Text

Requests Proposed Change to Tech Specs Deleting Option or Take the Action Required by Table 3.3.1-1 (and 3.3.2-1) in Spec 3.3.1,to Prevent Improper Actions in Event of Inoperable Channels
	ML19282B239
Person / Time
Site:	Brunswick
Issue date:	02/12/1979
From:	Ippolito T; Office of Nuclear Reactor Regulation
To:	Jackie Jones; CAROLINA POWER & LIGHT CO.
References
	NUDOCS 7903120012
	Download: ML19282B239 (17)
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UNITED STATES

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FEBRUARY 12 579 Dockets Nos. 50-325 and 50-324 Mr. J. A. Jones Executive Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602

Dear Mr. Jones:

Review of the General Electric Standard Technical Specifications (GE-STS) has disclosed that the action statements applicable to the Reactor Protection System Instrumentation, Specification 3.3.1, the Isolation Actuation Instrumentation, Specification 3.3.2, and the Bases for Applicability Specification 3.0.3 require revision to prevent improper actions by the licensee in the event of operation with inoperable intrumentation channels.

Brunswick Steam Electric Plant, Units Nos.1 and 2, Reactor Protection System Instrumentation Specification 3.3.1, action "a", specifies:

"With the requirements for the minimum number of OPERABLE channels not satisified for one trip system, place that trip system in the tripped condition within one hour or take the ACTION required by Table 3.3.1-1.",

and Isolation Actuation Instrumentation Specification 3.3.2, action "b", specifies:

"With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel in the tripped condition within one hour, or take the ACTION required by Table 3.3.2-1".

It is not the intent of the Commission to pemit 'the application of the optional action "or take the ACTION required by Table 3.3.1-1 (or 3.3.2-1)" when the minimum number of operable channels is not satisfied for only one of two trip systems in the 1 of 2 taken twice logic. When the associated specific "... ACTION required by Table 3.3.1-1 (or 3.3.2-1)" is "be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months " or "be in at least STARTUP within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ", the licensee would be permitted to continue operation for up to 12 (8) hours with one or both channels in one of the two trip systems inoperable in a non-safe 7903120012_.

Mr. J. A. Jones (untripped) condition. With one channel in one trip system inoperable in a non-safe condition, system safety perfomance would be dependent on a 1-out-of-l logic. With both channels in one trip system inoperable in a non-safe condition the Reactor Protection System Instrumentation and the Isolation Actuation Instrumentation would be unable to perfom their safety functions. This optional action is not necessary to unit operation and is not typically provided f a existirg BWR custom Technical Specifications. The current GE-STS nave been revised to delete this optional action.

You are requested to propose a change to the Technical Specifications for Brunswick Steam Electric Plant, Units Nos.1 and 2, to delete the optional action "or take the ACTION required by Table 3.3.1-1 (and 3.3.2-1)" in Specification 3.3.1, action "a" and Specification 3.3.2, action "b" within 30 days from receipt of this letter.

Brunswick Steam Electric Plant, Units Nos. I and 2, Reactor Protection System Instrumentation Specification 3.3.1, action "b", and Isolation Actuation Instrumentation Specification 3.3.2, action "c", specify:

"With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems take the ACTION required by Table 3.3.1-1 (or 3.3.2-1}."

When the associated specific "... ACTION required by Table 3.3.1-1 (or 3.3.2-1)" is "be in at least HOT SHUTDOWN (or STARTUP) within 12 (8) hours", the licensee would be permitted to continue operation for up to 12 (8) hours in a degraded condition in which up to all four channels j

in both trip systems could be inoperable in a non-safe condition. Again, both instrumentation systems would be unable to perfom their safety functions or would be dependent on 1-out-of-l logic. This action is not necessary to unit operation and is not provided in existing BWR custom Technical Specifications. The following changes have been made to the current GE-STS and you are requestad to propose the following changes to the Technical Specifications for the Brunswick Steam Electric Plant, Units Nos. I and 2, within 30 days from receipt of this letter.

Mr. J. A. Jones.

1.

Change Specification 3.3.1, action "b", and Specification 3.3.2, action "c", to read:

"With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoperable channel in at least one trip system

in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1 (or 3.3.2-1)".

2.

Change Specification 3.3.1, Table 3.3.1-1:

a.

ACTION 1, 3, 5, 6, 9 and 10 to require the units to be in at least HOT SHUTDOWh within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , instead of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

ACTION 4 to require the units to be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , instead of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c.

ACTION 7 to require the units to be in STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.

Change Specification 3.3.2, Table 3.3.2-1; ACTION 20 to require the units to take the ACTION required by a.

Specification 3.0.3.

b.

ACTION 21 to require the units to be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or take the ACTION required by Specification 3.0.3.

c.

ACTION 22 to require the units to be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , instead of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The following addition has been made to the bases for Specification 3.0.3 in the GE-STS to provide guidance in the execution of required actions.

You are requested to propose the same following addition to the bases of the Technical Specifications for the Brunswick Steam Electric Plant, Units Nos. I and 2, within 30 days from receipt of this letter.

"*If both channels are inoperable in one trip system, select at least one inoperable channel in that trip system to place in the tripped condition, except when that would cause the Trip Function to occur."

Mr. J. A. Jones "The unit shall be brought to HOT SHUTDOWN and COLD SHUTDOWN within the required times by promptly initiating and carrying out an orderly shutdown.

It is intended that this guidance also apply whenever an ACTION statement requires the units to be in (at least) STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or to be in (at least) HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ".

To assist you with your submittal we have attached appropriate pages of the Brunswick Units Nos.1 and 2 Technical Specifications which affect the above described changes.

We have determined that for fee purposes that this action normally would be a Cla;5 III amendment as defined in 10 CFR 170.22 but that this action is exempt from fees pursuant to footnote 2 of Section 170.22.

If you have any questions regarding these changes, please contact us.

Sincerely, A

s i

o, Chief Operating Reactors Branch #3 Division of Operating Reactors

Enclosure:

Sample Technical Specifications

s.

Carolina Power & Light Company cc: Richard E. Jones, Esquire Carolina Power & Lig;it Company 336 Fayetteville Street Raleigh, North Carclina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street, NW Washington, D. C.

20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot 110 North Fifth Avera Wilmington, North Carolina 284E Southport - Brunswick County Library 109 W. Moore Street Southport, North Carolina 28461 e

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

Set points and interlocks are given in Table 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

4J With the requirements for the minimum nuhr of OPERABLE channels a.

not satisfied for one trip system, placcMh:t trip sj;t;; in the tripped condition within one hour,sr ::!n 't ACT!= ic:i irtd be' Tw. -

c.

b.

With the requirements for the minimum number of OPERABLE channels tems,V ake the TION reg red by not satisfied for both tri t

AofMM Table 3.3.1-1. A <#Y4 &a L @-t&A cenA' at A c

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The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANtE REQUIREMENTS

4. 3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1, 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of tin.e delay relays and timers necessary for proper functioning of the trip system.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least nce per 18 months. Each test sM11 include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such tLat all channels are t=5ted at least once every N times 18 months where N is the total number of redundan6 channels in a specific reactor trip function.

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e TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 In CONDITION 2 be in at least HOT SHUTDOWN within ours.

In CONDITION 5, suspend all operations involving CORE ALTERATIONS or postive reactivity changes and fully insert all insertable control rods within one hour.

ACTION 2 Lock the reactor mode switch in the Shutdown position within one hour.

ACTION 3 PERATIONAL CONDITION 2, be in at least HOT SHUTDOWN within ours.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

Bu in at least STARTUP withi 1 ours.

ACTION 4 ACTION 5 In OPI NAL CONDITION 1 or 2, be in at least HOT SHUTDOWN withi ours.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods ithin one hour.

Be in at least HOT SHUTDOWN within h ours.

ACTION 6 Be in " RTUP with the main steam line isolation s closed ACTION 7 withi $.oursorinatleastHOTSHUTDOWNwithi ours.

ACTION 8 Initiate a reduction in THERMAL POWER within 15 minutes and be at less than 30% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

In OP NAL CONDITION 1 or 2, be in at least HOT SHUTDOWN ACTION 9 withi ours.

In bPERATIONAL CONDITION 3 ~or 4, immediately and at least once 'er 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify that all control rods are fully inser ed.

In OPERATIONAL CONDITION 5. suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

BRUNSWICX-UNIT 1 3/4 3-4

.o TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 10 - In OPE AL CONDITION 1 or 2, be in at least HOT SHUTDOWN withi urs.

In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

TABLE NOTATIONS a.

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter, b.

The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations.

c.

An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.

d.

These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

e.

This function is not required to be OPERABLE when PRIMARY CONTAIN-MENT INTEGRITY is not required.

f.

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

g.

These functions are bypassed when THERMAL POWER is less than 30%

of RATED THERMAL POWER.

BRUNSWICK - UN'T 1 3/43-5 we

1.

e INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a.

With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declam the channel inoperable and place the inoperable channel.n the tripped condition until the channel is restored to OPERASLE status with its trip setpoint adjusted consister.t with the Trip Setpoint value.

,j b.

With the recuirements for the minimum nudr of OPERABLE channels not satisfieo for one trip system, placeMthe inoperable channel in the tripped condition,within one hour, m s AGIGN

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c.

the eq ents for the minimum number PnA3 c

els not satisfied for both trip systems,V ake th action equired by t

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The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

1 SURVEILLANCE REOU'REMENTS 4.3.2.1 Each isolation actuation instrumeJitation channel shall be-demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all chsnnels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS Be in at least HOT SHUTDOWN in b h rs and in COLD ACTION 20 SHUTDOWN within the followin 3Ohour vesclosedwithin8)-housorbeinatleastHOTSH t-traft'5TARTUP tp t steam line isolatio.

ACTION 21 Be i f

DOWN within Tb hours an n COLD SHUTDOWN within the next

' 3Ohoors.

Be in at least STARTUP withi 2 ours.

ACTION 2E ACTION.23 Establish SECONDARY CONTAIfN INTEGRITY with the standby gas treatment system operating within one hour.

ACTION 24 Isolate the reactor water cleanup system.

ACTION 25 Close the affected system isolation valves and declare the affected systcm inoperable.

ACTION 26 Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 27 Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

NOTES When haid'ing irradiated fuel in the secondary containment.

a.

See Spe:ification 3.6.3.1, Table 3.6.3.1-1 for valves in each

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valve group.

b.

A channel may be placed in an ineserable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance withor, placing the trip system in the tripped condition providod at least one other. OPERABLE channel in the same trip system is monitoring that parameter.

c.

With only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function

.shall be taken.

d.

Trips the mechanical vacuum pumps.

e.

A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.

f.

With reactor steam pressure > 500 psig.

g.

Closes only RWCU outlet isolation valve.

h.

Alarm only.

BRUNSWICK - UNIT 1 3/4 3-16

/e 3/4.0 APPLICABILITY f

I BASES U

Ihe specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveil-lance Requirements within Section 3/4.

3.0.1 This specification states the applicability of each specifi-cation in terms of defined OPERATIONAL CONDITION and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Concition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of specification. For example.

Specification 3.5.1 calls for the HpCI to be OPERABLE and specifies explicit requirements if it become inoperable. Under the terms of i

Specification 3.0.3 if the required additional systems are not OPERABLE, the facility is' to be placed in HOT SHUTDOWN $tithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and W in COLD SHUTDOWN within the following $0 hours.Y

rhe unit shall be brough.t to tQT SWTDOWN And COLD SHUTDOWN

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within the reautred times by promptly tnitiattng and carrying out an orderly shutdown. It is intended that this guidance also apply whenever an ACTION statement requires the units to be in (at least) STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or to be in (at least) t HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.0.4 This specification provides that entry into an OPERABLE CONDITION must be made with (a) the full complement of required system:,

i equipment or components OPERABLE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard for k

allowable deviations and out of service provisions contained in the ACTION statements.

The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other limits being exceeded.

Exceptions to this provision hav.e been provided for a limited q

number of specifications when startup with incperable equipment would not affect plant safety. These exceptions are statea in the ACTION statements of the appropriate specifications.

a 3/4.3 INSTRUMENTATI0t[

3/4.3.1 REACTC? PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

Set points and interlocks are given in Table 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1.

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I a.

With the requirements for the minimum mmber et OPEABLE chan-nels not satisfied for one trip system, plat:84a&tr'; ;.,;t;.T.

in the tripped condition within one hour.ow-teh-4.he AC',3

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With the requirements for the minimum number of OPERABLE chan-nels not satisfied for both trip systems,V ake the ACTION t

required by Taole 3.3.1-1.

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c.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

I SURVEILLANCE REQUIREMENTS

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4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.

4. 3.1. 2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4. 3.1. 3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic trtin such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

s BRUNSWICK - UNIT 2 3/4 3-1 M /2.

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e TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 In CONDITION 2, be in at least HOT SHUTDOWN within ours.

In CONDITION 5. suspend all operations involving CORE ALTERATIONS or postive reactivity changes and fully insert all insertable control rods within one hour.

ACTION 2 Lock the reactor mode switch in the Shutdown position within one hour.

ACTION 3 PERATIONAL CONDITION 2 be in at least HOT SHUTDOWN within ours.

In OPERATIONAL CONDITION 5. suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

ACTION 4 Be in at least STARTUP within ours.

ACTION 5 In OPE

. NAL CONDITION 1 or 2 be in at least HOT SHUTDOWN-within ours.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods w thin one hour.

ACTION 6 Be in at least HOT SHUTDOWN -within ouri.

ACTION 7 Be in TUP with the main steam line isolation 'a s closed withi ours or in at least HOT SHUTDOWW within, ours.

ACTION 3 Initiate a reduction in THERMAL POWER within 15 minutes and be at less than 30% of RATED THEPfiAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

within%Tt0f!A! CONDITION 1 or 2, be in at least HOT SHUTDOWN In OPE ACTION 9 Str;urs.

In OPERn NAL CONDITION 3 or 4, immediately and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify that all control rods are fully inserted.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or pesitive reactivity changes and fully insert all insertable control rods within one hour.

BRUNSWICK - UNIT 2 3/4 3-4

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TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 10 - In OPE RAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within ours.

In OPERATIONAL CONDITION 3 or 4 lock the reactor mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

TABLE NOTATIONS a.

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

.b.

The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin denonstrations.

c.

An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel, d.

These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

o e.

This function is not required to be OPERABLE when PRIMARY CONTAIN-MENT INTEGRITY is not required.

f.

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

g.

These functions are bypassed when THERMAL POWER is less than 30%

of RATED THERMAL POWER.

BRUNSWICK - UNIT 2 3/4 3-5

e INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RE' 'ONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a.

With an isolation actuation instrumentation chunel trip

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setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped con (ition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

ggg b.

With the requirements for the minimum number f OPERABLE channels not satisfied for one trip system, place ee ' inoperable channel r

in the tripped condition within one hour, - "'

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n1, c.

With the requirements for the minimum number of r BLE channels not satisfied for both trip systems,Vtake the action; required by Table 3.3.2-1. f 44.L et 4.# c4 A% a -.. A 1 d -

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4 uQQ The provisions of Specification 3.0.3 ar@e not applica e in d.

OPERATIONAL CONDITION 5 SURVEILLANCE RE0VIREh2NTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip systeel.

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTIONS ihinhhoursandinCOLD ACTION 20 Be in at least HOT SHUTDOWN SHUTDOWN within the followi O ho s.

ACTION 21 Be in at 1 ARTU ith t e main steam line isolation valve ose4within ours or be in at least HOT SHUT-OWN within (p1 ho and in COLD SHUTDOWN within the next hours ACTION 22 Be in at least STARTUP withi urs.

ACTION 23 Establish SECONDARY CONTAINMENT INTEfRITY with the standby gas treatment system operating within one hour.

ACTION 24 Isolate the reactor wate' cleanup system.

ACTION 25 Close the affected system isolation valves and declare the affected system inoperable.

ACTION 76 Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION'27

. Deactivate the shutdown cooling supply and reactor vessel head spray isolation valves in the closed position until the reactor steam dome pressure is within the specified limits.

NOTES When handling irradiated fuel in the secondary containment.

a.

See Spacification 3.6.3.1, Table 3.6.3.1-1 for valves in each valve g oup.

b.

A channel.,.ay be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

c.

With only one channel per trip system, an inoperable channel need not be olaced in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

d.

Trips the mechanical vacuum pumps.

e.

A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE..

f.

With reactor steam pressure > 500 psig.

g.

Closes only RWCU outlet isolation valve.

h.

A,lann only.

BRUNSWICK.- UNIT 2 3/4 3-16

3/4.0 ApPLICABILITl ei f

BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation ard Surveil-lance Requirements within Section 3/4.

3.0.1 This specification states the applicability of each specifi-cation in terms of defined OPERATIONAL CONDITION and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the tems of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements and whose occurrence would violate the intent of specification. For example, Specification 3.5.1 calls for the HPCI to be OPERABLE and specifies i

explicit requirements if it become inoperable;l systems are not OPERABLE, Under the '.erms of Specification 3.0.3 if the required additiona the facility is to be placed in HOT SHUTDOWN hithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Dr in COLD SHUTDOWN within the following GO hours.Y Wrhe unit shall bet bra agh.t to t@T Stt0TD0$ and COLD SHtfTDOWN within the recutred times by promptly initiattng and carrying out an orderly shutdown. It is intended that this guidance also apply whenever an ACTION staternent requires the units to be in (at least) STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or to be in at least HOTSHUTDOWNwithin6hourf.

~

3.0.4 This specification provides,that entry into an OPERABLE CONDITION must be made with (a) the full complement of required systems, j

equipment or components OPERABLE and (b} all other parameters as specified in the Limiting Conditions for Operation being met without regard for i

allowable deviations and out of servica provisions contained in the ACTION statements.

The intent of this provision is to insure that far.ility operation is not initiated with either required equipment or syszems inoperable or other limits being exceeded.

Exceptions to this provision i. ave been provided for a limited number of specifications when startup with inoperable equipment would not affect plant safety. These exceptions are stated in the ACTION t

statements of the appropriate specifications.

BRUNSWICK - UNIT 2 B 3/4 0-1

ML19282B239

Text

Dear Mr. Jones:

Enclosure:

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