ML17284A852

Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown.

ML17284A852
Person / Time
Site:	Columbia
Issue date:	07/29/1999
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17284A851	List: ML17284A850 ML17284A852
References
NUDOCS 9908060116
Download: ML17284A852 (25)

Text

REQVE~ST FOR AbMNDMENT TECHNICALSPECIFICATION 3.4.9 Attachment 3 Marked-Uy Version of Technical Syecification 3.4.9, 3.5.1, and Associated Bases P'P08060iih 990729 PDR ADOCK 0500039'7 P PDR

s RHR Shutdown Cool~ System Hot Shutdown 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per B hour period.

2. One RHR shutdown: cooling subsystem may be inoperable for up, to 2, hours for performance,.of.Surveillances.

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APPLICABILITY: NODE 3 with rea steam dome ress re ess an )l4 cu - ppmis ive repaurf.

ACTIONS NOTES'-

1. LCO 3.0.4 is not applicable..'.

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR A.l Initiate action to Immediately shutdown cooling restore RHR shutdown subsystems inoperable. cooling subsystem to OPERABLE status.

(continued)

WNP-2 3.4-18 Amendment No. 149

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RHR Shutdown Cool'ystem Hot Shutdown 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -- ---- ------ NOTE Not required to be met. until 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after r actor steam dome ess re 'is less than pg psrg tP t- p reefs v ppe u 6.

Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or recirculation pump is operating.

~ P WP-2 3.4-20 Amendment No. 149

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ECCS Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to'he injection valve.

SR 3.5.1.2 ---------- ------ NOTE Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reacto . steam dome ressure less tha . rpsi al/ eat Vgpr '~ + re ev c -s per'm ssi'Pe p esture in NOD , ~ capa e o eing manua ly realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5. 1.3 Verify ADS accumulator backup compressed 31 days gas system average pressure in the required bottles is o 2200 psig.

(continued)

WNP-2 3.5-4 Amendment No. 149

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RHR Shutdown Co g System Hot Shutdown B 3.4.9

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BASES U l~

LCO one subsystem can maintain or reduce the reactor coolant (continued) temperature as required. However, to ensure adequate core flow to allow for accurate average reactor coolant temperature monitoring, nearly continuous operation is required.

o Note 1 permits both RHR shutdown cooling subsystems and ~ Q~

recirculation pumps to be shut down for a period of 2 hours in an 8 hour period. Note 2 allows one RHR shutdown cooling subsystem to be inoperable for up to 2 hours for performance of surveillance tests. These tests may be on the affected RHR System or on some other plant system or component that necessitates placing the RHR System in an inoperable status during the performance. This is permitted because the core heat generation can be low enough and the heatup rate slow enough to allow some changes.to the RHR subsystems or other

- operations requiring RHR flow interruption and loss of redundancy.

APPLICABILITY I OD 3 w'th reactor stea me press re belo t c -i per is 'vg pp s ref (i e. ac a r s u e t t ill egTocK r seg) he RHR BUtdbwn oo ing ystem mus e GPE503 an s al e operated in the shutdown cooling mode to remove decay heat to reduce or maintain coolant temperature. Otherwise, a recirculation pump is required to be in operation.

VIp In. MODES 1 and 2, and in MODE 3 wi reactor steam dome ress e greater than or e ual to e s ve sd're, is CO is not appl>cable. Opera >on of the R ys em sn the shutdown cooling mode is not allowed above s r re because e ay excee t e

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oJoo e steam in below this pressure, t e main condenser.

the OPERABILITY Emergency Core Cooling Systems (ECCS) (LCO 3.5. 1, "ECCS Additionally, in MODE 2.

Operating" ) do not allow placing the RHR shutdown cooling requirements for the VEp j subsystem into operation.

The requirements for decay heat removal in MODES 4 and 5 are discussed in LCO 3.4. 10, "Residual Heat Removal (RHR)

Shutdown Cooling System Cold Shutdown"; LCO 3.9.8, "Residual Heat Removal (RHR) High Water Level"; and LCO 3.9.9, "Residual Heat Removal (RHR) Low Water Level."

(continued)

WNP-2 B 3.4-45 Revision 5

RHR Shutdown Coo 'ystem Hot Shutdown B 3.4.9 BASES (continued)

SURVEILLANCE SR 3.4.9.1 REQUIREMENTS This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.'he, required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient in view of other visual and audible indications available to the operator for monitoring the RHR subsystem in the control room.

This Surveillance is modified .by a Note allowing sufficient .

/<> time to align the RHR System for shutdown coolin operation acA ev after c a n e re s in r p k a i ge s s , or or placing a recircu a ion pump in operation.

p'gw c:6 v /7P<~ he Note takes exception to the requirements of the Surveillance being met (i.e., forced coolant circulation is Q~ pvccs-ural. not required for this initial 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period), which also allows entry into the Applicability of this Specification in accordance with SR 3.0.4 since the Surveillance will not be "not met" at the time of entry into the Applicability.

REFERENCES l. 10 CFR 50.36(c)(2)(ii).

WNP-2 B 3.4-48 Revision 5

C Cold Shutdown RHR Shutdown Cool O System B 3.4. 1 0 BASES LCO can maintain and reduce the reactor coolant temperature as (continued) required. To ensure adequate core flow to allow for accurate average reactor coolant temperature monitoring, nearly continuous opebation is required.

Note 1. permits both RHR shutdown cooling .subsystems and recirculation pumps to be shut down for a period'of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in an 8 hour period. Note 2 allows one RHR shutdown cooling subsystem to be inoperable 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 performance of Surveillance tests. These tests may be on the affected RHR System or on some other plant system or component that necessitates placing the RHR System in an inoperable status during the performance. This is permitted because the core heat generation can be low enough and the heatup rate slow enough to allow some changes to the RHR subsystems or other operations requiring RHR flow interruption and loss of'edundancy.

APPLICABILITY In MODE 4, the RHR Shutdown Cooling System must be OPERABLE and shall be operated in the shutdown cooling mode to remove decay heat to maintain coolant temperature below 200'F.

Otherwise, a recirculation pump is required to be in operation.

Ig'OD S 1 nd 2 and in NODE 3 wit) rea tor team dome pf'ess re g cate tha or qual to he R R cu -in phrmi sive res re, his CO i no appl'cab e. pera ion f th RH Syst m in the hutd wn olin mo e is not lowe ab e thi pre sure beca se t e RC pre sure may xcee the desi n pr ssur of e s tdo n coo ing pipi g. ecay eat emo al at rea or essu es cate tha or qual to t e RH cut in p rmis ive ress re i typi all acc mpli ed b co ens'ng e s earn n th mai ,cond nser. Ad itio ally in ODE elo thi pre's ure,'he ERA ILIT req irem ts f r t e Emer ency Core Cool ng Sy tern (ECC ) (L 0 3. . 1, 'CCS Ope atin ") d not allow plac ng t e RH shu own ooli g syst m int op atio .

'u The re uirements for decay heat removal in NODE 3 below t er iv pressure and in MODE 5 are discusse in es> ual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown"; LCO 3.9.8, "Residual Heat Removal (RHR) High Water Level"; and LCO 3.9.9, "Residual Heat Removal (RHR) Low Water Level."

(continued)

WNP-2 B 3.4-50 Revision 5

ECCS-Operating 8 3.5.1 BASES (continued)

LCO Each ECCS injection/spray subsystem and six ADS valves are required to be OPERABLE. The ECCS injection/spray subsystems are defined as the three LPCI subsystems, the LPCS System, and the HPCS System. The low pressure ECCS injection/spray subsystems are defined as the LPCS System and the three LPCI subsystems.

With less than the required number of ECCS subsystems OPERABLE during a limiting design basis LOCA concurrent with the worst case single failure, the limits specified in 10 CFR 50.46 (Ref. 10) could potentially be exceeded. All ECCS subsystems must, therefore be OPERABLE to satisfy the single failure criterion required by 10 CFR 50.46 (Ref. 10).

LPCI subsystems may be considered OPERABLE durin ali nment "IFpc'iq rcndop- and o aration'or decay heat removal w en below .a II csft i ermimssv pressure in NQDE 3, ff capable o being manually rea igned (remote or local) to the LPCI mode and not otherwise inoperable. Alignment and operation for decay heat removal includes when the required RHR pump is not operating or when the system is being realigned from or to the RHR shutdown cooling mode. At these low pressures and decay heat levels, a reduced complement of ECCS subsystems should provide the required core cooling, thereby allowing operation of RHR.shutdown cooling when necessary.

APPLICABILITY All ECCS subsystems are required to be OPERABLE during MODES 1, 2, and 3 when there is considerable energy in the reactor core and core cooling would be required to prevent fuel damage in the event of a break in the primary system piping. In MODES 2 and 3, the ADS function is not required when pressure is c 150 psig because the low pressure ECCS s'ubsystems (LPCS and LPCI) are capable of providing flow into the RPV below this pressure. ECCS requirements for MODES 4 and 5 are specified in LCO 3.5.2, "ECCS Shutdown."

ACTIONS A.l I'f any one low .pressure ECCS injection/spray subsystem is inoperable, the inoperable subsystem must be restored to OPERABLE status within 7 days. In this condition, the remaining OPERABLE subsystems provide adequate core cooling during a LOCA. However, overall ECCS reliability is reduced because a single failure in one of the remaining OPERABLE subsystems concurrent with a LOCA may result in the ECCS not continued WNP-2 B 3.5-5 Revision 5

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ECCS Operating

~ ~ B 3.5.1 BASES SURVEILLANCE SR 3.5.1.1 (continued}

RE(UIREHENTS the lines are full is to vent at the high points. The 31 day Frequency is based on operating experience, on the procedural controls governing. system operation, and on the gradual nature of void buildup in the ECCS piping.

SR 3.5.1.2 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that. the proper flow, paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking,;,sealing, or securing. A valve. that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it invol'ves verification that those valves potentially capable of being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.

The 31 'day Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing at least once every 92 days. The Frequency of 31 days is further justified because the valves are operated under procedural control and because improper valve alignment would only affect a single subsystem. This Frequency has been shown to be acceptable through operating .

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.experience. gg s'n MODE 3 with the reactor steam dome pressure less than ac c -s p rms iv pr ssur , e RH System may be require o opera e sn the s utdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, this SR is modified by a Note that allows LPCI subsystems to be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. Alignment and operation for decay heat removal includes when the required RHR pump is riot operating or when the system is being realigned from or to the RHR shutdown cooling mode. At the low pressures and decay heat loads continued MNP-2 B 3.5-9 Revision 5

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ECCS Operating

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B 3.5.1 BASES SURVEILLANCE SR 3.5. 1.2 (continued)

REQUIREHENTS associated with ope ation in HODE 3 with reactor steam dome pressure less than t of low c t pressure ytmyCs e su sys es ems r,

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reduced complement ECCS provide the required core cooling, thereby allowing operation of RHR shutdown cooling, when necessary.

SR 3.5.1.3 Verification every 31 days that ADS accumulator backup compressed gas system average pressure. in the required bottles is e 2200 psig-assures an adequate and OPERABLE air supply to the ADS valves.'he minimum number of required bottles is 14 bottles in Division I and 17 in Division 2.

The remote nitrogen cylinder connection in'he DG corridor may be used to make up the minimum number of required bottles, provided the bottle(s) is properly installed to satisfy the seismic Category 1 restraint requirements and the bottle(s) capacity is greater than or equal to the capacity of the bottle being replaced. The nitrogen banks are sized to provide a 30 day supply of nitrogen for the ADS function. The ADS function is required to provide a flow path for alternate shutdown cooling. Alternate shutdown cooling is accomplished utilizing one RHR subsystem and the ADS to provide a path to the suppression pool for decay heat removal.

SR 3.5.1.4 The performance requirements of the ECCS pumps are determined through. application of the,10 CFR 50, Appendix K, criteria (Ref. 8). This periodic Surveillance is performed (in accordance with the ASHE Code,Section XI, requirements for the ECCS pumps) to verify that the ECCS pumps will develop the flow rates required by the respective analyses.

The ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of 10 CFR 50.46 (Ref. 10).

The pump flow rates are verified against a system pressure difference. For the LPCS and LPCI pumps the pressure difference is equivalent to that between the reactor and the suppression pool air volume. For the HPCS pump it is equivalent to the differential above the suction source continued WNP-2 B 3.5-10 Revision 5

REQUEST FOR AMENDME<NT TECHNICAL SPECIFICATION 3.4.9 Replacement Pages for Technical Specification 3.4.9 and 3.5.1

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R HR Shutdown Cooling System Hot Shutdown 3.4.9

'.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES-

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.

2. One RHR shutdown cooling subsystem may. be .inoperable for up to 2 hours for performance of Surveillances.

APPLICABILITY: MODE 3 with reactor steam dome pressure less than 48 psig.

ACTIONS NOTES

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION RE(UIRED ACTION COMPLETION TIME A. One or two RHR A.1 Initiate action to Immediately shutdown cooling restore RHR shutdown subsystems inoperable. cooling subsystem to OPERABLE status.

AND (continued)

WNP-2 3.4-18 Amendment No. 449

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RHR Shutdown Coolin System Hot Shutdown 3.4.9

'URVEILLANCE REQUIREMENTS SURVEILLANCE FRE(UENCY SR 3.4.9.1 NOTE Not required to be met until 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after reactor steam dome pressure is less than 48 psig.

Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or recirculation pump is operating.

WNP-2 3.4-20 Amendment No. 449

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ECCS Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5. 1. 1 Verify, for each ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 -NOTE-Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for. decay heat removal with reactor steam dome pressure less than 48 psig in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5. 1.3 Verify ADS accumulator backup compressed 31 days gas system average pressure in the required bottles is z 2200 psig.

(continued)

WNP-2 3.5-4 Amendment No. 449

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