ML20155D085

Correction to Amend 213 to License DPR-68.TS Page & Several Bases Pages Were Missing from Some Copies of Amend,

ML20155D085
Person / Time
Site:	Browns Ferry
Issue date:	10/23/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20155D089	List: ML20155D085
References
NUDOCS 9811030103
Download: ML20155D085 (7)

Text

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RPS Elactric Powsr Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS

., SURVEILLANCE FREQUENCY i

SR 3.3.8.2.1 Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.8.2.2 Perform CHANNNL CAllBRATION. The184 days Allowable Values shall be:

a. Overvoltage s 132 V, with time delay set to s 4 seconds,

b. Undervoltage 2108.5 V, with time delay set to s 4 seconds.

c. Underfrequency 2 56 Hz, with time delay set to s 4 seconds.

SR 3.3.8.2.3 Perform a system functional test.

18 months 1

BFN-UNIT 3 3.3-78 Amendment NO. 213 9811030103 981023 PDR ADOCK 05000296 p

PDR y

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Control Rod Block Instrum ntation B 3.3.2.1 BASES ACTIONS C.1. C.2.1.1. C.21.2. and C.2.2 (continued) accordance with the restrictions imposed by Required Action C.2.2. Required Action C.2.2 allows for the RWM Function to be performed manually and requires a double check of compliance with the prescribed rod sequence by a second licensed operator (Reactor Operator or Senior Reactor Operator) or other qualified member of the technical staff (e.g.,

a qualified shift technical advisor or reactor engineer).

The RWM may be bypassed under these conditions to allow continued operations. In addition, Required Actions of LCO 3.1.3 and LCO 3.1.6 may require bypassing the RWM, during which time the RWM must be considered inoperable with Condition C entered and its Required Actions taken.

D1 With the RWM inoperable during a reactor shutdown, the operator is still capable of enforcing the prescribed control rod sequence. Required Action D 1 allows for the RWM Function to be performed manually and requires a double check of compliance with the prescribed rod sequence by a second licensed operator (Reactor Operator or Senior Reactor Operator) or other qualified member of the technical staff. The RWM may be bypassed under these conditions to allow the reactor shutdown to continue.

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BFN-UNIT 3 B 3.3-67 Amendment No. 213

Control Rod Block Instrumsntation B 3.3.2.1 BASES a

SURVEILLANCE Condition entered and Required Actions taken. This Note is REQUIREMENTS based on the reliability analysis (Ref. 9) assumption of the (continued) average time required to perform a channel Surveillance. That analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that a control rod block will be initiated when necessary.

SR 3.3.2.1.1 A CHANNEL FUNCTIONAL TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function. It includes the Reactor Manual Control System input.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 184 days is based on reliability analyses (Ref.11).

SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function.

The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs. This test is performed as soon as possible after the applicable conditions are entered. As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until i hour after (continued)

BFN-UNIT 3 B 3.3-69 Amendment No. 213

e Control Rod Block Instrumsntation B 3.3.2.1 BASES s

SURVEILLANCE SR 3 3.2.1.5 REQUIREMENTS (continued)

The RWM is automatically bypassed when power is above a specified value..The power level is determined from feedwater flow and steam flow signals. The automatic bypass setpoint must be verified periodically to be > 10% RTP. If the RWM low power setpoint is nonconservative, then the RWM is considered inoperable. Alternately, the low power setpoint channel can be placed in the conservative condition (nonbypass). If placed in the nonbypassed condition, the SR is met and the RWM is not considered inoperable. The Frequency is based on the trip setpoint methodology utilized for the low power setpoint channel.

SR 3.3.2.1.6 A CHANNEL FUNCTIONAL TEST is performed for the Reactor Mode Switch - Shutdown Position Function to ensure that the entire channel will perform the intended function. The CHANNEL FUNCTIONAL TEST for the Reactor Mode Switch -

Shutdown Position Function is performed by attempting to withdraw any control rod with the reactor mode switch in the shutdown position and verifying a control rod block occurs.

As noted in the SR, the Surveillance is not required to be performed until i hour after the reactor mode switch is in the shutdown position, since testing of this interlock with the reactor mode switch in any other position cannot be performed without using jumpers, lifted leads, or movable links. This allows entry into MODES 3 and 4 if the 18 month Frequency is not met per SR 3.0.2. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowance is based on operating experience and in consideration of providing a reasonable time in which to complete the SRs.

(continued)

BFN-UNIT 3 B 3.3-71 Amendment No. 213

PAM instrum:ntation B 3.3.3.1 BASES 4

LCO

5. Primary Containment Area Radiation (Hioh Rance)

(continued)

(RR-90-272 and RR-90-273)

Primary containrhent area radiation (high range) is provided to monitor the potential of significant radiation releases and to provide release assessment for use by operators in determining the need to invoke site emergency plans. Two high range

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primary containment area radiation signals are transmitted from i

separate radiation detectors and are continuously recorded and

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displayed on two control room recorders. These recorders are the primary indication used by the operator during an accident.

Therefore, the PAM Specification deals specifically with this portion of the instrument channel.

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6. Primary Con; iinment isolation Valve (PCIV) Position PCIV position is provided for verification of containment integrity, in the case of PCIV position, the important information is the isolation status of the containment penetration. The LCO requires one channel of valve position indication in the control room to be OPERABLE for each active PCIV in a containment penetration flow path, i.e., two total channels of PCIV position indication for a penetration flow path with two active valves.

For containment penetrations with only one active PCIV having control room indication, Note (b) requires a single channel of valve position indication to be OPERABLE. This is sufficient to redundantly verify the isolation status of each isolable penetration via indicated status of the active valve, as applicable, and prior knowledge of passive valve or system boundary status, if a penetration flow path is isolated, position indication for the PCIV(s) in the associated penetration flow patn is not needed to determine status. Therefore, the position indication for valves in an isolated penetration flow path is not required to be OPERABLE.

(continued)

BFN-UNIT 3 B 3.3-89 Amendment No. 213

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ATWS-RPTInstrum ntation B 3.3.4.2 J

BASES s

APPLICABLE

b. Reactor Steam Dome Pressure - Hiah SAFETY ANALYSES, (PIS-3-204A, PIS-3-204B, PIS-3-2040, and PIS-3-204D)

LCO, and APPLICABILITY Excessively high RPV pressure may rupture the RCPB. An (continued) increase in the RPV pressure during reactor operation compresses the steam voids and results in a positive reactivity insertion. This increases neutron flux and THERMAL POWER, which could potentially result in fuel i

failure and overpressurization. The Reactor Steam Dome Pressure - High Function initiates an RPT for transients that i

result in a pressure increase, counteracting the pressure increase by rapidly reducing core power generation. For the overpressurization event, the RPT aids in the termination of the ATWS event and, along with the safety / relief valves, limits the peak RPV pressure to less than the ASME Section ll1 Code limits.

The Reactor Steam Dome Pressure - High signals are initiated from four pressure transmitters that monitor reactor steam dome pressure. Four channels of Reactor Steam Dome Pressure - High, with two channels in each trip system, are available and are required to be OPERABLE to j

ensure that no single instrument failure can preclude an

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ATWS-RPT from this Function on a valid signal. The Reactor Steam Dome Pressure - High Allowable Value is chosen to provide an adequate margin to the ASME Section lil Code limits.

(continued)

BFN-UNIT 3 B 3.3-124 Amendment No. 213

Primiry Containmsnt isolation Instrumtntation B 3.3.6.1

=

I BASES

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BACKGROUND

3. 4. Hioh Pressure Coolant iniection System isolation and Reactor Core Isolation Coolino System Isolation (continued) i The Steam Supply Line Pressure - Low and Turbine Exhaust Diaphragm Pressure - High Functions for HPCI and RCIC each contain four channels in a single trip system. The Steam Supply Line Pressure - Low channels are arranged in a series of logic parallel pairs to form one-out-of-two taken twice logic.

Each HPCI isolation valve receives a single isolation signal from this log c. Each RCIC isolation valve receives an isolation signal from this logic through redundant logic systems. The trip system for the Turbine Exhaust Diaphragm Pressure - High Function contains two trip channels. Each trip channel contains two instrument channels (logic parallel pair). The output relays for the trip channels are arranged in logic systems (redundant logic systems for most isolation valves) such that both trip channels must trip (effectively one-out-of-two taken twice logic for the instrument channels) to cause an isolation.

The HPCI and RCIC Area Temperature - High Functions each contain sixteen channels, four Pump Room Area and twelve Torus Aree channels (four channels for each area monitored).

Each trip system contains two trip channels; Logic A trip channel 1 (trip channel output relay 23A-K34 for HPCI and 13A-K10 for RCIC) and trip channel 2 (trip channel output relay 23A-K35 for HPCI and 13A-K11 for RCIC) and Logic B trip channel 1 (trip channel output relay 23A-K6 for HPCI and 13A-K30 for RCIC) and trip channel 2 (trip channel output relay 23A-K8 for HPCI and 13A-K31 for RCIC). Each trip channel receives one input from each of the four areas monitored. Any (continued)

BFN-UNIT 3 B 3.3-193 Amendment No. 213

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