ML20059A504

Proposed Tech Specs Extending STI & AOT Times for Selected Instrumentation

ML20059A504
Person / Time
Site:	Hope Creek
Issue date:	10/18/1993
From:	Public Service Enterprise Group
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Shared Package
ML20059A500	List: ML20059A496 ML20059A504
References
NLR-N93154, NUDOCS 9310260350
Download: ML20059A504 (17)

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ATTACHMENT 2 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION 93-06, NLR-N93154 STI/AOT EXTENSIONS FOR SELECTED INSTRUMENTATION FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 l

The following Technical Specifications have been revised to reflect the proposed changes:

Technical Specification Pace 3.3.4.2 3/4 3-45 l

l Table 3.3.4.2-1, Note (a) 3/4 3-47 l

Table 4.3.4.2.1-1 3/4 3-50 3.3.4.1 3/4 3-41 Table 3.3.4.1-1, Note (a) 3/4 3-42 Table 4.3.4.1-1 3/4 3-44 3/4.3.4 Bases B 3/4 3-3 4.3.9.1 3/4 3-105 4.3.9.1, Note (*)

3/4 3-105 Table 4.3.9.1-1 3/4 3-108 l

3/4.3.9 Bases B 3/4 3-7 4.4.2.1 3/4 4-8 4.4.2.2.1 3/4 4-9 4.4.2.2.1 Note (**)

3/4 4-9 3/4.4.2 Bases B 3/4 4-2 j

9310260350 931018 I

PDR ADOCK 05000354 p

PDR m

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3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION I

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.4.1-2.

APPLICABILITY:

OPERATIONAL CONDITION 1.

i ACTION:

With an ATWS recirculation pump trip system instrumentation channel a.

trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4.1-2, declare the channel inoperable until i

the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value.

With the number of OPERABLE channels one less than required by the b.

Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.

With the number of OPERABLE channels two or more less than required c.

by the Minimum OPERABLE Channels per Trip System requirement for one trip system, and.

I 1.

If the inoperable channels consist of one reactor vessel water inoperable channels in the tripped condition withi levelchannelandonereactorvesselpressurechannel, placebo r if this action will initiate a pump trip, declare the trip system inoperable.

2.

If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperable.

With one trip system inoperable, restore the inoperable trip system d.

to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With both trip systems inoperable, restore at least one trip system e.

to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.4.1.1.

Each ATWS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.1-1.

4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

HOPE CREEK 3/4 3-41

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8 TABLE 3.3.4.1-1 h!

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION HINIMUM OPERABLE CHANNELS PER TRIP FUNCTION TRIP SYSTEM (8) 1.

Reactor Vessel Water Level -

2 Low Low, level 2 2.

Reactor Vessel Pressure - High 2

R T

O (a) One channel may be placed in an inoperable status for up to 3shours for required surveillance provided the other channel is OPERABLE.

d TABLE 4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS O

m CHANNEL CHANNEL FUNCTIONAL CHANNEL

^

TRIP FUNCTION CHECK IEST CAllBRATION 1.

Reactor Vessel Water level -

5

%Q R

Low Low, level 2 2.

Reactor Vessel Pressure - High S

% Q R

R.

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+

INSTRUMENTATION

_END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATIO LIMITING CONDITION FOR OPERATION 3.3.4.2 Th.

end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels shown in Table 3.3.4.2-1 shall be OPERA column of Table 3.3.4.2-2 and with the END-OF-CYCLE SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.

APPLICABILITY:

equal to 30% ~of RATED THERMAL POWER. OPERATIONAL CONDITION 1, w s

i ACTION:

L V'th an end-of cycle recirculation pump trip system instrumentation a.

21 trip setpoint less conservative than the value shown in the

.sowable Values column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE-status with the i

channel setpoir.t adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels one Ussa than required by the Minimum OPERABLE Channels per Trip Syste's requirement for one or botn trip systems, place the inoperable chanrai(s) in the tripped condition within one.houm, il With the number of OPERABLE channels two or more less than required c.

by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

1.

If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within-one hour 0.

62.

2.

If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip systeg inoperable.

d.

W1.th one trip system inoperable, restore the inoperable trip system to OPERA 8LE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or take the ACTION required by Specification 3.2.3.

With both trip systems inoperable, restore at least one trip system e.

to OPERABLE status within one hour or take the ACTION required by l

Specification 3.2.3.

I HOPE CREEK i

3/4 3-45 Amendment No. 1

5 A

l Alll E 3. 3. 4. 2-1 k

END-01 -CYCll RLCIRCul All0N PUNP IRIP SYS il H IN___S_i_k.i1Ht til Al..l_u_il HINIMUM OPI RAlli 1 LilANNI PIR1RIPSYSilH{})

TRIP FUNCil0N 1.

Turbine Stop Valve - diosure Ih) 2 2.

Turbine Control Valve-Fast Closure IDI F

A Lrip system may be placed iii an inopes'able slatus f or up toh@ tioisi s d

w that the other trip system is OPERAllLE.

Ius i espii n eil siirvei i lasite pi uv s.le.1 i

(b)This function shall be automatically bypassed when turbine first stage pi' essure is : 159./ lisig espia valesit l to TilERMAL POWER less than 30% of RATED TilERMAL POWER.

To allow foi-iii> ti uittesit as s_iii at.y, s al ibrat ion and dr.ift, a setpoint of < 135.7 psig is used.

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TABLE 4.3.4.2.1-1 5

A END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS h

CHANNEL p

FUNCTIONAL CHANNEL TRIP FUNCTION TEST CALIBRATION 1.

Turbine Stop Valve-Closure KQ R

2.

Turbine Control Valve-Fast Closure

%Q R

R.

Y 8

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INSTRUMENTATION 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9 The feedwater/ main turbine trip system actuation instrumentation channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9-2.

APPLICABILITY:

As shown in Table 3.3.9-1.

ACTION:

With a feedwater/ main turbine trip system actuation instrumentation a.

channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9-2, declare the channel inoperable and either place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, or declare the associated system inoperable.

b.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With the number of OPERABLE channels two less than required by the c.

Minimum OPERABLE Channels requirement, restore at least one of the inoperable _ channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.9.1 Each feedwater/ main turbine trip system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST sad CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.9.1-1, t 4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

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TABLE 4.3.9.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS a

A CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WillCil TRIP FUNCTIONAL CliECK CHECK TEST CAllBRATION SURVLILLANCE REQUIRED 1.

Reactor Vessel Water Level-High, level 8 S

R 1

=

a co l

l l

REAC.R.CCLANT :iS~Eu IURVEILLANCE REOUIREMENT5 J. 1. 2. '

'he acoustic monitor for eacn safety / relief valve shall te cemonstratec PERABLE.ith tne setooint serifiea to :e < 30% of full coen noise level *"

oy per'Ormance of a:

(gg, s.

CHANNEL UNCTIONAL TEST at ' east once ser '

days, and a

HANNEL CALIBRATION at least once per 18 months" c.

2.2.2.2 At least 1/2 of tne safety relief valves snail be removed, set oressure testec anc reinstalled or replaced with spares that have been oreviously set oressure testec and stored in accoraance with manufacturer's recommenaations at

' east once per 18 months, and they snall be rotated such that all 14 safety

+

elief saives are removec, set oressure tested and reinstalled or reolacea witn scares that nave oeen oreviously set pressure tested ano stored in accorcance

.itn manufacturer's recommencations at least once per 40 months.

"The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

• • Initial setting shall be in accordance with the manufacturer's recommendations.

Adjustment to the valve full open noise level shall be accomplished after the initial noise traces have been analyzed.

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HOPE CREEK 3/4 4-8 Amendment No. 35 l

l

REACTOR C00LANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION LIMITING CONDITION FOR OPERATION

]

3.4.2.2 The relief valve function and the low-low set function of the following reactor coolant system safety / relief valves shall be OPERA 8LE with the following settings:

Low-Low Set Function Setpoint" (psic) 22%

Valve No.

Open Close F013H 1017 905 F013P 1047 935 APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the relief valve function and/or the low-low set function of one of a.

the above required reactor coolant system safety /reifef valves inoperable, restore the inoperable relief valve function and low-low set function to OPERABLE status within 14 days or be in at least NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

With the relief valve function and/or the low-low set function of both of the above required reactor coolant system safety / relief valves inoperable, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.2.2.1. The relief valve function and the low-low set function pressure actuation instrumentation shall be comonstrated OPERA 8LE Vy performance of a:

92-CHANNELFUNCTIONALTESTatleastonceper3/ days.

a.

b.

CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automati:

operation of the entire system (excluding actual valve actuation) at least once per 18 months.

"The lift setting pressure shall correspond t.o ambient conditions of the valves at nominal operating temperatures and pressures.

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D i e urs for required & true; mnn oc o fwu+ pa u g + N 1"P Q Gi o n r n a ht; irippe c1 Ca s til ML J

HOPE CREEK 3/4 4-9

~

4 I

Add insert A to Technical Specification Bases 3/4.3.4,

" Recirculation Pump Trip Actuation Instrumentation".

Insert A:

Specified surveillance intervals and surveillance and maintenance allowed out-of-service times have been j

determined in accordance with GENE-770-06-1-A, " Bases for Changes to Surveillance Test intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications", as approved by the NRC and documented in the SER (letter to R.

D.

Binz (BWROG) from C.

E. Rossi, dated July 21, 1992).

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i INSTRUMENTATION BASES 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.

The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NEDO-10349, dated March 1971, NEDO-24222, dated December 1979, and Section 15.8 of the FSAR.

The end-of cycle recirculation pump trip (EOC-RPT) system is an essential safety supplement to the reactor trip.

The purpose of the EOC-RPT is to recover the loss of thermal margin which occurs at the end-of-cycle.

The physical phe-nomenon involved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity.

Each EOC-RPT system trips both recirculation pumps, reducing coolant flow ~in order to reduce the void col-lapse in the core during two of the most limiting pressurization events.

The two events for which the E0C-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine control valves.

J A fast closure sensor from each of two turbine control valves provides input to the EOC-RPT system; a fast closure sensor from each of the other two turbine control valves provides input to the second EOC-RPT system.

Similarly, a position switch for each of two turbine stop valves provides input to one EOC-RPT system; a position switch from each of the other two stop valves provides j

1 input to the other EOC-RPT system.

For each EOC-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for the fast closure of turbine control valves and a 2-out-of-2 logic for the turbine stop valves.

The operation of either logic will actuate the EOC-RPT system and trip both recirculation pumps.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled.

The manual bypasses and the automatic Operating Bypass at less than 30% of RATED THERMAL POWER are annunciated in the control room.

The EOC-RPT system response time is the time assumed in the analysis between initiation of valve motion and complete suppression of the electric arc, i.e.,175 ms.

Included in this time are:

the response time of the sensor, the time allotted for breaker arc suppression (135 ms @ 100% RTP), and the response time of the system logic.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint end the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.

(ifdSO2T A)

HOPE CREEK B 3/4 3-3

[

i Add insert A to Technical Specification Bases 3/4.4.2,

.f'

" Safety / Relief Valves".

Insert A:

Specified surveillance intervals and surveillance and'

.i maintenance allowed out-of-service times have been determined in accordance with GENE-770-06-1-A, " Bases for Changes to Surveillance Test intervals and Allowed

[

Out-Of-Service Times for Selected Instrumentation i

Technical Specifications", as approved by the NRC and documented in the SER (letter to R.

D.

Binz.(BWROG) from C.

E.

Rossi, dated July 21, 1992).

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f 4

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REACTOR COOLANT SYSTEM BASES Neutron flux noise limits are also established to ensure early detection of limit cycle neutron flux oscillations.

BWR cores typically operate with neutron flux noise caused by random boiling and flow noise.

Typical neutron flux noise levels of 1-12% of rated power (peak-to peak) have been reported for the range of low to high recirculation loop flow during both single and dual recirculation loop operation.

Neuw flux noise levels which significantly bound these values are considered in the thermal / mechanical design of GE BWR fuel and are found to be of negligible consequence.

In addition, stability tests at operating BWRs have demonstrated that when stability related neutron flux limit cycle oscillations occur they result in peak-to peak neutron flux limit cycles of 5-10 times the typical values.

Therefore, actions taken to reduce neutron flux noise levels exceeding three (3) times the typical value are suf-ficient to ensure early detection of limit cycle neutron flux oscillations.

Typically, neutron flux noise levels show a gradual increase in absolute magnitude as core flow is increased (constant control rod pattern) with two reactor recirculation loops in operation.

Therefore, the baseline neutron flux noise level obtained at a specific core flow can be applied over a range of core flows.

To maintain a reasonable variation between the low flow and high flow end of the flow range, the range over which a specific baseline is applied should not exceed 20% of rated core flow with two recirculation loops in operation.

Data from tests and operating plants indicate that a range of 20% of rated core flow will result in approximately a 50% increase in neutron flux noise level during

'i operation with two recirculation loops.

Baseline data should be taken near the maximum rod line at which the majority of operation will occur.

However, base-line date taken at lower rod lines (i.e., lower power) will result in a conser-vative value since the neutron flux noise level is proportional to the power level at a given core flow.

3/4.4.2 SAFETY / RELIEF VALVES The safety valve function of the safety / relief valves operates to prevent the reactor coolant system from being pressurized above the Safety Limit of 1375 psig in accordance with the ASME Code.

A total of 13 OPERABLE safety / relief valves is required to limit reactor pressure to within ASME III allowable values for the worst case transient.

Demonstration of the safety / relief valve lift settings will occur only during shutdown.

The safety / relief valves will be removed and either set pres-sure tested or replaced with spares which have been previously set pressure tested and stored in accordance with manufacturer's recommendations at the specified frequency.

The tow-low set system ensures that safety / relief valve discharges are minimized for a second opening of these valves, following any overpressure tran-sient.

This is achieved by automatically lowering the closing setpoint of two valves and lowering the opening setpoint of two varves following the initial opening.

In this way, the frequency and magnitude of the containment blowdown duty cycle is substantially reduced.

Suf ficient redundancy is provided for the low-low set system such that failure of any one valve to open or close at its reduced setpoint does not violate the design basis. ( WECT A)

HOPE CREEK B 3/4 4-2

Add insert A to Technical Specification Bases 3/4.3.9, "Feedwater/ Main Turbine Trip System Actuation Instrumentation".

j Insert A:

Specified surveillance intervals and surveillance and maintenance allowed out-of-service times have been determined in accordance with GENE-770-06-1-A, " Bases for Changes to Surveillance Test intervals and Allowed Out-Of-Service Times for Selected Instrumentation-Technical Specifications", as approved by the NRC and documented in the SER (letter to R.

D.

Binz (BWROG) from C.

E.

Rossi, dated July 21, 1992).

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INSTRUMENTATION BASES 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

3/4.3.9 FEEDWAlER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is pro-vided to initiate action of the feedwater system / main turbine trip system in the event of a high reactor vessel water level (Level 8) to mitigate potential damage to the main turbine-(IGCR'T A)

HOPE CREEK B 3/4 3-7