ML042540094
| ML042540094 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/02/2004 |
| From: | NRC/NRR/DLPM/LPD2 |
| To: | Duke Energy Corp |
| Olshan L N, NRR/DLPM, 415-1419 | |
| Shared Package | |
| ML042370102 | List: |
| References | |
| TAC MC3334, TAC MC3335, TAC MC3336 | |
| Download: ML042540094 (15) | |
Text
RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from the following RCS PIV shall be within limits:
a.
b.
C.
d.
e.
f.
CF-12, CF-14, LP-47, LP-48, LP-176, and LP-177 I
NOTES-------------------------------------------
- 1.
The limits of LP-47 and LP-48 are not applicable except as stated in Note 2 below.
- 2.
The limits of both LP-47 and LP-48 may be met in lieu of either LP-176 or LP-177 limits.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4 except valves in the decay heat removal (DHR) flow path when in, or during the transition to or from, the DHR mode of operation.
ACTIONS N
NOTES --------------------------------- ----------------------
- 1.
Separate Condition entry is allowed for each flow path.
- 2.
Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more flow
NOTE-----------
paths with leakage Each valve used to satisfy from one or more Required Action A.1 and required RCS PIVs Required Action A.2 must have not within limit.
been verified to meet SR 3.4.14.1 and be on the RCS pressure boundary or the high pressure portion of the system.
(continued)
OCONEE UNITS 1, 2, & 3 3.4.14-1 Amendment Nos. 340, 342, 341 l
LPI 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 Low Pressure Injection (LPI)
LCO 3.5.3 Two LPI trains shall be OPERABLE.
NOTES---------------------------------------------
- 1.
Only one LPI train is required to be OPERABLE in MODE 4.
- 2.
In MODE 4, an LPI train may be considered OPERABLE during alignment, when aligned or when operating for decay heat removal (DHR) if capable of being manually realigned to the LPI mode of operation.
- 3.
In MODES 1, 2, and 3, the LPI discharge header crossover valves inside containment shall be open.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One LPI train A.1 Restore LPI train to 7 days inoperable in MODE 1, OPERABLE status.
2, or 3.
B.
One or more LPI B.1 Open LPI discharge 7 days discharge header header crossover crossover valve(s) valve(s) inside inside containment not containment.
open in MODE 1, 2, or3.
(continued)
I OCONEE UNITS 1, 2, & 3 3.5.3-1 Amendment Nos. 340, 342, 341 l
LPI 3.5.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Action and C.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or AND B not met.
C.2 Be in MODE 4.
60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> D. One required LPI train D.1 Initiate action to restore Immediately inoperable in MODE 4.
required LPI train to OPERABLE status.
AND D.2
NOTE-----------
Only required if DHR loop is OPERABLE.
Be in MODE 5.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify each LPI manual and non-automatic 31 days power operated valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
(continued)
I I
I OCONEE UNITS 1, 2, & 3 3.5.3-2 Amendment Nos.340, 342, 341 1
LPI 3.5.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.3.2
NOTE------------------------
Not applicable to operating LPI pump(s).
Vent each LPI pump casing.
31 days SR 3.5.3.3 Verify each LPI pump's developed head at the In accordance with the test flow point is greater than or equal to the Inservice Testing required developed head.
Program SR 3.5.3.4 Verify each LPI automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.5.3.5 Verify each LPI pump starts automatically on 18 months an actual or simulated actuation signal.
SR 3.5.3.6 Verify, by visual inspection, each LPI train 18 months reactor building sump suction inlet is not restricted by debris and suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion.
OCONEE UNITS 1, 2, & 3 3.5.3-3 Amendment Nos. 340, 342, 341 1
RCS PIV Leakage B 3.4.14 BASES BACKGROUND (continued)
Violation of this LCO could result in continued degradation of a PIV, which could lead to overpressurization of a low pressure system and the loss of the integrity of a fission product barrier.
APPLICABLE SAFETY ANALYSES Reference 4 identified potential intersystem LOCAs as a significant contributor to the risk of core melt. The dominant accident sequence in the intersystem LOCA category is the failure of the low pressure portion of the LPI System outside of containment. The accident is the result of a postulated failure of the PlVs, which are part of the reactor coolant pressure boundary (RCPB), and the subsequent pressurization of the LPI System downstream of the PIVs from the RCS. Because the low pressure portion of the LPI System is designed for pressures significantly less than RCS pressure, overpressurization failure of the LPI low pressure line would result in a LOCA outside containment and subsequent risk of core melt.
Reference 5 evaluated various PIV configurations, leakage testing of the valves, and operational changes to determine the effect on the probability of intersystem LOCAs. This study concluded that periodic leakage testing of the PIVs can substantially reduce the probability of an intersystem LOCA.
RCS PIV leakage satisfies Criterion 2 of 10 CFR 50.36 (Ref. 6).
LCO RCS PIV leakage is identified LEAKAGE into closed low pressure systems connected to the RCS. PIV leakage is usually on the order of drops per minute. Leakage that increases significantly suggests that something is operationally wrong and corrective action must be taken.
The PIV leakage limit for specified valves is 0.5 gpm per nominal inch of valve size with a maximum limit of 5 gpm. A study concluded a leakage rate limit based on valve size was superior to a single allowable value.
Reference 7 permits leakage testing at a lower pressure differential than between the specified maximum RCS pressure and the normal pressure of the connected system during RCS operation (the maximum pressure differential) in those types of valves in which the higher service pressure will tend to diminish the overall leakage channel opening. In such cases, the observed rate may be adjusted to the maximum pressure differential by assuming leakage is directly proportional to the pressure differential to the one half power.
OCONEE UNITS 1, 2, & 3 B 3.4.14-2 Amendment Nos. 340, 342, 341 l
RCS PIV Leakage B 3.4.14 BASES LCO (continued)
The LCO is modified by two Notes. Note 1 indicates that the limits for LP-47 and LP-48 are not applicable except as stated in Note 2. Note 2 indicates that the limits of both LP-47 and LP-48 may be met in lieu of either LP-176 or LP-177 limits. If either LP-176 or LP-177 limits are not met both LP-47 and LP-48 limits must be met.
APPLICABILITY In MODES 1, 2, 3, and 4, this LCO applies because the PIV leakage potential is greatest when the RCS is pressurized. In MODE 4, valves in the DHR flow path are not required to meet the requirements of this LCO when in, or during the transition to or from, the DHR mode of operation.
In MODES 5 and 6, leakage limits are not provided because the lower reactor coolant pressure results in a reduced potential for leakage and for a LOCA outside the containment.
ACTIONS The ACTIONS are modified by two Notes. Note 1 is added to provide clarification that each flow path allows separate entry into a Condition. This is allowed based upon the functional independence of the flow path.
Note 2 requires an evaluation of affected systems if a PIV is inoperable.
The leakage may have affected system OPERABILITY, or isolation of a leaking flow path with an alternate valve may have degraded the ability of the interconnected system to perform its safety function.
A.1 and A.2 The flow path with leakage must be isolated by two valves. Required Actions A.1 and A.2 are modified by a Note that the valves used for isolation must meet the same leakage requirements as the PlVs and must be on the RCS pressure boundary or the high pressure portion of the system.
Required Action A.1 requires that the isolation with one valve must be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Four hours provides time to reduce leakage in excess of the allowable limit and to isolate the affected system if leakage cannot be reduced. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> allows the actions and restricts the operation with leaking isolation valves.
OCONEE UNITS 1, 2, & 3 B 3.4.14-3 Amendment Nos. 340, 342, 341 l
LPI B 3.5.3 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
B 3.5.3 Low Pressure Injection (LPI)
BASES BACKGROUND The function of the ECCS is to provide core cooling to ensure that the reactor core is protected after any of the following accidents:
- a.
Loss of coolant accident (LOCA);
- b.
Rod ejection accident (REA);
- c.
Steam generator tube rupture (SGTR); and
- d.
Main steam line break (MSLB).
There are two phases of ECCS operation: injection and recirculation. In the injection phase, all injection is initially added to the Reactor Coolant System (RCS) via the cold legs or Core Flood Tank (CFT) lines to the reactor vessel. After the borated water storage tank (BWST) has been depleted, the recirculation phase is entered as the suction is transferred to the reactor building sump.
Two redundant low pressure injection (LPI) trains are provided. The LPI trains consist of piping, valves, instruments, controls, heat exchangers, and pumps, such that water from the borated water storage tank (BWST) can be injected into the Reactor Coolant System (RCS). In MODES 1, 2 and 3, both trains of LPI must be OPERABLE. This ensures that 100% of the core cooling requirements can be provided even in the event of a single active failure. The LPI discharge header manual crossover valves inside containment must be maintained administratively open in MODE 1, 2, and 3 to assure abundant, long term cooling. Only one LPI train is required for MODE 4.
A suction header supplies water from the BWST or the reactor building sump to the LPI pumps. LPI discharges into each of the two core flood nozzles on the reactor vessel that discharge into the vessel downcomer area.
OCONEE UNITS 1, 2, & 3 B 3.5.3-1 Amendment Nos. 340, 342, 341
LPI B 3.5.3 BASES BACKGROUND The LPI pumps are capable of discharging to the RCS at an RCS pressure (continued) of approximately 200 psia. When the BWST has been nearly emptied, the suction for the LPI pumps is manually transferred to the reactor building sump.
In the long term cooling period, flow paths in the LPI System are established to preclude the possibility of boric acid in the core region reaching an unacceptably high concentration. Two gravity flow paths are available by means of a drain line from the hot leg to the Reactor Building sump which draws coolant from the top of the core, thereby inducing core circulation. The system is designed with redundant drain lines.
During a large break LOCA, RCS pressure will rapidly decrease. The LPI System is actuated upon receipt of an ESPS signal. If offsite power is available, the safeguard loads start immediately. If offsite power is not available, the Engineered Safeguards (ES) buses are connected to the Keowee Hydro Units. The time delay (38 seconds) associated with Keowee Hydro Unit startup and LPI pump starting determines the time required before pumped flow is available to the core following a LOCA. Full LPI flow is not available until the LPI header isolation valve strokes full open. The ES signal has been removed from LP-21 and LP-22. These valves shall be open when automatic initiation of the LPI system is required. If either one is closed during this time, the associated LPI and RBS train is inoperable.
The LPI and HPI (LCO 3.5.2, 'High Pressure Injection (HPI)"), along with the passive CFTs and the BWST covered in LCO 3.5.1, 'Core Flood Tanks (CFTs)," and LCO 3.5.4, "Borated Water Storage Tank (BWST),' provide the cooling water necessary to meet 10 CFR 50.46 (Ref. 1).
APPLICABLE The LCO helps to ensure that the following acceptance criteria for the SAFETY ANALYSES ECCS, established by 10 CFR 50.46 (Ref. 1), will be met following a LOCA:
- a.
Maximum fuel element cladding temperature is < 22000F;
- b.
Maximum cladding oxidation is < 0.17 times the total cladding thickness before oxidation;
- c.
Maximum hydrogen generation from a zirconium water reaction is
< 0.01 times the hypothetical amount generated if all of the metal in the cladding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react;
- d.
Core is maintained in a coolable geometry; and OCONEE UNITS 1, 2, & 3 B 3.5.3-2 Amendment Nos. 340, 342, 341
LPI B 3.5.3 BASES APPLICABLE
- e.
Adequate long term core cooling capability is maintained.
SAFETY ANALYSES (continued)
The LCO also helps ensure that reactor building temperature limits are met.
The LPI System is assumed to provide injection in the large break LOCA analysis at full power (Ref. 2). This analysis establishes a minimum required flow for the LPI pumps, as well as the minimum required response time for their actuation.
The large break LOCA event assumes a loss of offsite power and a single failure (loss of the CT-4 transformer). For analysis purposes, the loss of offsite power assumption may be conservatively inconsistent with the assumed operation of some equipment, such as reactor coolant pumps (Ref. 3). During the blowdown stage of a LOCA, the RCS depressurizes as primary coolant is ejected through the break into the reactor building. The nuclear reaction is terminated by moderator voiding during large breaks.
Following depressurization, emergency cooling water is injected into the reactor vessel core flood nozzles, then flows into the downcomer, fills the lower plenum, and refloods the core.
In the event of a Core Flood line break which results in a LOCA, with a concurrent single failure on the unaffected LPI train opposite the Core Flood line break, the system is fitted with flow restricting devices in each injection leg and an upstream cross-connect pipe. These serve to limit the ECCS spillage through the faulted header and ensure that flow is diverted from the faulted header to the intact header at lower pressures. These flow restricting devices also provide LPI pump run-out protection during LBLOCAs.
The safety analyses show that an LPI train will deliver sufficient water to match decay heat boiloff rates for a large break LOCA.
In the large break LOCA analyses, full LPI is not credited until 74 seconds after actuation of the ESPS signal. This is based on a loss of offsite power and the associated time delays in Keowee Hydro Unit startup, valve opening and pump start. Further, LPI flow is not credited until RCS pressure drops below the pump's shutoff head. For a large break LOCA, HPI is not credited at all.
The LPI trains satisfy Criterion 3 of 10 CFR 50.36 (Ref. 4).
OCONEE UNITS 1, 2, & 3 B 3.5.3-3 Amendment Nos. 340, 342, 341
LPI B 3.5.3 BASES (continued)
LCO In MODES 1, 2, and 3, two independent (and redundant) LPI trains are required to ensure that at least one LPI train is available, assuming a single failure in the other train. Additionally, individual components within the LPI trains may be called upon to mitigate the consequences of other transients and accidents. Each LPI train includes the piping, instruments, pumps, valves, heat exchangers and controls to ensure an OPERABLE flow path capable of taking suction from the BWST upon an ES signal and the capability to manually (remotely) transfer suction to the reactor building sump. The safety grade flow indicator of an LPI train is required to support OPERABILITY of the LPI and RBS trains to preclude NPSH or runout pro-blems. RBS flow is hydraulically maintained by system resistance, and throttling of RBS flow is not required. Therefore, RBS flow indication is not required to support LPI or RBS train OPERABILITY. However, TS 3.3.8, Required Action F.1 requires the affected RBS train to be declared inoperable when an RBS flow instrument is inoperable. A license amendment is being processed to eliminate this requirement. The safety grade flow indicator associated with LPSW flow to an LPI cooler is required to be OPERABLE to support LPI train OPERABILITY.
LPI BWST Suction Valves, LP-21 and LP-22 do not have an ES signal to open. These valves shall be open when automatic initiation of the LPI and the RBS system is required to be OPERABLE. If either one is closed during this time, the associated LPI and RBS train is inoperable.
In MODE 4, one of the two LPI trains is required to ensure sufficient LPI flow is available to the core.
During an event requiring LPI injection, a flow path is required to provide an abundant supply of water from the BWST to the RCS, via the LPI pumps and their respective supply headers, to the reactor vessel. In the long term, this flow path may be switched to take its supply from the reactor building sump.
This LCO is modified by three Notes. Note 1 changes the LCO requirement when in MODE 4 for the number of OPERABLE trains from two to one. Note 2 allows an LPI train to be considered OPERABLE during alignment, when aligned or when operating for decay heat removal if capable of being manually (remotely) realigned to the LPI mode of operation. This provision is necessary because of the dual requirements of the components that comprise the LPI and decay heat removal modes of the LPI System. Note 3 requires the LPI discharge header crossover valves inside containment to be open in MODES 1, 2, and 3. If one of these valves is closed, then the system will be unable to sustain a single failure.
OCONEE UNITS 1, 2, & 3 B 3.5.3-4 Amendment Nos. 340, 342, 341 1
LPI B 3.5.3 BASES LCO (continued)
The flow path for each train must maintain its designed independence outside containment to ensure that no single failure can disable both LPI trains. If train separation is not maintained outside containment then only one LPI train is considered OPERABLE.
APPLICABILITY In MODES 1, 2 and 3, the LPI train OPERABILITY requirements for the Design Basis Accident, a large break LOCA, are based on full power operation. The position requirements of the LPI discharge crossover valves inside containment for the CFT line break are based on full power operation. Although reduced power would not require the same level of performance, the accident analysis does not provide for reduced cooling requirements in the lower MODES.
I In MODE 4, one OPERABLE LPI train is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
In MODES 5 and 6, unit conditions are such that the probability of an event requiring LPI injection is extremely low. Core cooling requirements in MODE 5 are addressed by LCO 3.4.7, ARCS Loops-MODE 5, Loops Filled,' and LCO 3.4.8, 'RCS Loops-MODE 5, Loops Not Filled." MODE 6.
core cooling requirements are addressed by LCO 3.9.4, DHR and Coolant Circulation-High Water Level,' and LCO 3.9.5, "DHR and Coolant Circulation-Low Water Level."
ACTIONS A.1 With one LPI train inoperable in MODES 1, 2 or 3, the inoperable train must be returned to OPERABLE status within 7 days. The 7 day Completion Time is based on the findings of the deterministic and probabilistic analysis in Reference 7. Reference 7 concluded that extending the Completion Time to 7 days for an inoperable LPI train improves plant operational flexibility while simultaneously reducing overall plant risk. Specifically, the risk incurred by having the LPI train unavailable for a longer time at power will be substantially offset by the benefits associated with avoiding unnecessary plant transitions and by reducing risk during shutdown operations.
OCONEE UNITS 1, 2, & 3 B 3.5.3-5 Amendment Nos. 340, 342, 341
LPI B 3.5.3 BASES ACTIONS B.1 (continued)
With one or more required LPI discharge header manual crossover valves inside containment closed, the closed valve(s) must be opened within 7 days. The 7 day Completion Time is based on the findings of the deterministic and probabilistic analysis in Reference 7.
C.1 If the Required Action and associated Completion Time of Condition A or B are not met, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
D.1 With one required LPI train inoperable in MODE 4, the unit is not prepared to respond to an event requiring low pressure injection and may not be prepared to continue cooldown using the LPI pumps and LPI heat exchangers. The Completion Time of immediately, which would initiate action to restore at least one LPI train to OPERABLE status, ensures that prompt action is taken to restore the required LPI capacity. Normally, in MODE 4, reactor decay heat must be removed by a decay heat removal (DHR) loop operating with suction from the RCS. If no LPI train is OPERABLE for this function, reactor decay heat must be removed by some alternate method, such as use of the steam generator(s).
The alternate means of heat removal must continue until one of the inoperable LPI trains can be restored to operation so that continuation of decay heat removal (DHR) is provided.
With the LPI pumps (including the non ES pump) and LPI heat exchangers inoperable, it would be unwise to require the unit to go to MODE 5, where the only available heat removal system is the LPI trains operating in the DHR mode. Therefore, the appropriate action is to initiate measures to restore one LPI train and to continue the actions until the subsystem is restored to OPERABLE status.
OCONEE UNITS 1, 2, & 3 B, 3.5.3-6 Amendment Nos. 340, 342, 341 1
LPI B 3.5.3 BASES ACTIONS D.2 (continued)
Required Action D.2 requires that the unit be placed in MODE 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This Required Action is modified by a Note that states that the Required Action is only required to be performed if a DHR loop is OPERABLE. This Required Action provides for those circumstances where the LPI trains may be inoperable but otherwise capable of providing the necessary decay heat removal. Under this circumstance, the prudent action is to remove the unit from the Applicability of the LCO and place the unit in a stable condition in MODE 5. The Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is reasonable, based on operating experience, to reach MODE 5 in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.5.3.1 REQUIREMENTS Verifying the correct alignment for manual and non-automatic power operated valves in the LPI flow paths provides assurance that the proper flow paths will exist for LPI 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. Similarly, this SR does not apply to automatic valves since automatic valves actuate to their required position upon an accident signal.
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 operated under administrative control, and an inoperable valve position would only affect a single train. This Frequency has been shown to be acceptable through operating experience.
When in MODE 4 an LPI train may be considered OPERABLE during alignment, when aligned or when operating for decay heat removal if capable of being manually realigned to the LPI mode of operation.
Therefore, for this condition, the SR verifies that LPI is capable of being manually realigned to the LPI mode of operation.
SR 3.5.3.2 With the exception of systems in operation, the LPI pumps are normally in a standby, non-operating mode. As such, the flow path piping has the potential to develop voids and pockets of entrained gases. Venting the LPI pump casings periodically reduces the potential that such voids and pockets of entrained gases can adversely affect operation of the LPI System. This will also minimize the potential for water hammer, pump OCONEE UNITS 1, 2, & 3 B 3.5.3-7 Amendment Nos. 340, 342, 341 1
LPI B 3.5.3 BASES SURVEILLANCE SR 3.5.3.2 (continued)
REQUIREMENTS cavitation, and pumping of noncondensible gas (e.g., air, nitrogen, or hydrogen) into the reactor vessel following an ESPS signal or during shutdown cooling. This Surveillance is modified by a Note that indicates it is not applicable to operating LPI pump(s). The 31 day Frequency takes into consideration the gradual nature of gas accumulation in the LPI piping and the existence of procedural controls governing system operation.
SR 3.5.3.3 Periodic surveillance testing of LPI pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by Section Xl of the ASME Code (Ref. 6). SRs are specified in the Inservice Testing Program, which encompasses Section Xl of the ASME Code.
SR 3.5.3.4 and SR 3.5.3.5 These SRs demonstrate that each automatic LPI valve actuates to the required position on an actual or simulated ESPS signal and that each LPI pump starts on receipt of an actual or simulated ESPS signal. This SR is not required for valves that are locked, sealed, or otherwise secured in position under administrative controls. The test will be considered satisfactory H control board indication verifies that all components have responded to the ESPS actuation signal properly (all appropriate ESPS actuated pump breakers have opened or closed and all ESPS actuated valves have completed their travel). The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a unit outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. The 18 month Frequency is also acceptable based on consideration of the design reliability (and confirming operating experience) of the equipment.
The actuation logic is tested as part of the ESPS testing, and equipment performance is monitored as part of the Inservice Testing Program.
OCONEE UNITS 1, 2, & 3 B 3.5.3-8 Amendment Nos.340, 342, 341 1
LPI B 3.5.3 BASES SURVEILLANCE SR 3.5.3.6 REQUIREMENTS (continued) to the location, and on the potential for an unplanned transient if the Surveillance were performed with the reactor at power. This Frequency has been found to be sufficient to detect abnormal degradation and has been confirmed by operating experience.
REFERENCES
- 1.
- 2.
UFSAR, Section 15.14.3.3.6.
- 3.
UFSAR, Section 15.14.3.3.5.
- 4.
- 5.
NRC Memorandum to V. Stello, Jr., from R.L. Baer, "Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.
- 6.
ASME, Boiler and Pressure Vessel Code,Section XI, Inservice Inspection, Article IWV-3400.
- 7.
NRC Safety Evaluation of Babcock & Wilcox Owners Group (B&WOG) Topical Report BAW-2295, Revision 1, Justification for the Extension of Allowed Outage Time for Low Pressure Injection and Reactor Building Spray systems," (TAC No. MA3807) dated June 30,1999.
I OCONEE UNITS 1, 2, & 3 B 3.5.3-9 Amendment Nos.3 40, 342, 341