m et. measures. cause for inoperability, and schedule for restoration to OPERABLE.

AND B.2 Document the justincation for the I month actions taken and input provided to 0-RAP in plant records.

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July 11,1997 i 16.3-9 l _

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I TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 1.2.1 Perfonn CHANNEL CHECK on each required 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> CHANNEL.

SR 1.2.2 Perfonn CHANNEL OPERATIONAL TEST on each 92 days

, required CHANNEL.

SR I.2.3 Perfonn CllANNEL CALIBRATION on each mquired 24 months CHANNEL.

l Table 1.2-1, DAS ESFA Functions l l

DAS Initiating Number Channels Setpoint Function Signal Installed Required PRHR HX SG Wide 2 per SG 1 per SG > [25,000 lbl

• Actuation Level or HL Temp i per HL 1 per HL < [620lF CMT Actuation Pzr Level 2 2 > [717c and RCP trip Passive Cont. Cont. Temp 2 2 < [200lF Cooling and Selected Cont.

Isolation Actuation Resision: Prel. W Westinghouse

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TABLE 163-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 1.0 Instrumentation Systems 1

1.2 DAS ESFA 1

BASES:

The DAS ESFA functions listed in Table 1.2-1 should be available to provide accident mitigation j capability. This function is important because it provides margin in the PRA sensitivity perfonned j assuming no credit for nonsafety-related SSCs to mitigate at-power and shutdown events. The margin provided in the PRA study assumes a minimum availability of 75% for this function.

The DAS uses a 2 out of 2 logic to actuate automatic functions. When a required channel is unavailable the automatic DAS function is unavailable. SSAR section 7.7.1.11 provides additional )

infonnation. The DAS channels listed in Table 1,21 should be available. l Automated operator aids may be used to facilitate performance of the CHANNEL CHECK. An  ;

automated tester may be used to facilitate perfonnance of the CHANNEL OPERATIONAL TEST.

The DAS ESFA mitigation functions should be available during MODES 1, 2, 3, 4, 5, 6 when accident mitigation is beneficial to the PRA results. The DAS ESFA should be available in. MODE 6 j with upper intemals in place and cavity level less than full. Planned maintenance affecting these DAS j functions should be perfonned in MODE 6 when the refueling cavity is full; this MODE is selected 1 because requiring DAS ESFA are not anticipated in this MODE.

I W W85tingh00S8 Revision: Prel.

July 11,1997 16.3-11

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TABLE 16.3-2 INVESTMENT PROTECTION SHORT. TERM AVAILABILITY CONTROLS 2.0 Plant Systems ,

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2.1 Nonnal Residual Heat Removal System (RNS)

OPERABILITY: One train of RNS injection should be operable APPLICABILITY: MODE 1, 2, 3 l

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One requireil train not A.1 Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> operable. [on-call attemate).

AND A.2 Restore one train to operable status 14 days B, Required Action and B.I. Submit report to (chief nuclear 1 day I associated Completion l officer] or [on-call attemate]

Time not met. detailing interim compensatory measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND

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B.2 Document the justification for the I month actions taken and input provided to 0-RAP in plant records.

Revision: Prel. W West lrighouse

.luly 11,1997 16.3 12

L . l TABLE 16.3-2  !

1 INVESTMENT PROTECTION SHORT-TERM AVAILAlllLITY CONTROLS l

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SURVEILLANCE FREQUENCY t

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-l l SR 1.1.1,1 Verify that one RNS pump develops a differential head of 92 days

[330] feet on recirculation 110w i

SR 1.1.1.2 Verify that the following valves stroke open 92 days RNS V011 RNS Discharge Cont. Isolation RNS V022 RNS Suction Header Cont. Isolation RNS V023 RNS Suction from IRWST Isolation I

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July 11,1997 16.3-13

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TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems 2.1 RNS BASES:

The RNS injection function provides a nonsafety< elated means of injecting IRWST water into the RCS following ADS actuations. The RNS injection function is important because it provides margin in the PRA sensitivity perfonned assuming no credit for nonsafety-related SSCs to mitigate at-power and shutdown events. The margin provided in the PRA study assumes a minimum availability of 75'7e for this function.

One train of RNS injection includes one RNS pump and the line from the IRWST to the RCS. Three of the valves in the line between the IRWST and the RCS are normally closed and need to be opened to allow injection. This equipment does not nonnally operate during MODES 1,2,3. Refer to SSAR section 5.4.7 for additional infonnation on the RNS.

The RNS injection function should be available during MODES 1,2,3 because decay heat is higher and the need for ADS is greater.

Plarmed maintenance on redundant RNS SSCs should be performed during MODES 1,2,3. Such maintenance should be perfonned on an RNS SSC not required to be available. The bases for this recommendation is that the RNS is more risk important during shutdown MODES when it is nonnally operating than during other MODES when it only provides a backup to PXS injection.

Planned maintenance on non-redundant RNS valves (such as V0ll, V022 V023) should be perfomied

, to minimize the impact on their RNS injection and their containment isolation capability. . Non-pressure boundary maintenance should be performed during MODE 5 with a visible pressurizer level or MODE 6 with the refueling cavity full. In these MODES, these valves need to be open but they do not need to.be able to close. Containment closure which is required in these MODES can be satisfied by one nonnally open operable valve. Pressure boundary maintenance can not be performed during MODES when the RNS is used to cool the core, therefore such maintenance should be performed during MODES 1,2,3. Since these valves are also contairunent isolation valves, maintenance that renders the valves inoperable requires that the containment isolation valve hicated in series with the inoperable valve has to closed and de-activated. The bases for this recommendation is that the RNS is more risk imponant during shutdown MODES when it is nonnally operating than during other MODES when it only provides a backup to PXS injection. In addition, it is not possible to perfonn pressure boundary maintenance of these valves during RNS operation.

Revision: Prel. W Westinghouse

. inly iI,1997 16.3-14 I

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l TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems 1

2.2 Nonnal Residual Heat Removal System (RNS) - Reduced Inventory OPERABILITY: Both RNS pumps should be operable for RCS cooling APPLICABILITY: _ MODE 5 with RCS open, level not visible in pressurizer, MODE 6 with upper intemals in place and cavity level less than full ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

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) A. . One pump no' op-rable. A.i Remove plant from applicable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

MODES i -- B. Required Action and B.I Submit report to [cidef nuclear iday 1 associated Completion officer] or [on-call attemate]

Time not met. detailing interim compensatory measures, cause for inoperability, 1

and schedule for restoration to i OPERABLE. ,

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B.2 Document the justification for the I month actions taken and input provided ,

j to 0-RAP in plant records. l 1

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July 11,1997

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. TABLE 16.3-2 INVESTMENT PROTECTION SHORT. TERM AVAILABILITY CONTROLS l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 2.2.1 Verify that one RNS pum,n is in operation and that each Within I day prior to RNS pump operating individually circulates reactor entering reduced coolant at a flow > [900] gpm inventory conditions OR

, Verify that both RNS pumps are in operation and circulating reactor coolant at a flow > [1800] gpm I

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Revision: Prel. { Westinghouse

.luly i1,1997 16 3-16

TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems 2.2 RNS - Reduced Inventory BASES:

1 The RNS cooling function provides a nonsafety-related means to nonnally cool the RCS dunng shutdown operations (MODES 4,5,6). 'ntis RNS cooling function is imponant during reduced RCS ,

inventory conditions because it reduces the probability of an initiating event due to loss of RNS I cooling and because it provides margin in the PRA sensitivity perfonned assuming no credit for 1 nonsafety-related SSCs to mitigate at-power and shutdown events. The margin provided in the PRA '

study assumes a minimum availability of 75% for this function.

The RNS cooling of the RCS involves the RNS suction line from the RCS HL, the two RNS pumps and the RNS discharge line retuming to the RCS through the DVI lines. The valves located in these lines should be open prior to the plant entering reduced inventory conditions. One of the RNS pumps has to be operating; the other pump may be operating or may be in standby. Standby includes the capability of being able to be placed into operation from the main control room. Refer to SSAR section 5.4.7 for additional information on the RNS.

Both RNS pumps should be available during MODES 5 and 6 with reduced RCS inventory when the loss of RNS cooling is risk imponant. If both RNS pumps are not available, the plant should not enter reduced inventory conditions. If the plant has entered reduced inventory conditions, then the plant should take action to restore full system operation.

. Planned maintenance affecting this RNS cooling function should be performed in MODES 1,2,3 when the RNS is not nonnally operating. The bases for this recommendation is that the RNS is more risk important during shutdown MODES, especially during reduced RCS inventory conditions than during other MODES when it only provides a backup to PXS injection.

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July 11,1997 t

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TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS

. 2.0 Plant Systems

' 2.3 ' Component Cooling Water System (CCS) - Reduced Inventory OPERABILITY: Both CCS pumps should be operable for RNS cooling APPLICABILITY: MODE 5 with RCS open, level not visible in pressurizer, MODE 6 with upper intemals in place and cavity level less than full ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump not operable. A.1 Remove plant from applicable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> MODES B. Required Action and B.1 Submit report to [ chief nuclear i day associated Cotapletion officer] or [on-call altemate]

Time not met. detailing interim compensatory measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND B.2 Document the justification for the 1 month actions taken and input provided to 0-RAP in plant records.

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l Revision: Prel. W" Westinghouse .

.luly 11,1997 16.3-18

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, INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 4

i-l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR ' 2.3.1 Verify that one CCS pump is in operation'and each CCS Within i day prior to pump operating individually provides a CCS flow through entering reduced one RNS heat exchanger > [2520] gpm inventory conditions -

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j OR l Verify that both CCS pumps are in operation and the CCS flow through cabh RNS heat exchanger is > [2520] gpm j l

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i T Westinghouse Revision: Prel, July 11,1997 16.3 19

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l TABLE 16.3-2 l

INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS l

1 2.0 Plant Systems I 2.3 CCS - Reduced Inventory  ;

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l BASES:

The CCS cooling of the RNS HXs provides a nonsafety-related means to nonnally cool the RCS during shutdown operations (MODES 4,5,6). Tids RNS cooling function is important because it' reduces the probability of an initiating event due to loss of RNS cooling and because it provides

, margin in the PRA sensitivity perfonned assuming no credit for nonsafety-related SSCs to mitigate at-power and shutdown events. The margin provided in the PRA study assumes a minimum availability ,

of 75M for this function.  !

l The CCS cooling of the RNS involves two CCS pumps and HXs and the CCS line to the RNS HXs.

The valves around the CCS pumps and HXs and in the lines to the RNS HXs should be open prior to the plant entering reduced inventory conditions. One of the CCS pumps and its HX has to be operating. One of the lines to a RNS HX also has to be open. The other CCS pump and HX may be ,

operating or may be in standby. Standby includes the capability of being able to be placed into I operation from the main control room. Refer to SSAR section 9.2.2 for additional infomiation on the CCS.

Both CCS pumps should be available during MODES 5 and 6 with reduced RCS inventory when the  !

loss of RNS cooling is risk important. If both CCS pumps are not available, the plant should not ,

enter reduced inventory conditions, if the plant has entered reduced inventory conditions, then the I plant should take action to restore both CCS pumps or to leave reduced inventory conditions. l l

Plamled maintenance affecting this CCS cooling function should be perfonned in MODES 1,2,3 j when the CCS is not supporting RNS operation. The bases for this recommendation is that the CCS is more risk imponant during shutdown MODES, especially during reduced RCS inventory conditions than during other MODES.

l Revision: Prel. W Westingh00S8

.luly 11,1997 16.3-20

TABLE 16.3 2 INVESTMENT PROTECTION SHORT-TERM AVAILAHILITY CONTROLS 2.0 Plant Systems -

2.4 Service Water System (SWS) - Reduced Inventory

- OPERABILITY: Both SWS pumps and cooling tower fans should be operable for CCS cooling APPLICABILITY: MODE 5 with RCS open, level not visible in pressurizer, MODE 6 with upper intemals in place and cavity level less than full ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump or fan not A.1 Remove plant from applicable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> operable. MODES B. Required Action and B.I Submit report to [ chief nuclear I day associated Completion officer] or [on-call attemate)

Time not met, detailing interim compensatory measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND B.2 Document the justification for the i month actions taken and input provided to 0-RAP in plant records.

i i

I l

l l

l l  %, Westirighouse Revision: Prel.

July 11,1997 16.3-21

l '

I -

TABLE 16.3-2 I INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS SURVEILLANCE REQUIREMENTS i

SURVEILLANCE FREQUENCY SR 2.4.1 Verify that one SWS pump is operating and that each Within i day prior to SWS pump operating individually provides a SWS tiow entering reduced i

> [6200] gpm inventory conditions i

SR 2.4.2 Operate each cooling tower fan for > 15 min Within I day prior to entering reduced inventory conditions

==:::.-

4 4

e Revision: l'rel. T Westinghouse l .luly 11,1997 16.3-22

• l l

I TABLE 16.3-2 I

INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 1

2.0 Plant Systems t i 2.4 SWS - Reduced Inventory BASES: I l

l De SWS cooling of the CCS HXs provides a nonsafety-related means to nonnally cool the RNS HX l which cool the RCS during shutdown operations (MODES 4,5,6). This RNS cooling function is I important because it reduces the probability of an initiating event due to loss of RNS cooling and because it provides margin in the PRA sensitivity perfonned assuming no credit for nonsafety-related SSCs to mitigate at-power and shutdown events. The margin provided in the PRA study assumes a minimum availability of 75% for this function.

l The SWS cooling of the CCS HXs involves two SWS pumps and cooling tower fans and the SWS line to the RNS HXs. The valves in the SWS lines should be open prior to the plant entering reduced inventory conditions. One of the SWS pumps and its cooling tower fan has to be operating. The other SWS pump and cooling tower fan may be operating or may be in standby. Standby includes the capability of being able to be placed into operation from the main control room. Refer to SSAR section 9.2.1 for additional infonnation on the CCS.

Both SWS pumps and cooling tower fans should be available during MODES 5 and 6 with reduced RCS inventory when the loss of RNS cooling is risk important. If both SWS pumps and cooling tower fans are not available, the plant should not enter reduced inventory conditions. If the plant has entered reduced inventory conditions, then the plant should take action to restore both SWS pumps /

fans or to leave reduced inventory conditions.

Phuuied maintenance affecting this SWS cooling function should be performed in MODES when the

' SWS is not supporting RNS operation,ie during MODES 1,2,3. The bases for this recommendation is that the SWS is more risk important during shutdown MODES, especially during reduced RCS l inventory conditions than during other MODES.

l i

W Westinghouse Revision: Prel.

.luly 11.1997 16.3-23 l

., . -. .._ . - - . - - - - - ~ . . - _ - .

TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems j l

2.5 Passive Containment System Water Storage Tank (PCCWST) Makeup - Long Tenn Shutdown i i

OPERABILITY: Long tenn makeup to the PCCWST should be operable l APPLICABILITY: MODES 1. 2, 3,4, MODES S and 6 with calculated core decay heat > 6 MWt.

ACTIONS i

CONDITION' REQUIRED ACTION COMPLETION TIME l

i A. Water volume in PCS A.1 Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ancillary tank less than [on-call altemate).

limit. ,

AND I A.2 Restore volume to within limits 14 days l l

l B. One required PCS B.I Notify [ chief nuclear officer) or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i recirculation pump not [on-call attemate).

l operable.

AND B.2 Restore pump to operable status 14 days h

l l

I r

. Revision: Prel. W Westinghouse i

.luly 11,1997 16.3-24

?

TABLE 16.3-2

( INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS l

Q' C. Required Action and C.! Submit report to [ chief nuclear i day

? associated Completion officer] or [on-call attemate]

Time of Condition A, B detailing interim compensatory not met. measures, cause for inoperability, and schedule for n:storation to OPERABLE.

1 AND l l

C.2 Document the justification for the 1 month actions taken and input provided I to 0-RAP in plant records. I I

l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

SR 2.5.1 Verify water volume in the PCS ancillary tank is 31 days i

> [362,000] gal.

SR 2.5.2 Record that the required PCS recirculation pump provides 92 days -

recirculation of the PCCWST at > [621 gpm.

SR 2.5.3 Verify that each PCS recirculation pump transfers 10 years j

> [62] gpm from the PCS ancillary tank to the PCCWST. ]

During this test, each PCS recirculation pump will be -!

powered from a ancillary diesel.

i W Westingh00$8 Revision: Prel.

.luly 11,1997 16.3-25

l TABLE 16.3 2 i

INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems 2.5 PCCWST Makeup - Long Tenn Shutdown 1

BASES: I The PCS recirculation pumps provide long tenn shutdown support by transferring water from the PCS ancillary tank to the PCCWST. This water is used to maintain PCS cooling during the 3 to 7 day i time period following an accident. After 7 days water brought in from offsite allows the PCCWST to l continue to provide PCS cooling and also to provide makeup to the spent fuel pit. .This PCCWST makeup function is important because it supports long-tenn shutdown operation.-

The PCCWST makeup function involves the use of one PCS recirculation pump, the PCS ancillary tank and the line connecting the PCS ancillary tank with the PCCWST. One PCS recirculation pump nonnally operates to recirculate the PCCWST. Refer to SSAR section 6.2.2 for additional infonnation on the PCCWST makeup function. j i

l The PCCWST makeup function should be available during MODES of operation when PCS cooling is )

required; one PCS recirculation pump and PCS ancillary tank should be available during MODES  !

l_ 1,2,3,4, and MODES 5 and 6 with calculated core decay heat > 6 MWt. The PCS is required to be l available during these MODES: it is not required to be available in MODE 5 or 6 with calculated core l decay heat < 6 MWt.

I i Planned maintenance affecting the required PCCWST recirculation pump should not be perfonned during required MODES; planned maintenance should be performed on the redundant pump (ie the l pump not required to be available). Planned maintenance affecting the PCS ancillary tank that l requires less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to perform can be perfonned in any MODE of operation. Planned maintenance requiring more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> should be performed in MODES S or 6 when the calculated core decay heat is < 6 MWt. The bases for this recommendation is that the long-tenn PCS makeup is not required in this condition.

I I

i.

).

! Revision: Prel.

' 3 Westinghouse

.luly 11,1997 16.3-26 4

. . . . .. ~ . ~ .

)

TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS i l

2.0 Plant Systems 2.6 Main Control Room (MCR) Cooling - Long Term Shutdown OPERABILITY: Long tenn cooling of the MCR should be operable I APPLICABILITY: MODES 1, 2, 3, 4, 5. 6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i

A. One required MCR A.1 Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ancillary fans not [on-call attemate].

operable.

AND A.2 Restore one fan to operable status 14 days B. Required Action and B.I Submit report to [ chief nuclear iday associated Completion officerl or [on-call attemate]

Time not met. detailing interim compensatory measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND  ;

B.2 Document the justification for the i month actions taken and input provided to 0-RAP in plant records.

i W WeStingh00S8 Revision: Prel. j July 11,1997 i 16.3 27

. .--- .- - . ~ . - . . . . . - . _ . - - _ _ - - - . . - - . .- _-

l I *

• I i TABLE 16.3-2 ,

i INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS I l

' I I

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l l

SR 2.6.1 Operate required MCR ancillary fan for > 15 min 92 days  ;

l )

SR 2.6.2 Verify that each MCR ancillary fan can provide a flow of 10 years air into the MCR for >l5 min. During this test, the MCR ancillary fans will be powered from the ancillary diesels. . l 1

1 1

l Revision: Prel. W W85tingh00S8

.luly 11,1997 16.3-28

I TABLE 16.3-2 l .

i INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS l l

2.0 Plant Systems 2.6 MCR Cooling - Long Temi Shutdown BASES:

l The MCR ancillary fans provide long term shutdown support by cooling the main control itxim. For  ;

the first three days after an accident the emergency HVAC system (VES) together with the passive i heat sinks in the MCR provide cooling of the MCR. After 3 days, the MCR ancillary fans can be used to circulate ambient air through the MCR to provide cooling. The long tenn MCR cooling  !

function should be available during all MODES of operation. This long temi MCR cooling function is important because it supports long-tenn shutdown operation.

.The long temi MCR cooling function involves the use of a MCR ancillary fan. During SR 2.6.1 the fan will be mn to verify that it operates without providing flow to the MCR. During SR 2.6.2 each fan will be connected to the MCR and operated such that they provide flow to the MCR. Refer to SSAR section 9.4.1 for additional infonnation on the long term MCR cooling function.

One MCR ancillary fan should be available during all MODES of plant operation. Planned maintenance should not be perfonned on the required MCR ancillary fan during a required MODE of operation; planned maintenance should be performed on the redundant MCR ancillary fan (ie the fan l not required to be available) during MODES 3 or 4, MODE 5 with a visible pressurizer level or MODE 6 with the refueling cavity full; these MODES are selected because the reactor is tripped in these MODES and the risk of core damage / hydrogen generation is low.

I f

W WeStingh0US8 Revision: Prel.

July 11,1997 l 16.3-29 l

. . . . . . . - - . . .. . ~ . . - _ . - - - . . . - - . . - - - . _ , . ,

I TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems 2.7 I&C Room Cooling - Long Tenn Shutdown OPERABILITY: Long tenu cooling of I&C rooms B & C should be operable APPLICABILITY: MODES 1, 2, 3, 4, 5, 6 i

, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME j A. One required I&C room A.1 Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

ancillary fan not operable. (on-call altematel.

I-l AND A.2 Restore one fan to operable status 14 days l

B. Required Action and B.! Submit report to [ chief nuclear i day i associated Completion officer] or [on-call attemate]

! Time not met, detailing interim compensatory j

measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND B.2 Document the justification for the 1 month

[ actions taken and input provided to 0-RAP in plant records.

I L

i i

l 4

Revision: Prel. W Westinghouse i ~

.luly 11,1997 16.3-30 4

i l -

TABLE 16.:i-2 i

INVESTMENT l'ROTECTION SHORT-TERM AVAIL.AHILITY CONTROLS l

t i I

SURVEILLANCE REQUIREMENTS  ;

I SURVEILLANCE FREQUENCY .

l SR 2.7.1 Operate required !&C room ancillary fan for > 15 min 92 days l

SR 2.7.2 Verify that each 1&C room ancillary fan can provide a 10 years J

, llow of air into an l&C room for >l5 min. During this  !

test, the I&C room ancillary fans will be powered from an j l

ancillary diesel.

l l

l l

l l

I f

(

l i

k W W85tifigh00S8 REVISI"" I'FCI-

! .luly 11,1997 16.,3-31

I TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 2.0 Plant Systems 2.7 I&C Room Cooling - Long Tenn Shutdown BASES:

Tie I&C nxim ancillary fans provide long tenn shutdown support by cooling I&C rooms B & C j which contain post accident instrument processing equipment. For the first three days after an accidem the passive heat sinks in the I&C rooms provide cooling. After 3 days, the I&C room ancillary fans can be used to circulate ambient air through the I&C room to provide cooling. The  :

long tenn I&C room cooling function should be available during all MODES of operation. 'This long l tenu I&C room cooling function is important because it supports long-tenn shutdown operation.

The long tenn I&C room cooling function involves the use of two I&C room ancillary fans; each fan is associated with one I&C room (B or C). During SR 2.6.1 the required fan will be run to verify that it operates without providing flow to the I&C room. During SR 2.6.2 each fan will be connected to its associated I&C room and operated such that flow is provided to the I&C room. Refer to SSAR j section 9.4.1 for additional information on the long term I&C room cooling function.

One I&C room ancillary fan should be available during all MODES of plant operation. Planned maintenance should not be perfomied on the required I&C room ancillary fan during a required MODE of operation; plasmed maintenance should be perf<mned on the redundant I&C room ancillary fan.

Revision: Prel. W*

Westinghouse

.luly 11.1997 16.3-32

. .- . . - - -- . . . ~ . . - - - . . - - . - . - - . . . , . - . - . - - . -. - - .-

',- TABLE 16.3-2 5 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS u

2.0 Plant Systems I 8 Hydrogen Ignitors

j. ' OPERABILITY.: The hydrogen ignitors listed in Table 2.8-1 should be operable

- APPLICABILITY: MODE 1,2, 3 MODE $_ with RCS open, level not visible in pmssurizer,

MODE 6 with upper intemals in place and cavity level less than full ACTIONS .

CONDITION - REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l1 hydrogen Ignitor [on-call altematel, inoperable.

AND A.2 Restore required ignitors to 14 days operable status.

B. Required Action and B.1 Submit report to [ chief nuclear i day associated Completion officerl or [on-call alternate)

Time of Condition A not detailing interim' compensatory m et. measures, cause for inoperability, and schedule for restoration to  !

OPERABLE.

AND l

B.2 Document the justification for the 1 month  ;

I actions taken and input provided to 0-RAP in plant records.

W W85tiligh00S8 Revision: Prel.

July ll,1997 16.3-33

TABLE 16.3-2 INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS l

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

. SR 2.8.1 Energize each required hydrogen ignitor and verify the surface Each refueling outage temperature is > [1700] F.

Table 2.8-1, Hydrogen Ignitors (1) l Location Hydrogen Ignitors  !

Group i Group 2 I

- Reactor Cavity note 2 note 2

- Loop Companment 01 12,13 11,14 Loop Compartment 02 5,8 6,7

- Pressurizer Compartment 49,60 50,59

- Tmulel connecting Loop 1,3,31 2,4,30 Compartments

- Southeast Valve Room & 21 20 Southeast Accumulator Room

- East Valve Room, Northeast 18 17,19 Accumulator Room, & Nonheast Valve Room

- Nonh CVS Equipment Room 34 33

- Lower Compartment Area 22.27,28,29,31, 23,24,25,26,30 (CMT and Valve Area) 32 IRWST 9,35,37 10,36,38

- IRWST inlet 16 15

- Refueling Cavity 55,58 56,57

- Upper Compartment

- Lower Region 39,42,43,44,47 40,41,45,46,47

- Mid Region 51,54 52,53

- Upper Region 61,63 62,64 Notes:

1) 7he table lists the hydrogen ignitors. In each hication, all of the ignitors in group I or group 2 should be available.

2) Ignitors in this location are shared with other locations.

Revision: Prel. W W85tingh00S8

~

,luly 11,1997 16.3-34 1

I I

TABLE 16.3 2

$ INVESTMENT PROTECTION SHORT TERM AVAIL. ABILITY CONTROLS 2.0 Plant Systems 2.8 Hydrogen Ignitors BASES:

The hydrogen ignitors should be available to provide the capability of burning hydrogen generated during severe accidents. This function is important because it provides margin in the PRA sensitivity perfonned assuming no credit for nonsafety-related SSCs to mitigate at-power and shutdown events.

The margin provided in the PRA study assumes a minimum availability of 75% for this function.

SSAR section 6.2.4 provides additional infonnation.

The hydrogen ignitor function should be available during MODES I and 2 when core decay heat is I high and during MODES 5 and 6 when the RCS inventory is reduced. Planned maintenance should not be perfonned on required hydrogen ignitors during a required MODE of operation; planned maintenance should be perfomied on redundant hydrogen ignitors.

1 l

e i

I I

4 I

I W Westinghouse Revision: Prel. l July 11,1997 16.3 35 l

TABLE 16.3-2

]

l -INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 3.0 Electrical Power Systems 3.1 'AC Power Supplies Il OPERABILITY: One standby diesel generator should be operable ,

1 APPLICABILITY: MODES 1, 2, 3, 4, 5 l I  !

l l ACTIONS 1 3 CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel volume in one A.1 Notify [ chief nuclear officer) or. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> -

required standby diesel [on-call altemate).

fuel tank less than limit. l AND A.2 Restore volume to within limits 14 days  ;

B. One required fuel tnutsfer B.! Notify [ chief nuclear officer) or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l pump or standby diesel [on-call alternate].

generator not operable.

AND 1

B.2 Restore pump and diesel generator 14 days to operable status I

l l

l l

l l

l Revision: Prel. W W85tingh00$8

~

l .luly II,1997 16,3-36

l TABLE 16.3-2 INVESTS 1ENT PROTECTION SIIORT-TERM AVAILABILITY CONTROLS C. Required Action and C.l Submit report to [ chief nuclear I day associated Completion officer] or [on-call altemate]

Time not met. detailing interim compensatory measures, cause for inoperability and schedule for restoration to OPERABLE.

AND C.2 Document the justification for the 1 month actions taken and input provided to 0-RAP in plant records.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1 Verity that the fuel oil volume in the required standby 31 days diesel generator fuel tank is > [50,(XX)] gal.

SR 3.1.2 Record that the required fuel oil transfer pump provides a 92 days recirculation flow of > [8] gpm.

SR 3.1.3 Verify that the required standby diesel generator starts and 92 days i operates at > [38tX)] kw for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This test may l utilize diesel engine prelube prior to starting and a l wannup period prior to loading. -

l l

l SR 3.1.4 Verify that each standby diesel generator starts and 10 years operates at > [38001 kw for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This test may utilize diesel engine prelube prior to starting and a l warmup period prior to loading. Both diesel generators will be operated at the same time during this test.

W WestilighotJse Revision: Prel.

.luly 11,1997 16.3-37

l .

I TABLE 16.3 2 INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS i

3.0 Electrical Power Systems 3.1 AC Power Supplies BASES:

AC power is required to power the RNS and to provide a nonsafety-related means of supplying power to the safety-related PMS for actuation and post accident monitoring. The RNS provides a nonsafety-related means to inject water into the RCS following ADS actuations in MODES 1,2,3,4 (when steam generators cool the RCS). This AC power supply function is important because it adds margin to the PRA sensitivity performed assuming no credit for nonsafety-related SSCs to mitigate at-power and shutdown events. The margin provided in the PRA study assumes a minimum availability of 75% for this function.

Two standby diesel generators are provided. Each standby diesel generator has its own fuel oil l transfer pump and fuel oil tank. The volume of fuel oil required is that volume that is above the connection to the fuel oil transfer pump. Refer to SSAR section 8.3.1 for additional information.

This AC power supply function should be available during MODES 1,2,3,4,5 when RNS injection and PMS actuation are more risk important. Planned maintenance should not be performed on required AC power supply SSCs during a required MODE of operation; planned maintenance should be perfonned on redundant AC power supply SSCs during MODES 1,2,3 when the RNS is not nonnally in operation. The bases for this recommendation is that the AC power is more risk important during shutdown MODES, especially during reduced RCS inventory conditions, than during other MODES.

d Revision: Prel. T Westinghouse

.luly 11,1997 16.3 38 l

. TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS

- 3.0 Electrical Power Systems 3.2 AC Power Supplies - Reduced Inventory l

l OPERABILITY: Two AC power supplies should be operable to support RNS operation -

p APPLICABILITY: MODE 5 with RCS open, level not visible in pressurizer.

MODE 6 with upper intemals in place and cavity level less than full ACTIONS 4

j CONDITION REQUIRED ACTION COMPLETION TIME j'

1 A. . One required AC power A.1 Remove plant from applicable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />  !

supply not operable. MODES i

B. Required Action and B.I Submit report to (chief nuclear i day associated Completion officer) or (on-call altemate) y Time not met, detailing interim compensatory measures, cause for inoperability.

,-- and schedule for restoration to OPERABLE. .

AND d

B.2 Document the justification for the I month

! actions taken and input provided I

to 0-RAP in plant records.

h J

r 2

i 4

1 e

3 W W95tingh0Use Revisi m: Prel.

July 1997 16.3 39 4

. . - . . - ~ . - - - . - . . . - . . . . .. .. --. . . . - - . .

I TABLE 16.3-2

( INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS i

SURVEILLANCE REQUIREMENTS 1

l SURVEILLANCE FREQUENCY SR 3.2.1 Verify that the required number of AC power supplies are Within I day prior to

operable entering reduced h

inventory conditions E

i 1

l

. I i

Resision: Prel. W Westinghouse

,luly 11,1997 j 16.3-40

. l 4

TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS l

3.0 Electrical Power Systems I 3.2 AC Power Supplies - Reduced Inventory 1

BASES:

AC power is required to power the RNS and its required support systems (CCS & SWS); the RNS provides a nonsafety related means to nonnally cool the RCS during shutdown operations. Titis RNS cooling function is important in MODES 5 and 6 with reduced inventory because it reduces the probability of an initiating event due to loss of RNS cooling during these conditions and because it provides margin in the PRA sensitivity perfonned asstuning no credit for nonsafety-related SSCs to i mitigate at power and shutdown events. The margin provided in the PRA study assumes a minimum availability of 75% for this function.

Two AC power supplies, one offsite and one onsite supply, should be available as follows:

a) Offsite power through the transmission switchyard and either the main step-up transfonner

/ unit auxiliary transfomier or the reserve auxiliary transformer supply from the transmission switchyard, and b) Onsite power from one of the two standby diesel generators.

Refer to SSAR section 8.3.1 for additional infonnation on the standby diesel generators. Refer to SSAR section 8.2 for infonnation on the offsite AC power supply.

One offsite and one onsite AC power supply should be available during MODES 5 and 6 with reduced RCS inventory when the loss of RNS cooling is important. If both of these AC power supplies are not available, the plant should not enter reduced inventory conditions, if the plant has already entered reduced inventory conditions, then the plant should take action to restore this AC power supply function or to leave reduced inventory conditions.

Planned maintenance should not be perfonned on required AC power supply SSCs. Planned maintenance affecting the standby diesel generators should be perfonned in MODES 1,2,3 when the RNS is not nomially in operation. Planned mainteaance of the other AC power supply should be perfonned in MODES 2,3, or MODE 6 with the refueling cavity full. The bases for this recommendation is that the AC power is more risk important during shutdown MODES, especially during reduced RCS inventory conditions than during other MODES.

W W85tifigh0US8 Revision: Prel.

.luly 11,1997 16.3-41

j

'l

. 1

,- TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS ]

3.0 Electrical Power Systems 3.3 AC Power Supplies - Long Tenn Shutdown OPERABILITY: One ancillary diesel generator should be operable

. APPL.lCABILITY: MODES 1, 2. 3. 4, S. 6

)

i

! ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

1 A. Fuel volume in ancillary A.! Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />  ;

diesel fuel tank less than [on-call alternate). I limit.

1- AND A.2 Restore volume to within limits 14 days i B. One required ancillary B.I Notify [ chief nuclear officer] or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

diesel generator not (on-call allemate].

} operable.

4 AND i

B.2 Restore one diesel generator to 14 days

, operable status 1

5 s*

1 J

l 4

Revision: Prel. W" Westinghouse 4 . inly 11,1997 16.3-42

TABLE 16.3-2 INVESTMENT PROTECTION SIIORT-TERM AVAILABILITY CONTROLS l

C. Required Action and C.1 Submit report to [ chief nuclear i day associated Completion officer] or [on-call allemate]

Time not met. detailing interim compensatory measures, cause for inoperability, and schedule for restoration to OPERABLE.

AND C.2 Document the justification for the i month actions taken and input provided to 0-RAP in plant records.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1 Verify fuel volume in the ancillary fuel tank is >[350] gal 31 days SR 3.3.2 Verify that the required diesel generator stans and 92 days operates for >l hour connected to a test load > [14.5] kw.

l This test may utilize diesel engine warmup period prior to l loading. )

l SR 3.3.3 Verify that each diesel generator starts and operates for 4 10 years i hours while providing power to the regulating transfonner, an ancillary control room fan, an ancillary I&C room fan and a passive containment cooling water storage tank recirculation pump that it will power in a long tenn post accident condition. Test loads will be applied to the output of the regulating transformers that represent the loads required for post-accident monitoring and control room lighting. This test may utilize diesel engine wamlup prior to loading. Both diesel generators will be operated at the same time during this test.

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.luly 11,1997 16.3-43

TABLE 16.3-2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 3.0 Electrical Power Systems 3.3 AC Power Supplies - Long Tenn Shutdown I

l BASES; 1

The ancillary diesel generators provide long tenu power supplies for post accident monitoring, MCR l and I&C room cooling, PCS and spent fuel water makeup. For the first three days after an accident the IE batteries provide power for post accident monitoring. Passive heat sinks provide cooling of the MCR and the I&C rooms. The initial water supply in the PCCWST provides for at least 3 days of i PCS cooling. The initial water volume in the spent fuel pit nonnally provides for 7 days of spent fuel l cooling; in some shutdown events the PCCWST is used to supplement the spent fuel pit.

1 After 3 days, ancillary diesel generators can be used to power the MCR and I&C room ancillary fans, the PCS recirculation pumps and MCR lighting, in this time frame, the PCCWST provides water j makeup to both the PCS and the spent fuel pit. An ancillary generator should be available during all MODES of operation. This long tenn AC power supply function is imponant because it suppons long-tenn shutdown operation.

The long tenn AC power supply function involves the use of two ancillary diesel generators and an ancillary diesel generator fuel oil storage tank. Refer to SSAR section 8.3.1 for additional infonnation l on the long tenn AC power supply function. I One ancillary diesel generator and the ancillary diesel generator fuel oil storage tank should be available during all MODES of plant operation. Planned maintenance should not be performed on the l required ancillary diesel generator during a required MODE of operation; planned maintenance should be perfonned on the redundant ancillary diesel generator. Planned maintenance alTecting the ancillary diesel fuel tank that requires less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to perfonn can be perfonned in any MODE of operation. Planned maintenance requiring more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> should be perfonned in MODE 6 with the refueling cavity full. The basis for this recommendation is that core decay heat is low and the risk of core damage is low in these MODES, the inventory of the refueling cavity results in slow response of the plant to accidents.

Revision: Prel, W W85tingh0USS

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.luly 11,1997 16.3-44

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3 ~L TABLE 16.3 2 INVESTMENT PROTECTION SHORT-TERM AVAILABILITY CONTROLS 3.0 Electrical Power Systems i

3.4- DC Power Supplies i

OPERABILITY: Power for DAS automatic actuation functions listed in 1.1 and 1.2 should be . I operable .j 1

APPLICABILITY: MODES 1. 2. 3,4,5, MODE 6 with upper intemals in place and cavity level less than full ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. : Power to DAS Function 'A.1 Notify [ chief nuclear officer] or - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. [on-call altematel. i

~

1 AND l l

l A.2 Restore power supply to DAS to . 14 days operable status i l

B. Required Action and B.1 ' Submit report to [ chief nuclear i day )

associated Completion officerl or [on-call altemate]

Time of Condition A not detailing interim compensatory l m et. measures, cause for inoperability, and schedule for restoration to OPERABLE AND B.2 Document the justification for the I month actions taken and input pmvided ,

to 0-RAP in plant records.

l l

l W Westinghouse Revision: Prel.

July 11,1997 16.3-4,5 j

• 8 t TABLE 16.3-2 INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS  :

l

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR - 2.1.1 - Verify power supply voltage at each DAS cabinet is - 92 days 120 volts 2% -

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.luly 11,1997 16.3-46

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l I

.3' i I ** TABLE 16.3-2 INVESTMENT PROTECTION SIIORT-TERM AVAILABILITY CONTROLS 3.0 Electrical Power Systems 3.4 -Non Class IE DC and UPS System (EDS)

BASES:

The EDS function of providing power to DAS to support ATWS mitigation is important based on 10 l CFR 50.62 (ATWS Rule) and to suppon ESFA is important based on providing margin in the PRA l sensitivity perfonned assuming no credit for nonsafety-related SSCs to mitigate at-power and I shutdown events. The margin provided in the PRA study assumes a minimum availability of 75% for j this function, q

The DAS uses a 2 out of 2 logic to actuate automatic functions. EDS. power must be available to the I DAS sensors, DAS actuation, and the devices which control the actuated components. Power may be provided by EDS to DAS by non-lE batteries through non-lE inverters. Other means of providing power to DAS include the spare battery tiuvugh a non-lE inverter or non-lE regulating transfonners.

The EDS support of the DAS ATWS mitigation function is required during MODE I when ATWS is a limiting event and during MODES 1,2,3,4,5,6 when ESFA is important. The DAS ESFA is required in MODE 6 with upper intemals in place and cavity level less than full. Planned maintenance should not be perfonned on a required EDS SSC during a required MODE of operation; ,

planned main *enance should be perfonned on redundant supplies of EDS power l

l l W W85tingh0US8 Revision: Prel.

l July 11,1997 16.3-47

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