ML20217K218

Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings

ML20217K218
Person / Time
Site:	Wolf Creek
Issue date:	10/17/1997
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20217K215	List: ML20217K212 ML20217K218
References
NUDOCS 9710240065
Download: ML20217K218 (4)

Text

i Attachment IV to ET 97-0126 Page 2 of 3 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE001REMENTS

4. 5. 2' Each ECCS subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Numher Valva Function Valva Position bN-HV-8813 Safety Injection to Open RWST isolation V1v EM-HV-8802A(8) 51 Pump Discharge Closed Hot Leg Iso Vivs EM-HV-8835 Safety Injection Open Cold Leg Iso V 1ve EJ-HV-8840 RHR/S! Hot Leg Closed Recirc Iso Valve EJ-HV-880gA RHR to Accum Inj Open

. Loops 1 & 2 Iso Viv EJ-HV-88098 RHR to Accum Inj Open loops 3 & 4 Iso Viv ,

b. At least once per 31 days by:

1) is full of water'by ventin the VerifyingthattheECCSpipingle hg - pump casings and accessi rge piping high po nts,

2) Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position,

c. By a visual inspection which verifies that no loose debris (rags, trash,-clothing, etc.) is present in the containment which could be

. transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall-

~be performed:

1) For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and

2) At least once daily of the areks affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established,

d. At least once per 18 months by:

1). Verifying automatic interlock action of the RHR System from the

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Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System p'.' essure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened. 9710240065 971o17 "

PDR ADOCK 05000482 WOLF CREEK - UNIT-1 3/4 5-4 mondment No. 49,105 y .. . .. ..- .. . .

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! Attachment IV to ET 97-0126 Page 3 of 3 EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUB5YSTEMS (Continued)

The Ifmitation for a maximum of one centrifugal charging pump to be OPERA 8LE and the Surveillance Requirements to verify all charging pumps except the required OPERABLE charging pump to be ir. operable in M00E5 4 and 5 and in MODE 6 with the reactor vessel head on, provides assurance that a mass 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 M00E 4, in M00E 5 with the water level above the top of the reactor vessel flange.-and in MDOE 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 PORY 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 affacts of a loss of decay heat removal during a reduced RC5 inventory condition.

The surveillance Requirements provided to ensure OPERASILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem.0PERASILITV'is maintained. Surveillance Requirements for throttle valve positio.i stops and flow balance testing provide assurance that proper ECC5 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) provide the proper flow split between injection pidnts in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable 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 ensuret t;,at a failure of one valve will not cause an intersystem LOCA. The survel;1ance Requirements to vent t fees pump casings and accessible, i.e. .: can be reached without personnel haza or high radiation dose,mdischarge piping ensures against inoperable pumps ca ed by gas binding or wa 'or r in ECCS piping. .

3/4.5.5 UELING WATER STORAGE TANK R M d S I]

The OPERA 8ILITY-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 voluna 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 are. consistent with the LOCA' analyses.

n WOLF CREEK - UNIT--I B 3/4 5 Amendment No. 23, 35

l Attechment V to ET 97-0126 Pcge 1 of 2 ATTACHMENT V PROPOSED TECHNICAL SPECIFICATION CHANGES IMPROVED TECHNICAL SPECIFICATION BASES 4

o Attachment V to ET 97-0126 page 2 of 2 ECCS-Operating 8 3.5.2 i ..

' BASES SURVEILLMCE SR 3.5.2.2 REQUIREMENTS l (continued) Verifying the correct aligr. ment for manual, power operated, and l 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 pos1 tion, since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an actuation signal is allowed to be in a nonaccident position provided the valve will automatically reposition within the proper stroke time. This Surveillance does not require any testing or valve manipulation. Rather,it involves verification that those valves capable of being mispositioned are in the correct position. The 31 day Frequency is appropriate because the valves are operatW under administrative control, and an imprmer valve position would only

, affect a single train. This Freque.n;y has bcon shown to be acceptable through operating experience.

SR 3.5.2.3 The ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and y pockets of entrained gases. Maintainina the piping from the ECCS pumps to the RCS full of water by venting

• pump casings and p' accessible, discharge piping high point vents ensures that the system will perform properly, injecting its full capacity into the RCS upon demand., Accessible high point vents are those that ran De reached without hazard or high radiation dose to personnel. This will also prevent water hammer, pump cavitation, and pumping of noncondensible gas (e.g., air, nitrogen, or hydrogen) into the reactor vessel following an SI signal or during shutoown cooling. The 31 day Frequency takes into.

consideration the gradual nature of gas accumulation in the ECCS

-u pipjfELand the proc _edural controls governing system operationm, _

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Periodic surveillance testing of ECCS ptanps to detect gross degradation caused by irpeller structural damage or other hydraulic component problems is required by Section /I of the (continued) dCGS ITS BASES B 3.5 18 5/15/97 m _ ___a