ML20137D871

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Proposed Tech Specs Permitting Continued Operation W/O Completion of Instrumentation Response Time Testing,As Currently Defined in TS for Rps,Eccs & Isolation Actuation Instrumentation
ML20137D871
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 03/22/1997
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20137D856 List:
References
NUDOCS 9703260332
Download: ML20137D871 (11)
v • d • e


Text

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l ENCLOSURE 2 l .

l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 l l

NRC DOCKET NOS. 50-325 AND 50-324 l OPERATING LICENSE NOS. DPR-71 AND DPR-62 i

REQUEST FOR ENFORCEMENT DISCRETION INSTRUMENTATION RESPONSE TIME TESTING l-l MARKED UP TECHNICAL SPECIFICATION PAGES -

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, l l 9703260332 970322 DR ADOCK 05000324 l

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b;. ' l DEFINITIONS EMERCENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME l The EMERCENCY CORE C00LINC SYSTEM (ECCS) RESPONSE TIME shall be that time

! interval from when the monitored parameter exceeds its ECCS actuation setpoint  ;

l at the channel sensor until the ECCS equipment, is capable of performing its l safety function (i.e., the valves travel to their required positions, pump '

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discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

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l FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

CASEOUS RADWASTE TREATMENT SYSTEM i l

l A CASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to l reduce radioactive gaseous effluents by collecting primary coolant system ]

of fgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the g en vi ro nmen t .

IDENTIFIED LEAKACE l

l IDENTIFIED LEAKAGE shall be:

a. Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or l b. Leakage into the containment atmosphere f rom' sources that are both specifically located and known' either not to interfere with the i operation of the leakage detection 'ystems s or not be PRESSURE BOUNDARY LEAXACE.

ISOLATION SYSTEM RESPONSE TIME i

The ISOLATION SYSTEM RESPONSE TIME shall be that time interval trom when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays where j applicable. j@dd .frtsed B . j

. LIMITING CONTRpL ROD PATTERN j A LIMITINC CON'lcROL ROD PATTERN shall be a pattern which results in the core  ;

i being on a limiting value for APLHCR or MCPR.

i l BRUNSWICK - UNIT 1 1-3 Amendment No. 147

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' ' Insert A  :,

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The EMERGENCY CORE COOLING RESPONSE TIME may also be determined  ;

using an alternate methodology if previously reviewed and approved by the NRC. l

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i l Insert B The ISOLATION SYSTEM RESPONSE TIME may also be determined using an  ;

l attemate methodology ifpreviously reviewed and approved by the NRC..  ;

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DEFINITIONS ___

l PROCESS CONTROL

  • PROGRAM (PCP) ,

The PROCESS CONTROL PROGRAM (PCP) shall contain the current formult, sampling, analyses, tests and determinations to be made to ensure that the processing and packaging of solid radioactive vastes based on demonstrated processing of accuni or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 71, and Federal and State .

regulations and other requirements governing the' disposal of the radioactive l '

l waste.

l PURCE - PURCINC PURCE or PURCINC is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or ' gas is required to purify the containment.

RATED THERMAL POWER I

RATED THERMAL POWER shall be total reactor core heat transfer rate to the reactor coolant of 2436 MWt.

f' REACTOR PROTECTION SYSTEM RESPONSE TIME *

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j REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until  !

de-energization of the scram pilot valve solenoids.

/)dd .CM 6  !

l REFERENCE LEVEL ZERO The. REFERENCE LEVEL ZERO point is arbitrarily set at 367 inches above the vessel zero point. This REFERENCE LEVEL ZERO is approximately mid point on

  • the top fuel guide and is the single reference for all specifications of l

vessel water level.

REPORTABLE EVENT

-A REPORTABLE EVENT shall be any of those' conditions specified'in Section 50.73 to 10 CFR Part 50.

ROD DENSITY ,

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ROD DENSITY shall be' the number of control rod ' notches inserted as a fraction

- of the total number of notches. All rods fully inserted is equivalent to 100% ROD DENSITY.

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9 BRUNSWICK - UNIT 1 1-6 Amendment No. 131 l

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' Insert C The REACTOR PROTECTION SYSTEM RESPONSE TIME may also be determined  !

using an alternate methodology if previously reviewed and approved by the NRC. j I

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DEFINITIONS EMERCENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety , function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

Add fmMA END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be that time interval to recirculation pump breaker trip from initial movement of the associated:

a. Turbine stop valves, and
b. Turbine control valves.

l FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

i' CASEOUS RADWASTE TREATMENT SYSTEM A CASE 00S RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE shall be:

a. Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or
b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not be PRESSURE BOUNDARY LEAKAGE.

BRUNSWICK - UNIT 2 1-3 Amendment No.168

Insert A The EMERGENCY CORE COOLING RESPONSE TIME may also be determined using an alternate methodology if previously reviewed and approved by the NRC. l l

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i i,.' L'EFINITIONS

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i ISOLATION SYSTEM RESPONSE TIME The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the I monitored parameter exceeds its isolation actuation setpoint at the channel )

sensor until the isolation valves travel to their required positions. Times  !

shall include diesel generator starting and sequence loading delays where applicable. }Qolo(, fraert. 8 LIMITING CONTROL ROD PATTERN A LIMITINC CONTROL ROD PATTERN shall be a pattern which results in the core being on a limiting value for APLHCR or MCPR. l LOCIC SYSTEM FUNCTIONAL TEST A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all relays and contacts of a logic circuit, from sensor output to activated device, to ensure that components are OPERABLE.

MAXIMUM AVERACE PLANAR LINEAR HEAT CENERATION RATE RATIO The MAXIMUM AVERACE PLANAR LINEAR HEAT CENERATION RATE RATIO (MAPRAT) for a bundle shall be the largest value in the bundle of the ratio of the APLHCR at a specific height in the bundle divided by the exposure dependent APLHCR limit T for that specific height.

MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does not include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

MINIMUM CRITICAL POWER RATIO The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

ODYN OPTION A ODYN OPTION A shall be analyses which refer to minimum critical power ratio limits which are determined using a transient analysis plus an analysis .

uncertainty penalty. .

l j ODYN OPTION B t

i ODYN OPTION B shall be analyses which refer to minimum critical power ratio

, limits determined using a transient analysis which includes a requirement for 20% scram insertion times to reduce the analysis uncertainty penalty.

1 i BRUNSWICK - UNIT 2 1-4 Amendment No. 161

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,- Insert B The ISOLATION SYSTEM RESPONSE TIME may also be determined using an alternate methodology if previously reviewed and approved by the NRC.

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.. DEFINITIONS - ,

PRIMARY CONTAIMENT INTEGRITY (Continued) l

.b. All equipment hatches are closed and sealed.

c. Each containment ' air lock is OPERABLE pursuant to Specification  !

3.6.1.3. i l

d. The containment leakage rates are within the limits of Specification i 3.6.1.2. j l
a. The sealing mechanism associated with each penetration (e.g. , welds, j bellows, or 0-rings) is OPERABLE. ,

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! -1 PROCESS CONTROL PROGRAM (PCP)

The PROCESS CONTROL PROGRAM (PCP) shall contain the current formla, sampling, analyses, tests and determinations to be made-to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20,10 CFR Part 71, and Federal and State

. regulations and other requirements governing the disposal of the radioactive waste.

. PURGE - PURGING PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that reptacement air or gas is required to purify the containment.

i RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2436 MWt.

REACTOR PROTECTION SYSTEM RESPONSE TIME REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. Scki l~n64?r'l"[-

REFERENCE LEVEL ZERO

, The REFERENCE LEVEL ZERO point is arbitrarily set at 367 inches above the vessel zero point. This REFERENCE LEVEL ZERO is approximately mid point on the top fuel guide and is the single reference for all specifications of vessel water level.

BRUNSWICK - UNIT 2 1-6 Amendment No. 88

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,- - Insert C The REACTOR PROTECTION SYSTEM RESPONSE TIME may also be determined using an alternate methodology if previously reviewed and approved by the NRC.

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