ML19257D048

Revised Tech Specs 3/4 3-5 & 9-3 Re Source Range Instrumentation

ML19257D048
Person / Time
Site:	Brunswick
Issue date:	01/24/1980
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19257D046	List: ML19257D045 ML19257D048
References
NUDOCS 8001310279
Download: ML19257D048 (4)

Text

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TABLE 3.3.1-1 (Continuedl REACTOR PROTECTION SYSTFM INSTRUMENTATION .

ACTION 10 - In OPERAT!ONAL CONDITION I or 2, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

In OPERATIONAL CONDITICN 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

, inserc 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the scme trip system is monitoring that parameter.

b. DELETED

c. An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRi 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f. With any control red withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 o 3.9.10.2.

g. These functions are bypassed when THiRMAL POWER is less than 30%

of RATED THERMAL POWER.

/

3RUNSW:^K - UNIT 1 3/4 3-5 so01310 M 7

REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor (SRM) channels

• shall be OPERABLE and inserted co the normal operation level with:

a. A continuous visual indication in the control room,

b. One of the SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and tne other SR'1 detector located in an adjacent quadrant, and APPLICABILITY: CONDITION 5.

ACTION:

With the requirements of the above specification not sati,sfied, imme-diately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

1. Performance of a CHANNEL CHECK,

• The use of specia Fmovable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.

BRUNSWICK - UNIT 1 3/4 9-3

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTICM 10 - In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 12 bours.

In GPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shttdown 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 witnin one hour.

TABLE NOTATIONS

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

ame trip system is monitoring that parameter.

b. DELETED c.

An APRM channel is inoperable if there are less than'2 LPRM inputs per level or less than eleven LP.Ti inputs to an APR!i 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 OPEPABLE 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.

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

of RATED THERMAL POWER.

BRUNSWICK - UNIT 2 1841 225 3/4 3-5

REFUELIriG OPERATI0ils 3/4.9.2 IflSTRUMEtiTATION LIMITIflG CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor (SRM) channels

• shall be OPERABLE and inserted to the normal operation level with:

a. A continuous visual indication in the control room,

b. One of the SRM detectors located in the quadrant where CORE ALTERATI0 tis are being performed and the other SRM detector located in an adjacent quadrant, and s

APPLICABILITY: C0ilDITION 5.

ACTIOf t:

With the requirements of the above specification not satisfied, imme-diately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMEtlTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

1. Performance of a CHANilEL CHECK,

• The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.

1841 226 BRUNSWICK - UilIT 2 3/4 9-3