Text

Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys
	ML20198A081
Person / Time
Site:	Byron, Braidwood
Issue date:	12/14/1998
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20198A063	List: ML20198A057; ML20198A081;
References
	NUDOCS 9812160151
	Download: ML20198A081 (101)
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) %) 'Y Table LA - Details Relocated from CTS l Discussion of CTS Description of New Control Change Reference Re:ocated Details Location Process Type

. ITS Section 5.0,- Administrative Controls 5.0 LA13 6.14.1.b Requirement for the Onsite Review and investigative Function to review and QA $50.54(a);5 3 approve changes to the ODCM. MontselTR 0.59 !

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9812160151 DR 981214 .

ADOCK 05000454 i PDR '

Relocated Detail Types 1 Details of System Design 3 Procedural Details for Meeting TS Requirements 2 Description of System Operation 4 Surveitlance Requirements for Indication-only instrumentation (By)- Byron spectre !

(Bw)- Braidwood specific Byron and Braidwood 1 LA_TBLS.O

ENCLOSURE 1

O ITS REVISION T

ITS SECTION 3.4 4

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i BYRON AMENDMENT 106 i

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Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS)

O 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) l LC0 3.4.11 Each PORV and associated block valve shall be OPERABLE.

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- APPLICABILITY: ; MODES 1. 2. and 3.

} ACTIONS NOTES L. Separate Condition entry is allowed for each PORV and each block valve.

2. LCO 3.0.4 is not applicable.

i-CONDITION REQUIRED ACTION COMPLETION TIME f

a A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

. ino)erable and capable >ower to associated LG of )eing manually alock valve.

V cycled. l l 1 B. One PORV ,ino)erable B.1 Close associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

. and not capa)le of block valve. l being manually cycled. l AND l

l B.2 Remove power from I hour associated block valve. l MQ B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

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BYRON - UNITS 1 & 2 3.4.11 - 1 Amendment 106

Pressurizer PORVs 3.4.11 4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 ' Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperaDie. in manual. control.

AND C.2 Restore block valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

to OPERABLE status.

D. Required Action and 0.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A. AND B. or C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two PORVs inoperable E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and not capable of being manually cycled. MQ d E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. Two block valves F.1 Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months i inoperable, valve to OPERABLE ,

status.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l associated Completion '

Time of Condition F AND not met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months O BYRON - UNITS 1 & 2 3.4.11 - 2 Amendment 106

i Pressurizer PORVs ,

3.4.11 l

SURVEILLANCE RE0VIREMENTS O . _ . _ _ _ . . .

SURVEILLANCE-FREQUENCY l

.SR 3.4.11;.1 NOTE Not required to be met with block valve

'li closec in accordance with the Required Action of Condition B or E. l

. I Perform a complete cycle of each block 9;2 days ;

valve' .

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SR 3.4.11.2 NOTE i Only required to be performed in MODES 1 and 2.

l Perform a complete cycle of each PORV. 18 months j 1

SR L3.4.11.3- Perform a complete cycle of each solenoid 18 months O

-air control valve and check valve on the ,

air accumulators in PORV control systems. '

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- BYRON --UNITS 1 & 2- 3.4.11 - 3 Amendment 106 I l

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Pressurizer PORVs B 3.4.11 I

BASES

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V BACKGROUND (continued)

The unit has two PORVs. each having a relief capacity of 210.000 lb/hr at 2350 psia. The functional design of the PORVs is based on maintaining pressure below tne Pressurizer Pressure-Hign reactor trip setpoint folloviing a step reduction of 50% of full load with steam dump. In addition, the PORVs minimize challenges to the pressurizer safety valves and also may be used for Low Temperature Overpressure Protection (LTOP). See LC0 3.4.12. " Low Temperature Overpressure Protection (LTOP) System."

APPLICABLE Plant operators employ the PORVs to depressurize the RCS in SAFETY ANALYSES response to certain unit transients if normal pressurizer

, spray is not available. For the Steam Generator Tube Rupture (SGTR) event, the safety analysis assumes that manual operator actions are required to mitigate the event.

' If a loss of offsite power is assumed to accompany the event, normal pressurizer spray is unavailable to reduce RCS pressure. The PORVs are assumed to be used for RCS depressurization, which is one of the steps performed to equalize the primary and secondary pressures in order to r3 terminate the primary to secondary break flow and the

'Q radioactive releases from the affected steam generator.

' The PORVs are also modeled in safety analyses for events that result in increasing RCS pressure for which Departure from Nucleate Boiling Ratio (DNBR) criteria are critical (Ref. 2). By assuming PORV actuation. the primary pressure remains below the high pressurizer pressure trip setpoint:

thus, the DNBR calculation is more conservative. As such, i this actuation is not required to mitigate these events, and PORV automatic operation is, therefore not an assumed safety function.

Pressurizer PORVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).

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BYRON - UNITS 1 & 2 B 3.4.11 - 2 Amendment 106

Pressurizer PORVs B 3.4.11 BASES bc LC0 The LCO requires the PORVs and their associated block valves to be OPERABLE for manual operation to mitigate the effects associate 6 with an SGTR.

. By maintaining two PORVs and tneir associated bicck valves i OPERABLE, tne single failure criterion is satisfied. An OPERABLE block valve may be either open, or closed and energized with the capability to be o)ened, since the i

required safety function is accomplis 1ed by manual l o)eration. Although typically open to allow PORV operation, t1e block valves may be OPERABLE when closed to isolate the flow path of an inoperable PORV that is capable of being ,

manually cycled (e.g. as in the case of excessive PORV l leakageL Similarly, isolation of an OPERABLE PORV does not render that PORV cr block valve inoperable provided the I relief function remains available with manual action.

An OPERABLE PORV is required to be capable of manually opening and closing, and not experiencing excessive seat leakage. Excessive seat leakage, although not associated a

with a specific acce>tance criteria, exists when conditions dictate closure of t1e block valve to limit leakage.

T Satisfying the LCO helps minimize challenges to fission (Q product barriers.

1 APPLICABILITY In MODES 1. 2, and 3. the PORV and its block valve are i required to be OPERABLE to limit the potential for a small break LOCA through the flow path. The most likely cause for a PORV small break LOCA is a result of a pressure increase ,

transient that causes the FORV to automatically open. 1 Imbalances in the energy output of the core and heat removal by the secondary system can cause the RCS pressure to increase to the PORV opening setpoint. The most rapid increases will occur at the higher operating )ower and pressure conditions of MODES 1 and 2. The PORVs are also required to be OPERABLE in MODES 1, 2. and 3 for manual actuation to mitigate a steam generator tube rupture event.

O BYRON - UNITS 1 & 2 B 3.4.11 - 3 Amendment 106

Pressurizer PORVs B 3.4.11 i

g BASES lU APPLICABILITY (continued)

Pressure increases are less prominent in MODE 3 because the

, core input energy is reduced, but the RCS pressure is high.

Therefore. the LCO is acclicable in MODES 1, 2. and 3. The LCO is not applicable in MODE 4. 5. or 6. wnen botn oressure and core energy are decreased and the pressure surges become

- much less significant. LC0 3.4.12 addresses the PORV requirements in MODES 4 and 5. and in MODE 6 with the rector vessel head in place.

ACTIONS An ACTION Note 1 has been added to clarify that all pressurizer PORVs and block valves are treated as separate entities, each with separate Completion Times (i.e. the Completion Time is on a component basis). The exception for LCO 3.0.4. Note 2. permits entry into MODES 1. 2. and 3 to perform cycling of the PORVs or block valves to verify their OPERABLE status. Testing is not performed in lower MODES.

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PORVs may be inoperable and capable of being manually cycled (e.g.. excessive seat leakage). In this condition, either d.O the PORVs must be restored or the flow path isolated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The associated block valve is required to be closed but power must be maintained to the associated block valve, since removal of power would render the block valve inoperable. This permits operation of the unit until the next reiueling outage (MODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition.

Quick access to the PORV for pressure control can be made when power remains on the closed block valve. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is based on plant operating experience that has shown that minor problems can be ,

corrected or closure accomplished in this time period.

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O l BYRON - UNITS 1 & 2 B 3.4.11 - 4 Amendment 106 I

Pressurizer PORVs B 3.4.11 r

BASES ACTIONS (continued).

ILJ . B. 2 and B.3 :

If one PORV is inoperable and not capable of Deino manually cycled it must be eitner restored, or isoir : by c!osinu theass.ociated block valve and removing the power to the !

associated block valve. The Completion Times of I hour are !

reasonable, based on challenges to'the PORVs during this time period, and provide the operator adequate time to correct the situation. If the inoperable valve cannot be restored to OPERABLE status, it must be isolated within the ;

specified time. Because there is at least one PORV that '

remains OPERABLE. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is provided to restore the inoperable PORV to OPERABLE status. If the PORV cannot be ,

restored within this time, the unit must be brought to a ,

MODE in which the LC0 does not apply, as required by Condition D.

..GJ. and C.2 If one block valve is inoperable. then it is necessary to either restore the block valve to OPERABLE status within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or place the associated PORV in '

A manual control. The. prime importance for the capability to V

i close the block valve is to isolate a stuck open PORV. .

Therefore, if the block valve cannot be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Required Action is to place the PORV in manual control (i.e.. closed) to preclude its ,

automatic opening for an overaressure event and to avoid the '

potential for a stuck o)en PORV at a time that the block valve is inoyerable. T1e Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable. Jased on the small potential for challenges to j

' the system during this time period, and provides the l operator time to correct the situation. ;

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l Pressurizer PORVs l B 3.4.11 l 1

BASES ,

' ACTIONS (continued)

Because at least one PORV remains OPERABLE the operator is permitted a Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the inoperable block valve to GPERABLE status. The time allowed to restore the clock valve is Dased ueon the Comple: ion Time.

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for restoring an inoperable PORV in Condition B since the PORVs may not be capable:of mitigating an event if the ,

inoperable block valve'is not full' open. If the block valve is restored within the Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the power will be restored, and the PORV restored to OPERABLE >

l- status. If it cannot be restored within this additional f

time, the unit must be brought to a MODE in which the LCO

! does not apply, as required by Condition D. ;

D.1 and D.2 '

If the Required' Action of Condition A. B. or C is not met, I l then the unit must be brought to a MODE in which the LC0 l

-does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 ,

i within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are j reasonable, based on operating experience, to reach the

recuired plant conditions from full power conditions in an N

orcerly manner and without challenging plant systems. In

") MODE 4. 5. and 6 with the reactor vessel head'on, automatic PORV OPERABILITY may be required. See LC0 3.4.12.

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' Pressurizer PORVs B 3.4.11

,. BASES 3) v ACTIONS (continued)

E.1a$dE.2 If two PORVs are inoperable and not capable of being manually cyciec. Condition B and its a scciated Fea r ea Actions would already be entered. The Required Aca ons would either restore at least one valve within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or isolate the flow path by closing and removin.g the power to the associated block valves. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable, based on the small potential-for challenges to the system during this time and provides the operator time to correct the situation. If no PORVs are restored within the Completion Time, then the unit must be brought to a MODE in which the LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the ,

recuired unit conditions from full power conditions in an !

orcerly manner and without challenging plant systems. In MODE 4. 5. and 6 with the reactor vessel head on automatic PORV OPERABILITY may be required. See LCO 3.4.12.

(9 If two block valves are inoperable, it is necessary to restore at least one block valve within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The !

Completion Time is reasonable, based on the small potential !

for challenges to the system during this time and provide l the operator time to correct the situation. '

G.1 and G.2 If the Required Actions of Condition F are not met, the unit l

must be brought to a MODE in which the LC0 does not apply.

To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to' reach the required unit conditions from full power conditions in an orderly manner and without challenging plant systems. In MODE 4. 5. and 6 with the reactor vessel head on, automatic PORV OPERABILITY may be required. See LCO 3.4.12. ,

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BYRON - UNITS 1 & 2 B 3.4.11 - 7 Amendment 106

Pressurizer PORVs B 3.4.11

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SURVEILLANCE SR 3.4.11.1

' REQUIREMENTS Block valve cycling verifies that the valve (s) can be opened and closed if needed. The basis for the Frecuency of 92 aays is the ASME Cace.Section XI Gef. 3).

The Note modifies this SR by stating that it is not required to be met with the block valve closed in accordance with the Required Actions of this LCO. If the block valve is closed to isolate an inoperable PORV that is incapable of being manually cycled, the maximum Completion Time to restore the PORV and open the block valve is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , which is well within the allowable limits (25%) to extend the block udve J Frequency of 92 days. Furthermore, these test requirements would be completed by the reopening of a recently closed block valve upon restoration of the PORV to OPERABLE status ;

(i.e. completion of the Required Actions fulfills the SR).

SR 3.4.11.2 SR 3.4.11.2 requires a complete cycle of each PORV.

Operating a PORV through one complete cycle ensures that the PORV can be manually actuated for mitigation of an SGTR.

The Frequency of 18 months is based on a typical refueling A)

( cycle and industry accepted practice. l The Note modifies the SR to allow entry into and operation in MODE 3 prior to aerforming the SR. This allows the test to be performed in 40DE 3 under operating temperature and l pressure conditions prior to entering MODE 1 or 2. In )

accordance with Reference 4. this test should be performed in MODE 3 or 4 to adequately simulate operating temperature and pressure effects on PORV operation.

SR 3.4.11.3 Operating the solenoid air control valves and check valves on the air accumulators ensures the PORV control system actuates properly when called upon. The Frequency of 18 months is based on a typical refueling cycle and the Frequency of the other Surveillances used to demonstrate PORV OPERABILITY.

1 O BYRON - UNITS 1 & 2 B 3.4.11 - 8 Amendment 106 ,

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Pressurizer PORVs B 3.4.11 BASES REFERENCES 1. Regulatory Guide 1.32, February 1977.

2. UFSAR, Section 15.2.

3. ASME, Boiler and Pressure Vessel Coae. Section .G.

4 .- Generic Letter 90-06. " Resolution of Generic Issue 70.

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" Power Operated Relief Valve and Block Valve Reliability," and Generic Issue 94, " Additional Low Temperature Overpressure Protection for Light Water- l Redctors " pursuant to 10 CFR 50.54(f). June 25, 1990. 1 i

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O BYRON - UNITS 1 & 2 B 3.4.11 - 9 Amendment 106 l

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BRAIDWOOD AMENDMENT 98 O

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Pressurizer PORVs 3.4.11 ,

i 3.4- REACTOR COOLANT SYSTEM (RCS) 3 >

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3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LC0 3.4.11 Each PORV and associated block valve shall be OPERABLE.

l APPLICABILITY: . MODES 1, 2. and 3.

ACTIONS NOTES

1. Separate Condition entry is allowed for each PORV and each block valve.

2. LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION. COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoaerable and capable Sower to associated O of aeing manually alock valve.

(_) cycled.

B. One PORV inoserable B.1 Close associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capaale of block valve.

being manually cycled.

AND B.2 Remove power from I hour associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

BRAIDWOOD - UNITS 1 & 2 3.4.11 - 1 Amendment 98

Pressurizer PORVs

., 3.4.11

,., ACTIONS (continued)

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CONDITION REQUIRED ACTION COMPLETION TIME C .- One block valve C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in manual con +rol.

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! C.2 Restore block valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

4 D .- Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, AND B or C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

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E. Two PORVs inoperable E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

and not capable of being manually cycled. 6NS E.2 Be in' MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. Two block valves F.1 Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. valve to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition F AND not met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months O BRAIDWOOD - UNITS 1 & 2 3.4.11 - 2 Amendment 98

4 Pressurizer PORVs j 3.4.11 l 1

SURVEILLANCE REQUIREMENTS

-Q M SURVEILLANCE FREQUENCY SR 3.4.11.1 NOTE Not required to be met'with block valve closed in accorcance with.the Requirec

. Action of Condition B or E.

Perform a complete cycle of each block 92 days valve. <

.SR 3.4.11.2 NOTE Only required to be performed in MODES 1 and 2.

L Perform a complete cycle of each PORV. 18 months

.SR 3.4.11.3 Perform a complete cycle of each solenoid 18 months f-)

N air control valve and check valve on the air accumulators in PORV control systems.

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,. V BRAIDWOOD - UNITS 1 & 2 3.4.11 - 3 Amendment 98 I j

Pressurizer PORVs B 3.4.11

BASES IV . BACKGROUND (continued) i The unit has two PORVs, each having a relief capacity of 210.000 lb/hr at 2350 psia. The functional design of the PORVs is based on maintaining pressure below the P essurizer

' Pressure-High reactor trip se=c;nt following a sts reouction of 50% of full loaa with steam dump. In acdition. ;

' the PORVs minimize challenges to the pressurizer safety

' valves and also may.be used for Low Temperature Overpressure Protection (LTOP). See LC0 3.4.12. " Low Temperature Overpressure Protection (LTOP) System."

l'- APPLICABLE Plant operators employ the PORVs to depressurize the RCS in SAFETY ANALYSES response to certain unit transients if normal pressurizer i spray is not available. For the Steam Generator Tube 2

Rupture (SGTR) event, the safety analysis assumes that manual operator actions are required to mitigate the event.

If a' loss of offsite power is assumed to accompany the '

event, normal. pressurizer spray is unavailable to reduce RCS pressure. The PORVs are assumed to be used for RCS depressurization, which is one of the steps performed to equalize the primary and secondary pressures in order to terminate the primary to secondary break flow and the O radioactive releases from the affected steam generator.

The PORVs are also modeled in safety analyses for events that result in increasing RCS pressure for which Departure from Nucleate Boiling Ratio (DNBR) criteria are critical (Ref. 2). By assuming PORV actuation, the primary pressure remains below the high pressurizer pressure trip setpoint:

thus, the DNBR calculation is more conservative. As such, this actuation is not required to mitigate these events, and PORV automatic operation is, therefore, not an assumed

. safety function.

Pressurizer PORVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).

O BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 2 Amendment 98

1 Pressurizer PORVs B 3.4.11 BASES LCO The LC0 requires the PORVs and their associated block valves to be OPEPABLE for manual operation to mitigate the effects associated with an SGTR. l l

Bv maintaining two LORVs and their associated tbck velves 4

OPERABLE. the single failure criterion is satisfied. An OPERABLE block valve may be either open, or closed and energized with the capability to be o)ened, since the ;

. required safety function is accomplis 1ed by manual I o)eration. Although typically open to allow PORV operation, i tie block valves may be OPERABLE when closed to isolate the !

d flow path of an-inoperable PORV that is capable of being manually cycled (e.g. as in the case of excessive PORV 4 leakage). Similarly.. isolation of an OPERABLE PORV does not render that PORV or block valve inoperable provided the relief function remains available with manual action. ,

An OPERABLE PORV is required to be capable of manually

. o ening and closing, and not experiencing excessive seat )

3 1 akage. Excessive seat leakage, although not associated with a specific acceatance criteria, exists when conditions dictate closure of t1e block valve to limit leakage.

A Satisfying the LC0 helps minimize challenges to fission

() product barriers.

i APPLICABILITY In MODES 1. 2. and 3. the PORV and its block valve are required to be OPERABLE to limit the potential for a small break LOCA through the flow path. The most likely cause for a PORV small break LOCA is a result of a pressure increase transient that causes the PORV to automatically open.

Imbalances in the energy output of the core and heat removal by the secondary system can cause the RCS pressure to increase to the PORV opening setpoint. The most rapid increases will occur at the higher operating power and pressure conditions of MODES 1 and 2. The PORVs are also required to be OPERABLE in H0 DES 1. 2. and 3 for manual actuation to mitigate a steam generator tube rupture event.

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d[ BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 3 Amendment 98

Pressurizer PORVs B 3.4.11 BASES APPLICABILITY-(continued)

Prcssure increases are less prominent in MODE 3 because the core input. energy is reduced, but the RCS pressure is high. '

Therefore. the LCO is apolicable in MODES 1, 2. and 3. The LCO is not aoplicable ir. MDDE 4, 5, or 6. enen D:tn pressure and core energy are decreased and the pressure surges Deccme much less significant. LCO 3.4.12 addresses the PORV

, requirements in MODES 4 and 5, and in MODE 6 with the .

reactor vessel head in place.

ACTIONS An ACTION Note 1 has been added to clarify that all pressurizer PORVs and block valves are treated as separate entities, each with separate Comoletion Times (i.e., the Completion Time is on a component basis). The exception for LC0 3.0.4, Note 2, permits entry into MODES 1. 2. and 3 to perform cycling of the PORVs or block valves to verify their OPERABLE status. Testing is not performed in lower MODES, Al PORVs may be inoperable and capable of being manually cy'cled (e.g., excessive seat leakage). In this condition, either O, the PORVs must be restored or the flow path isolated within i 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The associated block valve is required to be closed but power must be maintained to the associated block valve, i since removal of power would render the block valve inoperable. This permits operation of the unit until the next refueling outage (MODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition.

Quick access to the PCRV for press ~ure control can be made

when power remains'on the closed block valve. The

! Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is based on plant operating experience that has shown that minor problems can be corrected or closure accomplished in this time period.

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BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 4 Amendment 98 ,

j

Pressurizer PORVs B 3.4.11 BASES ACTIONS (continued) 4 B.1. B.2 and B.3 If one PORV is inoperable and not capable of beina manually '

cycled. it must be either res:cred, or 1solatec of closini tne associated block valve and removing the power to the associated block valve.L The Completion Times of.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months are reasonable, based on challenges to the PORVs during this time period.-and provide the operator adequate time to correct the situation. If the inoperable valve cannot be restored to OPERABLE status.-it must be isolated within the specified time. Because there is at least one PORV that remains OPERABLE. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is provided to restore the inoperable PORV to OPERABLE status. If the PORV cannot be restored within this time, the unit must be brought to a MODE in which the LC0 does not apply, as required by Condition D.

C.1. and C.2 If one block' valve-is inoperable, then it is necessary to either restore the block valve to OPERABLE status within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or place the associated PORV in p manual control. . The prime importance for the capability to

!V close the block valve .is to isolate a stuck open PORV.

Therefore. if the block valve cannot be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Required Action is to place the PORV in manual control (i.e.. closed) to preclude its automatic opening for an over>ressure event and to avoid the potential for a stuck o>en PORV-at a time that the block :

valve is ino>erable. T1e Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable. Jased on the small potential for challenges to the system during this time period, and provides the operator time to correct the situation.

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4 0 .BRAIDWOOD - UNITS.1 & 2. B 3.4.11 - 5 Amendment 98 L

I

Pressurizer PORVs B 3.4.11 g BASES ACTIONS (continued)

Because at least one PORV remains OPERABLE. the operator is permitted a Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the inocerable block valve to OPERABLE status. The time allowed to " stcre the block vaive 's basec unor, the Completion 'ime for restoring an inoperable PORV in Condition B since tne PORVs may not be capable of mitigating an event if the inoperable block valve is not full open. If the block valve is restored within the Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the power will be restored, and the PORV restored to OPERABLE status. If it cannot be restored within this additional time, the unit must be brought to a MODE in which the LCO does not apply, as required by Condition D.

D.1 and D.2 If the Required Action of Condition A. B or C is not met, then the unit must be brought to a MODE in which the LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the recuired plant conditions from full power conditions in an orcerly manner and without challenging plant systems. In h^ MODE 4. 5. and 6 with the reactor vessel head on, automatic PORV OPERABILITY may be required. See LC0 3.4.12.

1 m

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BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 6 Amendment 98

_ __ . -= - .

l Pressurizer PORVs

B 3.4.11 BASES O

d ACTIONS (continued)

E.1 and E.2 If two PORVs are inoperable and not capable of being marually cycled. Co t tion B anc its associatec Recu m d Actions would already be entered. The Required Actions would either restore at least one valve within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or isolate the flow path by closing and removing the power to the associatec' block valves. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable, based on the small potential for challenges to the system during I this time and provides the operator. time to correct the situation. If no PORVs are restored within the Completion l Time, then the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are ,

reasonable, based on operating experience, to reach the '

recuired unit conditions from full power conditions in an orcerly manner and without. challenging plant systems. In MODE 4. 5. and 6 with the reactor vessel head on, automatic PORV OPERABILITY may be required. See LC0 3.4.12.

.If two block valves are inoperable, it is necessary to restore at least one block valve within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The Completion Time is reasonable, based on the small potential for challenges to the system during this time and provide the operator time to correct the situation.

G.1 and G.2 If the Required Actions of Condition F are not met, the unit must be brought to a MODE in which the LC0 does not apply.

To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable. based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging plant systems. In MODE 4. 5. and 6 with the reactor vessel head on, automatic PORV OPERABILITY may be required. See LC0 3.4.12.

(Q>

BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 7 Amendment 98

Pressurizer PORVs B 3.4.11 f BASES b)

SURVEILLANCE SR 3.4.11.1 REQUIREMENTS Block valve cycling verifies that the valve (s) can be opened and closed if needed. The basis for the Frecuency of 92 days is the ASME Code. Sction XI (Ref. 3;.

The Note modifies this SR by stating that it is not required to be met with the block valve closed in accordance with the Required Actions of this LCO. If the block valve is closed to isolate.an inoperable PORV that is incapable of being manually cycled. the maximum Completion Time to restore the PORV and open the block valve is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , which is well within the allowable limits (25%) to extend the block valve Frequency of 92 days. Furthermore. these test requirements would be completed by the reopening of a recently closed block valve upon restoration of the PORV to OPERABLE status (i.e.. completion of the Required Actions fulfills the SR).

SR 3.4.11.2 SR 3.4.11.2 requires a complete cycle of each PORV.

Operating a PORV through one complete cycle ensures that the PORV can be manually actuated for mitigation of an SGTR.

fm The Frequency of 18 months is based on a typical refueling V cycle and industry accepted practice.

The Note modifies the SR to allow entry into and operation in MODE 3 prior to aerforming the SR. This allows the test to be performed in ODE 3 under operating temperature and pressure conditions prior to entering MODE 1 or 2. In accordance with Reference 4. this test should be performed in MODE 3 or 4 to adequately simulate operating temperature and pressure effects on PORV operation.

SR 3.4.11.3 Operating the solenoid air control valves and check valves on the air accumulators ensures the PORV control system actuates properly when called upon. The Frequency of 18 months is based on a typical refueling cycle and the Frequency of the other Surveillances used to demonstrate PORV OPERABILITY.

BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 8 Amendment 98

Pressurizer PORVs B 3.4.11 BASES f-~

V REFERENCES 1. Regulatory Guide 1.32, February 1977.

2. UFSAR. Section 15.2.

3. ASME. Boiler anc Pressure Vessel Ccce. Sectior X .

4. Generic Letter 90-06. " Resolution of Generic Issue 70,

" Power Operated Relief Valve and Block Valve Reliability," and Generic issue 94, " Additional Low Temperature Overpressure Protection for Light Water Reactors." pursuarit to 10 CFR 50.54(f). June 25,1990.

O ,

i BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 9 Amendment 98

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Pressurizer PORVs 3.4.11 ,

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) l LC0 3.4.11 Each PORV and associated block valve shall be OPERABLE. !

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APPLICABILITY: MODES 1. 2. and 3.

ACTIONS 4

NOTES

1. Separate Condition entry is allowed for each PORV and each block valve.

2. LC0 3.0.4 is-not applicable.

?

j CONDITION REQUIRED ACTION COMPLETION TIME 4

A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ino)erable and capable )ower to associated of 3eing manually alock valve. ,

cycled.

B. One PORV ino)erable B.1 Close associated I hour and not capa)le of block valve.

being manually cycled.

I E l B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block -

valve.

E !

t B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued) i

'A i_)

BYRON - UNITS 1 & 2 3.4.11 - 1 12/6/98 Revision T l

Pressurizer PORVs 3.4.11 ACTIONS (continued)

. CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in manual control.

1 M l C.2 Restore block valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

l i

Q .l 9 D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months wj associated Completion H

Time of_ Condition A. M B..or C not met. l

@ D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months W

E. Two PORVs inoperable E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months y and not capable of being manually cycled. E l

0)'s . E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

-l F. Two block valves F.1 Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. valve to OPERABLE status.

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G. Required Action and associated Completion G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 0; Time of Condition F M not met.

H G.2 Be in MODF 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

$l Q BYRON - UNITS 1 & 2 3.4.11 - 2 12/6/98 Revision T

Pressurizer PORVs

} 3.4.11

! .ty SURVEILLANCE' REQUIREMENTS

.V ,

SURVEILLANCE FREQUENCY

'{ .

i. _

SR 3.4.11.1 -

.. NOTE

, l' Not required to De met with block valve

. closea in accorcance with the Requirea c

.l' Action of Condition B or E.

i .

1 Perform a complete cycle of each block 92 days e valve.

s..

SR 3.4.11.2 NOTE - .

Only required to be performed in MODES 1- ,

and 2 Perform a complete cycle of each PORV. 18 months SR 3.4.11.3 Perform a complete cycle of each solenoid 18 months !

O -air control valve and check valve on the air accumulators in PORV control systems.

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f 14 BYRON -. UNITS.1 & 2 3.4.11 - 3 12/6/98 Revision T k= - s , - - . er, .- w . .-m.-t

i Pressurizer PORVs B 3.4.11 BASES O BACKGROUND (continued)

The unit has two PORVs. each having a relief capacity of 210.000 lb/hr at 2350 psia. The functional design of the PORVs is based on maintaining pressure below tr.e Pressurizer Pressure-hign rea :cr tne se point following a ne;.

recuction of 50'. of full load with steam dump. In addition.

the PORVs minimize challenges to the pressurizer safety valves and also may be used for Low Temperature Overpressure Protection (LTOP). See LC0 3.4.12. " Low Temperature Overpressure Protection (LTOP) System." ,

I l

APPLICABLE Plant operators employ the PORVs to depressurize the RCS in ,

SAFETY ANALYSES response to certain unit transients if normal pressurizer i spray is not available. For the Steam Generator Tube Rupture (SGTR) event, the safety analysis assumes that )

manual operator actions are required to. mitigate the event. ;

If a loss of offsite power is assumed to accompany the i event, normal pressurizer spray is unavailable to reduce RCS l pressure. The PORVs are assumed to be used for RCS depressurization, which is one of the steps performed to )

equalize the primary and secondary 3ressures in order to l p terminate the primary to secondary areak flow and the tj radioactive releases from the affected steam generator.

The PORVs are also modeled in safety analyses for events that result in increasing RCS pressure for which Departure l from hucleate Boiling. Ratio (DNBR) criteria are critical l (Ref. 2). By assuming PORV actuation, the primary pressure remains below the high pressurizer pressure trip setpoint:

thus, the DNBR calculation is more conservative. As such, this actuation is not required to mitigate these events. and i PORV automatic operation is, therefore, not an assumed safety function.

Pressurizer PORVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(11). -

BYRON - UNITS 1 & 2 8 3.4.11 - 2 12/7/98 Revision T

1 Pressurizer PORVs ;

B 3.4.11 '

BASES LCO The LC0 requires the PORVs and their associated block valves i to be OPERABLE for manual operation to mitigate the effects associated with an SGTR.

l By m1ntaining two FORVs anc tneir usacinea do:L .aSec OPERABLE, the single failure criterion is satisfied. An OPERABLE block valve may be either open, or closed and -

energized with the capability to be oaened, since the i

required safety function is accomplis 1ed by manual 1 oaeration. Although typically open to allow PORV operation.

tie block valves may be OPERABLE when closed to isolate the i

flow path of an inoperable PORV that is capable of being '

l manually cycled (e.g. as in the case of excessive PORV leakage). Similarly.1 solation of an OPERABLE PORV does not i render that PORV or block valve inoperable provided the l relief function remains available with manual action.

An OPERABLE PORV is required to be capable of manually opening and closing, and not experiencing excessive seat leakage. Excessive seat leakage, although not associated I with a specific acce)tance criteria, exists when conditions dictate closure of tie block valve to limit leakage.

n Satisfying the LC0 helps minimize challenges to fis.uon (j product barriers.

APPLICABILITY In MODES 1. 2, and 3. the PORV and its block valve are required to be OPERABLE to limit the potential for a small break LOCA through the flow path. The most likely cause for a PORV small break LOCA is a result of a pressure increase transient that causes the PORV to automatically open.

Imbalances in the energy output of the core and heat removal by the secondary system can cause the RCS pressure to increase to the PORV opening setpoint. The most rapid increases will occur at the higher operating )ower and pressure conditions of MODES 1 and 2. Wa PORVs are'also 1 required to be OPERABLE in MODES 1. 2, and 3 for manual l

actuation to mitigate a steam generator tube rupture event.

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BYRON - UNITS 1 & 2 B 3.4.11 - 3 12/7/98 Revision T

Pressurizer PORVs B 3.4.11 BASES b

b APPLICABILITY (contir.ued) 4 Pressure increases are less prominent in MODE 3 because the core input energy is reduced, but the RCS pressure is high.

Therefore, the LCO is applicable in MODES 1. 2. and 3. The LCO is not applicacie in MODE 4. 5. or 6. wnen actr c enure and core energy are decreased and tne pressure surges become much less significant. LC0 3.4.12 addresses the PORV requirements in MODES 4 and 5. and in MODE 6 with the reactor vessel head in place.

ACTIONS An ACTION Note 1 has been added to clarify that all pressurizer PORVs and block valves are treated as separate D entities, each with separate Completion Times (i.e., the

Completion Time is on a component basis). The exception for y LC0 3.0.4. Note 2. permits entry into MODES 1, 2. and 3 to perform cycling of the PORVs or block valves to verify their kl OPERABLE status. Testing is not performed in lower MODES.

L.1 l PORVs may be inoperable and capable of being manually cycled (e.g., excessive seat leakage). In this condition, either (A)

~ the PORVs must be restored or the flow path isolated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The associated block valve is required to be closed but power must be maintained to the associated block valve, since removal of power would render the block valve inoperable. This permits operation of the unit until the next refueling outage (MODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition.

Quick access to the PORV for pressure control can be made when power remains on the closed block valve. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is based on plant operating.

experience that has shown that minor problems can be corrected or closure accomplished in this time period.

A V

BYRON - UNITS 1 & 2 B 3.4.11 - 4 12/8/98 Revision T

Pressurizer PORVs B 3.4.11 t

,, BASES

, ACTIONS (continued)

B.1. B.2 and B.3 If one PORV is inoperable and not caoable of bemg manually cy:ied, it must be eltr.er restore . or isola:ec oy cicsing tne associated block valve and removing the power to the

. associated block valve. The Completion Times of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months are reasonable, based on challenges to the PORVs during this time period, and provide the operator adequate time to

, correct the situation. If the inoperable valve cannot be restored to OPERABLE status, it must be isolated within the specified time. Because there is at least one PORV that l remains OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is provided to restore the inoperable PORV to OPERABLE status. If the PORV cannot be restored within this time, the unit must be brought to a MODE in which the LC0 does not apply, as required by Condition D.

C.1. and C.2 If one block valve is inoperable, then it is necessary to either restore the block valve to OPERABLE status within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or place the associated PORV in manual control. The prime importance for the capability to (nJ .

close the Mock valve is to isolate a stuck open PORV.

Therefore, if the block valve cannot be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Required Action is to place the PORV in manual control (i.e., closed) to preclude its automatic opening for an overaressure event and to avoid the potential for a stuck o)en PORV at a time that the block valve is ino>erable. T1e Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable, )ased on the small potential for challenges to the system during this time period, and provides the operator time to correct the situaticn.

I BYRON UNITS 1 & 2 8 3.4.11 - 5 12/7/9B Revision T 1

1 Pressurizer PORVs B 3.4.11 i

i - BASES

p,

J ACTIONS (continued) l Because at le' ast one PORV remains OPERABLE. the operator is i

permitted a Com)letion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the j incoerable bloc ( valve to OPERABLE status. The time allowed i I

to r' estore tne block valve is cased uDan tne Co'T!?ie:1cn Time for restoring an inoperable.PORV in Condition B. since the l PORVs may not.be capable of mitigating an event if the

! - inoperable block valve is not full open. If the block valve is restored within the~ Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . the power will be restored, and the PORV restored to OPERABLE status. 'If it-cannot be restored within this additional time, the' unit must be brought to a MODE in which the LC0

- does not apply, as required by Condition D.

. D.1 and 0.2 L If the Required Action of Condition A. B or C is not met, then the unit must be brought to a MODE in which the LC0

does not apply. To achieve this status, the unit must be i

brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 r within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are

i. reasonable, based on operating experience, to reach the recuired plant conditions from full power conditions in an '

lfs . orcerly manner and without challenging plant systems. In Lt ' l MODE 4. 5.'and 6 with the reactor vessel head on.' automatic PORV OPERABILITY may be required. See LCO 3.4.12.

l L

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BYRON - UNITS 1 & 2 B 3.4.11 - 6 12/7/98 Revision T I'

f l

Pressurizer PORVs B 3.4.11 BASES ACTIONS (continued) l E.1 and E.2 If two PORVs are inoperable and not cacable of bem::

manLally cycled. Condition B and its associnec Eevec Actions would already be entered. The Required Actions would either restore at least one valve within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or isolate the flow path by closing and removing the power to the associated block valves. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable, based on the small potential for challenges to the system during

~

this time and provides the operator time to correct the situation'. If no PORVs are restored within the Completion

? Time then the unit must'be brought to a MODE in which the

' N T:: LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 b within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience. to reach the recuired unit conditions from full power conditions in an orcerly manner and without challenging plant systems. In l MODE 4. 5. and 6 with the reactor vessel head on automatic PORV OPERABILITY may be required. See LCO 3.4.12.

(3 U If two block valves are inoperable, to restore at least one block valve withinit2ishours.

necessarkhe Completion Time is reasonable, based on the small potential ;

for challenges to the system during this time and provide the operator time to correct the situation.

G.1 and G.2 e

i If the Required Actions of Condition F are not met, the unit

must be brought to a MODE in which the LC0 does not apply. I H To achieve this status, the unit must be brought to at least

@ig MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating -

experience, to reach the required unit conditions from full power conditions in an orderly manner and without l challenging plant systems. In MODE 4. 5. and 6 with the 1 reactor vessel head on, automatic PORV OPERABILITY may be I required. See LC0 3.4.12.

P) v BYRON - UNITS 1 & 2 B 3.4.11 - 7 12/7/98 Revision T l

1 Pressurizer PORVs ;

B 3.4.11 ;

1 BASES U

SURVEILLANCE SR 3.4.11.1 !

REQUIREMENTS N

Block valve cycling verifies that the valve (s) can be opened and closed if needed. The basis for the Frequency of Sj j 92 days is tne ASME Code. Se::ien XI (Ref 3' Y l The Note modifies this SR by stating that it is not required to be met with the block valve closed in accordance with the N l Required Actions of this LCO. If the block valve is closed 9 to isolate.an inoperable PORV that is incapable of being l manually cycled, the maximum Completion Time to restore the g PORV and open the block valve is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , which is well D within the allowable limits (25%) to extend the block valve Frequency of 92 days. Furthermore. these test requirements rI would be completed by the reopening of a recently closed block valve upon restoration of the PORV to OPERABLE status (i.e., completion of the Required Actions fulfills the SR).

N SR 3.4.11.2 t h SR 3.4.11.2 requires a complete OperatingaPORVthroughonecomheleofeachPORV.

ete cycle ensures that the PORV can be manually actuated for mitigation of an SGTR.

,3 The Frequency of 18 months is based on a typical refueling g cycle and industry accepted practice.

The Note modifies the SR to allow entry into and operation in MODE 3 prior to aerforming the SR. This allows the test to be performed in 10DE 3 under operating temperature and pressure conditions prior to entering MODE 1 or 2. In accordance with Reference 4. this test should be performed in MODE 3 or 4 to adequately simulate operating temperature and pressure effects on PORV operation.

SR 3.4.11.3 Operating the solenoid air control valves and check valves on the air accumulators ensures the PORV control system ;

actuates properly when called.upon. The Frequency of 18 months is based on a typical refueling cycle and the I Frequency of the other Surveillances used to demonstrate .

PORV OPERABILITY. !

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BYRON - UNITS 1 & 2 B 3.4.11 - 8 12/7/98 Revision T I

I

Pressurizer PORVs B 3.4.11 BASES REFERENCES 1. Regulatory Guide 1.32. February 1977. ;

2. UFSAR. Section 15.2.

j 3. ASME. Cailer anc Pressure Vessel Code. Sec:ici x:.

4

4. Generic Letter 90-06. " Resolution of Generic Issue 70.

" Power Operated Relief Valve and Block Valve '

Reliability." and Generic Issue 94. " Additional Low l Temperature Overpressure Protection for Light Water

. Reactors." pursuant to 10 CFR 50.54(f). June 25. 1990.

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Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) b 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) 1 LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

, APPLICABILITY: MODES 1. 2..and 3.

.; . ACTIONS

~

' NOTES

1. Separate Condition entry is allowed for each PORV and each block valve.

2. LCO 3.0.4 is not applicable.

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. CONDITION REQUIRED ACTION COMPLETION TIME l l

A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ino)erable and capable power to associated

~f^. of 3eing manually block valve.

O cycled.

B. One PORY ino)erable B.1 Close associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capa)le of block valve.

being manually cycled. i l MQ l l B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months l associated block valve. .

MQ B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

BRAIDWOOD - UNITS 1 & 2 3.4.11 - 1 12/6/98 Revision T

Pressurizer PORVs 3.4.11

' ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME' C. One block valve C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperaole. in manual control.

AfjD C.2 Restore block valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months l to OPERABLE status, l

I k ,.

O D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l jf s

associated Completion ,

Time of Condition A. AND l S B, or C not met. '

M D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i N

E. Two PORVs inoperable E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and not capable of being manually cycled. E E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l F. Two block valves F.1 Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. valve to OPERABLE status.

0,

~ l G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion

[I Time of Condition F M

.not met.

hl G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months O

V BRAIDWOOD - UNITS 1 & 2 3.4.11 - 2 12/6/98 Revision T

i Pressurizer PORVs l 3.4.11 l

-SURVEILLANCE RE0UIREMENTS !

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SURVEILLANCE FREQUENCY l

)

SR 3.4.11.1 NOTE l l Not reauired to be met with block valve '

closed in accordan:e witn tne Requirec !

l Action of Condition B or E.

l l

Perform a complete cycle of each block 92 days valve.

SR 3.4.11.2 NOTE .

Only required to be performed in MODES 1 and 2.

l Perform a complete cycle of each PORV. 18 months l

l SR 3.4.11.3 Perform a complete cycle of each solenoid 18 months I air control valve and check valve on the O' air accumulators in PORV control systems.

BRAIDWOOD - UNITS 1 & 2 3.4.11 - 3 -12/6/98 Revision T

Pressurizer PORVs B 3.4.11 BASES

\

BACKGROUND (continued)

The unit has two PORVs, each having a relief capacity of 210.000 lb/hr at 2350 psia. The functional design of the PORVs is based on maintaining pressure below the Pressurizer Pressure-Hign reactor trip setooint following a ster reduction of 50% of full load with steam dump. In aodition.

the PORVs minimize challenges to the pressurizer safety valves and also may be used for Low Temperature Overpressure Protection (LTOP). See LCO 3.4.12. " Low Temperature

, Overpressure Protection (LTOP) System."

APPLICABLE Plant operators employ the PORVs to depressurize the RCS in SAFETY ANALYSES response to certain unit transients if normal pressurizer spray is not available. For the Steam Generator Tube Rupture (SGTR) event, the safety analysis assumes that manual operator actions are required to mitigate the event.

If a loss of offsite power is assumed to accompany the event, normal pressurizer spray is unavailable to reduce RCS' pressure. The PORVs are assumed to be used for RCS depressurization, which is one of the steps performed to equalize the primary and secondary 3ressures in order to e terminate the primary to secondary 3reak flow and the

C radioactive releases from the affected steam generator.

The PORVs are also modeled in safety analyses for events that result in increasing RCS pressure for which Departure from Nucleate Boiling Ratio (DNBR) criteria are critical (Ref. 2). By assuming PORV actuation, the primary pressure remains below the hi h pressurizer pressure trip setpoint:

thus, the DNBR calcu ation is more conservative. As such, this actuation is not required to mitigate these events, and PORV automatic operation is, therefore, not an assumed safety function.

Pressurizer PORVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).

BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 2 12/7/98 Revision T

Pressurizer PORVs B 3.4.11 o BASES

!v)

LCO The LCO requires the PORVs and their associated block valves to be OPERABLE for manual operation to mitigate the effects associated with an SGTR.

, By mairtaining two PORVs and their use: ated bic:k val /=s OPERABLE the single failure criterion is satisfied. .An OPERABLE block valve may be either open, or closed and energized with the capability to be o)ened, since the required safety function is accomplis 1ed by manual operation. Although typically open to allow PORV operation, the block valves may be OPERABLE when closed to isolate the flow path of an inoperable PORV that is capable of being l manually cycled (e.g. as in the case of excessive PORV leakage). Similarly, isolation of an OPERABLE PORV does not render that PORV or block valve inoperable provided the l relief function remains available with manual action.

An OPERABLE f;.V is required to be capable of manually opening and closing, and not experiencing excessive seat leakage. Excessive seat leakage, although not associated with a specific acce3tance criteria, exists when conditions dictate closure of t1e block valve to limit leakage,

p. Satisfying the LC0 helps minimize challenges to fission

() product barriers.

APPLICABILITY In MODES 1, 2. and 3. the PORV and its block valve are required to be OPERABLE to limit the potential for a small break LOCA through the flow path. The most likely cause for a PORV small break LOCA is a result of a pressure increase transient that causes the PORV to automatically open.

Imbalances in the energy output of the core and heat removal by the secondary system can cause the RCS pressure to increase to the PORV opening setpoint. The most rapid increases will occur at the higher operating power and pressure conditions of MODES 1 and 2. The PORVs are also required to be OPERABLE in MODES 1, 2. and 3 for manual actuation to mitigate a steam generator tube rupture event.

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BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 3 12/7/98 Revision T

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_- - . = . - . ..

Pressurizer PORVs B 3.4.11

, _ , BASES APPLICABILITY (continued)

Pressure increases are less prominent in MODE 3 because the core input energy is reduced, but the RCS pressure is high.

Therefore, the LCO is applicable in MODES 1. 2. and 3. The LCO is not applicable in MODE 4. 5. or 6 wnen batn oressure and core energy are decreased and the pressure surges become much less significant. LCO 3.4.12 addresses the PORV requirements in MODES 4 and 5. and in MODE 6 with the reactor vessel head in place.

ACTIONS An ACTION Note 1 has been added to clarify that all s

N pressurizer PORVs and block valves are treated as separate entities, each with separate Completion Times (i.e., the k Completion Time is on a component basis). The exception for LC0 3.0.4, Note 2, permits entry into MODES 1, 2, and 3 to h>% perform cycling of the PORVs or block valves to verify their

%Tl OPERABLE status. Testing is not performed in lower MODES.

J A

1 l PORVs may be inoperable and capable of being manually cycled (e.g.. excessive seat leakage). In this condition, either (o) the PORVs must be restored or the flow path isolated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The associated block valve is required to be closed but power must be maintained to the associated block valve, since removal of power would render the block valve inoperable. This permits operation of the unit until the next refueling outage (MODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition.

Quick access to the PORV for pressure control can be made when power remains on the closed block valve. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is based on plant operating experience that has shown that minor problems can be corrected or closure accomplished in this time period.

BRAIDWOOD - UNITS 1 & 2 8 3.4.11 - 4 12/8/98 Revision T

- ..- - - -... .- . - .-. - -.~.. - ---.- __ - -

1 Pressurizer PORVs '

B 3.4.11 BASES ACTIONS-(continued) i i B.1. B.2 and B.3 l '

If one PORV is inoperable and not capable of being manually cycled. . it must be either restored, or isolated Dy cicsing 4

the associated block valve and removing tne power to the

, associated block valve. The Completion Times of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months are

, reasonable, based on challenges to the PORVs during this

time period, and-provide the operator adequate time to !

correct'the situation. If-the inoperable valve cannot be -'

restored to OPERABLE status, it must bel1solated within the '

o specified time. Because there is at least one PORV that remains OPERABLE. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is provided to restore the l inoperable PORV to OPERABLE status. If the PORV cannot be restored within this time, the unit must be brought to a MODE in which the LCO does not apply, as required by l Condition D. ,

C.1. and C.2 If one block valve is inoperable, then it-is necessary to either restore the block valve to OPERABLE status within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or place the associated PORV in manual control. The prime importance for the capability to O. close the block valve is to isolate a stuck open PORV; Therefore if the block valve cannot be restored to OPERABLE 1

status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Required Action is to place the !

PORV in manual control (i.e., closed) to preclude its automatic opening for an over)ressure event and to avoid the

' potential for a stuck o>en PORV at a time that the block valve is ino>erable. T1e Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .is- .) 4 reasonable. 3ased on the small potential for challenges to a the system during this time period, and i operator time to correct the situation. provides the

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1 0 BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 5 12n/98 Revision T i

.________-__N

Pressurizer PORVs B 3.4.11 BASES O

V ACTIONS (continued)

Because at-least one PORV remains OPERABLE. the operator is permitted a Comaletion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the inoperable blocc valve to OPERABLE status. The time allowed to restore the olock valve is based upon the Ccmole:1:n Time for restoring an inoperable PORV in Condition B. since the PORVs may not be capable of mitigating an event if the inoperable block valve ~1s not full open. If the block valve is restored within the Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . the power will be restored, and the PORV restored to OPERABLE status. If it cannot be restored within this additional time, the unit must be brought to a MODE in which the LCO does not apply, as required by Condition D.

D.1 and D.2 If the Required Action of Condition A. B. or C is not met, then the unit must be brought to a MODE in which the LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the recuired plant conditions from full power conditions in an f orcerly manner and without challenging plant systems. In

' l MODE 4. 5. and 6 with the reactor vessel head on automatic PORV OPERABILITY may be required. See LC0 3.4.12. I O

BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 6 12/7/98 Revision T ,

l

Pressurizer PORVs B 3.4.11 BASES

,,C !-s}

ACTIONS (continued) l E.1 and E.2 If two PORVs are inoperable and not capable of being l manually cyclec. Condition B and its associatec RecuPed Actions would alreaay be entered. The Required Actions would either restore at least one valve within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or isolate the flow path by closing and removing the power to the associated block valves. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable, based on the small potential for challenges to the systua during s this time and provides the operator time to correct the o situation. If no PORVs are restored within the Completion

- I Time, then the unit must be brought to a MODE in which the i q%y LC0 does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 D6t within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the recuired unit conditions from full power conditions in an orcerly manner and without challenging plant systems. In l HODE 4. 5. and 6 with the ru ctor vessel head on, automatic PORV OPERABILITY may be required. See LC0 3.4.12.

' (3 U If two block valves are inoperable, it is necessary to restore at least one block valve within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The Completion Time is reasonable, based on the small potential for challenges to the system during this time and provide the operator time to correct the situation.

s G.1 and G.2 0

If the Required Actions of Condition F are not met, the unit

~ must be brought to a MODE in which the LCO does not apply.

H To achieve this status, the unit must be brought to at least Qt4 MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience. to reach the required unit conditions from full power conditions in an orderly manner and without challenging plant systems. In MODE 4. 5. and 6 with the reactor vessel head on, automatic PORV OPERABILITY may be required. .See LCO 3.4.12.

BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 7 12/7/98 Revision T

l Pressurizer PORVs f; B 3.4.11

)

! ,)

BASES l

"s l N SURVEILLANCE SR 3.4 11.1-g REQUIREMENTS s Block valve cycling verifies that the valve (s) can be opened !

O and closed if needed. The basis for the Frequency of

., l 92 days is the ACME Code.Section XI (Ref 3?

6 The Note modifies this SR by stating that it is not required H- l to be met with the block valve closed in accordance with the

@l Required Actions of this LCO. If the block valve is closed !

to isolate an inoperable PORV that is incapable of being l manually cycled, the maximum Completion Time to restore the PORV and open the block valve is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , which is well within the allowable limits (25%) to extend the block valve l Frequency of 92 days. Furthermore, these test requirements would be completed by the reopening of a recently closed block valve upon restoration of the PORV to OPERABLE status

) (i.e., completion of the Required Actions fulfills the SR).

k SR 3.4.11.2 i

?

5 SR 3.4.11.2 requires a complete cycle of each PORV; S Operating a PORV through one complete cycle ensures that the 4 PORV can be manually actuated for mitigation of an SGTR.

pg The Frequency of 18 months is based on a typical refueling Q cycle and industry accepted practice. l The Note modifies the SR to allow entry into and operation in MODE 3 prior to performing the SR. This allows the test to be performed in MODE 3 under operating temperature and ;

pressure conditions prior to entering MODE 1 or 2. In accordance with Reference 4. this test should be performed in MODE 3 or 4 to adequately simulate operating temperature and pressure effects on PORV operation.

l SR 3.4.11.3 Operating the solenoid air control valves and check valves on the air accumulators ensures the PORV control system actuates properly when called upon. The Frequency of 18 months is based on a typical refueling cycle and the Frequency of the other Surveillances used to demonstrate PORV OPERABILITY.

i BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 8 12/7/98 Revision T l'

_ . . _ _ . . . . _ _ . _ . ~ . _ _ _ . _ _ ~ - . _ -. .__ _ . . . _ . . _ .

Pressurizer PORVs B 3.4,11 BASES J

REFERENCES 1. Regulatory Guide 1.32., February 1977.

2. UFSAR, Section 15.2.

l 3. ASME. Boiler and Pressure Vessel Code. Senien XI.

4. Generic Letter 90-06. " Resolution of Generic Issue 70.

" Power Operated Relief Valve and Block Valve Reliability," and. Generic Issue 94, " Additional Low l Temperature Overpressure Protection for Light Water Reactorg"pursuantto10CFR50.54(f), June 25,1990.

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in h'I BRAIDWOOD - UNITS 1 & 2 B 3.4.11 - 9 12/7/98 Revision T l

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(3/4.4. RE IET /ALQ 3A.li Pwer operare ! FIehef VMV": IPOWO LIMITING CONDITION FOR OPERATION Lco 3.4. Moth pc,wer-operated relief valves (PORVs) and their associated block AchonsHeltI valves shall be OPERABLE. g (Insep- APPLICABILITY: MODES 1, 2, and 3. g ,. , ,, %., 4, Q 7T e ACTION: S)

- i, k

conD A +. With one or more PORV(sMinocerable Giause of exces:ive ce:: ! = k:@,

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months f ther--rectore the IORVC O L OPERACLE :tatur ej close the associated block valvels) with power maintained to tne clock g' CO N D D 3 ,

valve in HOT(s); otherwisewithin SHUTDOWN be intheat following least HOT STANDBY 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . % % p gwithin d

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 3 a)

CoND B .b. .With one PORV inoperable cdue t : ucer ether th:n excessiv: :esh l le m n6 within 1 hou 6 4ther rect ^re the Paa" t CPTn: ; m -- '

ia6closetheassociatedblockvalveandremovepowerfromtheblock@

valve; restore the PORV to OPERABLE status within e e fe!.ce g 9 COND D 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hofirs and in HOT i SHlITDOWN within the following 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months slancino+ caunae d uno rnonum cycled) t COND E es . With_both PORVs inoperableRee te crucer ether th= =cessive sat i Am 1

leMR, within I hourf tr r&re -Urset = PC'".' to 0=LE , An is"t= eB close its assoc ated block valve and remove power from '

'the b'ock valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Au g

p) COND c/F 4. .

With one or more block valves inoperab in 1 ouruesteretd ccicck .,uvet:) te C" =utt- n w 5 " place its associated PORY in '

manual control. Restore at least one block valve to OPERABLE status restore within Lim next anv remaining hour if t,uth inoperable blockblock valvevalves inre inoperable;ithin to OPERABLE status w 72 cowo.b/6 -

ho'urs; otherwise, be in at:~1 east H0i STANDBY within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sW ,

and HOT SHlfTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . l Achns Note 2 +. The provisions of Specification 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS xT m

1 M.4.4.? Q_;;ddPion t: the r:cui n nt: sf sectite: tion 4.U.:rJ e h PORV shall be demonstrated OPERABLE at least once per 18 months by:

.a. Perfer-ince of : CHA""El CALISPATION ef +ha ar +n=tinn1 E.in trementation, endi A33 dhl Ik GM AM -b. Operating solenc,id air control'and check valves on associated air l accumulators in the PORV control system through one complete cycle l of full travel, and i 2 34112. -e. 0perating the valve throuah one c lete cycle of full travel W. l

_ p = 3 ;; ". Crnser t S d-12 6 Lo se 3A.n .z No+e. l 23401 ff d A Each block valve shall be demonstrated OPERABLE at least once per "h l 92 days by operating the valve through one complete cycle of full travel \unless ;

snau,f the block valve is closed 5: th ;= r 7:=ve@in order to meet the requirements o

(Q m of ACTION b. or c. of Specification 3.4.4. g ll l

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! 8 l i l M REACTOR C00LAh" SY3 TEM (Rcs)

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g /' '.' ""L:Cr V',L":3 M.u her oproreci Rehef Valves (FORVs) 4 l

LIMITING CONDITION FOR OPERATION ,

lI

3.4.NBoth power-operated relief valves (PORVs) and their associated block Acilons Note i Valves shall be OPERABLE. l I

l PrnA ADDLICABILITY: MODES 1, 2, and 3.

l Q 4 - 120 ' ACTION: @ bM C@ UC E b" "W W Al

,' COND A 4. With one or more PORV(s) inaaerable ::::: : cr ::== c-e r:==:, '!

i within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (Pth;r r;; tere tre 70%) te 0" "XL: stet = delose 1

the associated blocx valvels) with power maintained to the b'ock ,

! coHD D valve (s); otherwise be in at least , HOT STANDBY within a ham e =ad k !

l in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .(ag;7agly of bei Co No B -b.

h l .With one PORV inoperabl y a err :: eth r +2 :n ceress w e seet- Aso d 1

i . +eekunt, within I hourWtr.x re;te.e tre 70"" t , Orc;;;d;;; ;;;t.;E A,,

D

c'ose the associated block valve and remove power from the blo'

! valve; restore the PORV to OPERABLE status within ^- *aPa"m- M6 h l ccN D D 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HDT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in KOT P

SHUTDOWN within the following 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months scamrecomw cmyn-nuo mim h '

! coHD E4. .With both PORVs inoperable Sr +- trrer eth-- the- e-reerP;: :::L Aso ,

l w . within I hour Et r rn^-.x = ::::e = "" - *- - - m y ' '

l

! 1"2 -'close its assoc < ated block valve and remove power from !

l W valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and i i in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . l coND c/F-d. ,With one or more block valves inoperabl n1 ur 6: tor: th[,

t == e.iv W te ;"E"o;;;LL ;tet= :. p ace its associated PORV in ~

manual control. Restore at least one block valve to OPERABLE status

! wiWin T.he next hour 11 Loth block viiva eiv inoperable; rutore -

i any remaining inoperable block valve to OPERABLE status within 72 j coND D/6 hours; othemise, be in et ivast HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months i~

! and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . u f Adionc Hole 2 es The provisions of Specification 3.0.4 are not applicable. ,

I ~

j SURVEILLANCE REQUIREMENTS f, m

) Caid O rdditte- te the --ert mt: :" "--4*4--+'-- Ix w ,

shall be demonstrated OPERABLE at ' east once per 18 months' by: ^' g'each PORVjj l L

j .a. 'Pe 'e = =; r4 e Oi!'"":L O'LI.""f !"" r tr.: e c rr!!en g f=tr .w ion,.=U @

G8 3.4 tl . 3 .b. Operating solenoid air control and check valves on associated air i accumulators in the PORV control system through one complete cycle of full travel, and 5 6 3 .4.11 2. +. _0perating the valve through one eggplete cycle of full trave'l GEiiER

-"EE z _-- n(2nser t 1 A -I2sWn sna.s.n 2Hskt 58 34l114"EQr) EachblockvaheshallbedemonstratedOPERABLEatheastonce 92 days by operating the va'va throuch one complete cycle of full trave _ un es m ,n.l' the block valve 15 closed it th ;U:7 7:::"J^O in order to meet the requirements -

O we lof ACTION b. or c. of Specificat<on 3.4.4.

3/4 4-12 AMENDMENT NO. 2 33 BRAIDWOOD - UNITS 1 & 2 Rev T

4 i~

CTS INSERT (S)

.L SECTION 3.4 2 .)

! LCO 3.4.11 i

, INSERT 3.4 12C !

i Deleted in Revision T '

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i l l INSERT 3.4 120 :

r ji Deleted in Revision T !

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? DISCUSSION OF CHANGES TO CTS l t- ITS SECTION 3.4 REACTOR COOLANT SYSTEM (RCS) w) ai W

$lAn Not used.

An The CTS 3.4.1.1 is revised to include a requirement for the RCS loops to l be OPERABLE. While this may seem more restrictive, it results in no !

change in operation since OPERABLE RCPs and SGs are already necessary to attain MODES 1 and 2. Therefore, this change is considered administrative in nature. This change is consistent with NUREG-1431. )

Au The Frequency for CTS 4.2.3.5 is revised from "after each fuel loading" to "18 months." Since the intent of an 18 month Frequency is to be l consistent with the length of a fuel cycle this change in terminology l is considered to be administrative in nature. This change is also '

consistent with NUREG-1431.

w

> A3 ..The: CTS. LC04A1,4.1, ActAons-a.- b -associated-footnotes r

@ SRs 4.4.1.3.3, 4.4.1.4.1.2. and 4.4.1.4.2 are revised to indicate the loops " required" to be in operation must be verified to be in operation.

The OPERABLE loops are not always " required" to be in operation since l the Notes allow de-energization for limited periods 1 l

w A3 The CTS 4.4.4.2 allowance that the block valve need not be tested if the ;

> block valve is closed with power removed in accordance with Actions b ;

@ and c requirements is revised to allow that the valve need not be tested !

O if the block valve is only closed in accordance with Required Actions.

'd Whether the power is removed does not imaact the fact that opening the valve would result in non-compliance witi Required Action A.1.

Therefore, this change is considered administrative. This change is g also consistent with NUREG-1431.

jlAn Not used.

O 8vaoa'8a^towooo uatts 1 5 2 347 12'8'98 aev4s4e" T l

4 i

DISCUSSION OF CHANGES TO CTS ITS SECTION 3.4 - REACTOR COOLANT SYSTEM (RCS)

U 4

klA3 Not used. - --

L gl An Not used.

Au CTS Action 3.4.4.a. Action 3.4.4.b. and Action 3.4.4.c refer to PORV inoperability due to " excessive seat leakage" or cue to "causes other than excessive seat leakage " Conditions A. B. and E of ITS LC0 3.4.11 h refer to the PORV being "ca able (or not capable) of being manually cycled." Excessive seat le kage is an example of PORV ino)erability

%D which does not prevent the PORV from being closed. This clange is perceived as the intent of the CTS wording, is considered editorial in nature und does not involve a technical change (either actual or interpretational) to the TS. This change is consistent with NUREG-1431. l 1

~

Au CTS LC0 3.4.1.2 Note *. LC0 3.4.1.3 Note

LC0 3.4.1.4.1 Note *. and LC0 3.4.1.4.2 Note ** specifies that the Jumps may be "de-energized."

ITS LC0 3.4.5. LCO 3.4.6. LC0 3.4.7. and _C0 3.4.8 specifies that the pumps may be removed from operation. This change is perceived as the intent of the CTS wording. is considered editorial in nature and does t

not involve a technical change (either actual or interpretational) to i the TS. This change is consistent with NUREG-1431.

\

l O 8vaoa'8a^1owooo uw11s 1 a 2 3.4 8 12 8'98 aev4s4on T

- _ . .- . - . _ - _ _ - - . = _ . - - - - . . _ -

DISCUSSION OF CHANGES TO CTS ITS SECTION 3.4 O REACTOR COOLANT SYSTEM (RCS)

LA, CTS SR 4.4.4.1.a provides a requirement for channel calibration testing of the PORV actuation instrumentation. These requirements are to be relocated to the TRM. This requirement is not necessary to ensure Operability of the PORVs in Modes 1, 2, and 3 on the basis that automatic operation is not credited in the accident analysis. The PORVs will remain capable of being manually cycled in the event of a transient. The ITS requirements for PORV operability will continue to verify the valves can be operated through one complete cycle of full F. travel. The requirements of ITS LC0 3.4.12 for LTOP and the associated

> Surveillance Requirements (i.e., SR 3.4.12.8) are adequate for ensuring the PORV actuation instrumentation can perform its intended safety

@ function. As such, the relocated requirement is not required to be in the TS to provide adequate protection of the public health and safety.

The relocation of this requirement maintains the consistency with NUREG-1431. Any change to this requirement will be made in accordance with 10 CFR 50.59.

LA, CTS Action 3.4.6.1.a contains details for performance of the action to analyze containment atmosphere (analyzed for gaseous and particulate radioactivity). These details are relocated to the ITS Bases. The action to analyze grab samples of the containment atmosphere, when the required containment atmosphere radioactivity monitor is inoperable, is maintained by ITS LCO 3.4.15 Required Action B.1.1. As a result, the

.O V

detail that grab sample be analyzed for gaseous and particulate radioactivity is not necessary to ensure the containment atmosphere is analyzed under this condition. As such, these relocated details are not required to be in the TS to provide adequate protection of the aublic i health and safety. The relocation of these details maintains t1e l consistency with NUREG-1431. Any change to these details will be made l

'in accordance with the Bases Control Program described in ITS. i Section 5.5.

LA w CTS LC0 3.4.6.2, Footnote

provides details of Pressure Isolation Valve (PIV) test performance for various unit conditions. These details are to be relocated to the ITS Bases. The requirements of ITS SR 3.4.14.1,

$ which include leakage limits stated in terms of equivalent leakage rates i

with a specified pressure range, are adequate to ensure RCS PIV leakage

+ is within required limits. As a result, the relocated details are not 7 necessary for ensuring RCS PIV leakage is within required limits and do T not need to be included in the TS to provided adequate protection of the 9 public health and safety. The relocation of these details maintains the !

H consistency with NUREG-1431. Any change to these details will be made T in accordance with the Bases Control Program described in ITS D Section 5.5.

O Bva0a Ba^10w000 uatTS 1 2 3.4 19 12'e<98 aev4s4en 1

.. . I LCO MARKUPS l O !

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Pressurizer PORVs 3.4.11 p 3.4 REACTOR COOLANT SYSTEM (RCS) l L/ 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) l 1

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE. l APPLICABILITY: MODES 1, 2 and 3.

ACTIONS

..........___.......__............._-NOTES-----------------------------------.

1. Separate Condition entry is allowed for each PORVgond each Woo. valve). !

2. LCO 3.0.4 is not applicable.

REQUIRED ACTION COMPLETION TIME A. One'or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoyerable and capable )ower to associated

-f~' of seing manually ) lock valve.

( cycled.

B. OneCor t c3 POR@ B.1 C1ose associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and no; block valv @ .

capable of being manually _ cycled. BiQ B.2 Remove power from I hour associated block

, valve @.

AjiQ B.3 Restore PORV @ to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

O WOG STS 3.4-23 Rev 1, 04/07/95 fTeV T

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1 h Pressurizer PORVs 3.4.11 l

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ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 1

C. One block valve C .1* Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i inoperable, in manual control. !

AND C.2 Restore block valve 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

l D. Required Action and 0.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A. AND B, or C not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two N PORVs E. C1 e associ ed [ hour inoperable and not ock valv .

capable of being O manually cycled. / AND E Remov power fr 1 hou I ass iated bloc l y v ves. l AND E.6i Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l 1

AND J l

E.82 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l l

Two j -

F. Ecrc th= c2 block f.1 lace as ciated hour valv@ noperable. / PORVs manual ,

contr / / {

l (continued)

(

o WOG STS 3.4-24 Rev 1. 04/07/95 ReV T

= - . . - - _ = . - - . - .- - . - - - - . . . . . - . - - . - . - - . -

Pressurizer PORVs 3.4.11 p ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F. (continued) F.@ l Restore one block 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months valve to OPERABLE statnd D f a.. W f Ill .,ck '!3lC' 2*P '

4 L "^^rr l c'J.

~

AND F.3 Restore rema 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months blo e s) to

. LE status.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition F AND not met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months r

, (.)h SURVEILLANCE REQUIREMENTS bUKVtlLLANLL FRWU SR 3.4.11.1 -------------------NOTE--------------------

Not required to be met with block valve I closed in accordance with the Required i Action of Condition B or E. l 4

i Perform a complete cycle of each block 92 days valve.

SR 3.4.11.2 Perform a complete cycle of each PORV. 118[ months Q t

P ------Nefe...--) (continued) n only required b be

(/ performect in Moors 1 WOG STS ) and 2 - - -

3.4225 Rev 1. 04/07/95 I Rev T l

Pressurizer PORVs 3.4.11

('T SURVEILLANCE RE0UIREMENTS (continued) g _

SURVEILLANCE FREQUENCY SR 3.4.11.3 Perform a complete cycle of each solenoid 31_87 months y

't .

air control valve and check valve on the Q3 air accumulators in PORV control systems.

[IS: .; .c;.2 h ofe4e

=a.ces.

D0 being Q b ock valvas are caoabla powerno _ . . -_ Pncy power O

l

i. -

i WOG STS 3.4-26 Rev 1, 04/07/95 Rev T

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JUSTIFICATION FOR DIFFERENCES TO NUREG 1431 LCOS q SECTION 3.4 - REACTOR COOLANT SYSTEM (RCS)

Pu NUREG and ITS LC0 3.4.11 allow separate condition entry for each PORV.

The Conditions and Required Actions provide appropriate compensatory measures for separate condition entry. ITS has been modified to add the abrase. " Separate Condition entry is allowed for each PORV and each alock valve." consistent with TSTF-247. In the event a PORV becomes inoperable and not capable of. being manually cycled (Condition ~ B). .the Required Action is to close the associated block vahe~ and remove power from the block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . In accordance with the Bases, once power is removed from the block valve. it is no longer OPERABLE and Condition C is also entered. Per ITS Required Action B.3 the 3 inoperable PORV is to be restor'd e within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Required Action C.2

, requires the inoperable block valve to be restored to OPERABLE (restore

- power) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In the event the second PORV becomes

'. inoperable. Required Actions require the associated block valve to be t closed and power removed from the valve. rendering it inoperable.

ta Condition B is re-entered for the second PORV. This results in 2 PORVs and 2 block valves inoperable and Condition F is entered for 2 H inoperable block valves. If the first PORV is restored to OPERABLE.

s. Condition E is exited, leaving Condition B entry for the second PORV M with the remainder of its 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months available in order to restore it to OPERABLE status. However, without separate Condition entry for the block valves, the second PORV and associated block valve must be restored to OPERABLE within the initial 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months clock of the first block valve. If the second PORV and associated block valve are not restored

~T within this initial 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Condition D is entered which requires the (V unit to be shutdown. As provided for the PORVs. the Conditions and Required Actions also provide appropriate compensatory actions for separate condition entry for eac1 block valve. Thus, the Actions Note is modified to allow separate condition entry for each block valve. In addition. Required Action E.1 and E.2 have been deleted. In the event two PORVs become inoperable. the Required Action was to close the associated block valves within I hour and remove power from the associated block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . These Required Actions are deleted since they are the same as for Condition B. Since the Actions Note allows separate Condition Entry for each PORV. Condition B would always be entered regardless of whetner one or two PORVs were inoperable. Therefore, the Required Actions E.1 and E.2 were redundant N to B.1 and B.2. Similarly. Required Action F.1 has been deleted. In the event two block valves become inoperable, the Required Action was to place the associated PORV in manual control within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . This b Required Action is deleted since it is the same as for Condition C.

> Since the Actions Note allows seaarate Condition Entry for each block g valve. Condition C would always Je entered regardless of whether one or two block valves were inoperable Therefore, the Required Action F.1 was redundant to C.1.

,) BYRON /BRAIDWOOD UNITS 1 & 2 3.4-Sa 12/6/98 Revision T

I JUSTIFICATION FOR DIFFERENCES TO NUREG 1431 LCOS SECTION 3.4 - REACTOR COOLANT SYSTEM (RCS)

P3 ITS SR 3.4.14.1 Note 1 and associated Bases were revised to clarify the requirement of the RCS PIVs. This is consistent with the use and -

application of the ITS.

Pa NUREG-1431 SR 3.4.11.4 and associated Bases were deleted. The SR verifies that the PORVs and associated block valves can be powered from a 1E source. The plant is designed with a normal power supply for the PORVs and their associated block valves from an ESF bus. Thus, no power transfer capability need be demonstrated.

YPu ITS LC0 3.4.12 and associated Bases were revised to specify an allowance Ql to operate in Mode 4 with all SI pumas and charging pumps capable of injecting into the RCS whenever all RCS cold legs exceed 330*F. This is necessary for the transition between Modes 3 and 4 since SI and charging pumps have different requirements between the two modes.

1 i

i

, l (a). BYRON /BRAIDWOOD UNITS 1 & 2 3.4 5b 12/6/98 Revision T l

1

JUSTIFICATION FOR DIFFERENCES TO NUREG 1431 LCOS r SECTION 3.4 REACTOR COOLANT SYSTEM (RCS)

( P. The references to " manual," " remote-manual." " power-operated,"

" check," and " automatic" is not consistent within the STS.

' Byron /Braidwood plant specific terminology distinguishes between the classification of valves designatti as "3ower operated" and " automatic."

Automatic valves refer to those va.ves t1at require a motive force to -

a actuate, such as air or electric, and receive an. automatic actuation -

> signal. Automatic air operated valves and automatic electric operated-O valves fall into this category. Power operated valves, on the other i

hand, require a motive force to actuate, such as air or electric, but do

% not receive an automatic actuation signal. Air power operated valves N

and electric power operated valves fall into this category. Therefore.

including the reference to " power operated" isolation valves reduces the Pi potential for misinterpreting the requirements of the Required Action, while maintaining the assumptions of the accident analysis, and is h consistent with plant s)ecific terminology. The words " closed manual or y deactivated automatic" lave been deleted from NUREG Required Action (RA) t C.1 due to those classifications of valves not being applicable to the penetrations with the RHR System suction isolation valves. With the RHR f

System suction isolation valve interlock function inoperable, ITS RA B.1 requires that the affected RHR suction penetration be isolated by at least one de-energized power operated valve. i.e., an RHR suction isolation valve.

ylPo Not used.

$P 7

2 The Actions for LC0 3.4.18 have been divided into two Conditions that are consistent with the two requirements of the LCO, a. and b. The

?

h Required Actions are similarly divided, and the Notes that were utilized to distinguish between the a)propriate Required Actions have been h eliminated. This change is )eing made to more clearly direct the

@ operating staff to the appropriate Required Action.

O svaoa'8a^1owooo uatTs 1 $ 2 3 4 1oe 12'8'98 aev4s'e" T

aA_a. _ s. e s. Asw-- as4E, _ ~ama = mamas a m +iM._ ssu. , -aue

% 4 A s ma#-.

BASES MARKUPS

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Pressurizer PORVs B 3.4.11 i

BASES l

i BACKGROUND the'PORVs minimize challenges to the pressurizer safety (continued) valves and also may be used for low temperature overpressure protection (LTOP). See LCO 3.4.12, " Low Temperature

] Overpressure Protection (LTOP) System." .,

, ; gurutJ APPLICABLE Plant operators employ the PORVs to depressurize the RCS in SAFETY ANALYSES response to certain $wd transients if normal pressurizer

, spray is not available. For the Steam Generator Tube Rupture (SGTR) event, the safety analysis assumes that manual operator actions are required to mitigate the event.

m W (2.ff->#1oss of offsite power is assumed to accompany the event, csss=WRph normal pressurizer spray is unavailable to reduce RCS pressure. The PORVs are assumed to be used for RCS depressurization, which is one of the steps performed to equalize the primary and secondary pressures in order to terminate the primary to secondary break flow and the L, i radioactive releases from the affected steam generator. >-

"ata m. deled] aef4)

The PORVs are@n safety analyses or ents that, result @

Og in increasing RCS pressure for which par ure from gucleate p foilingJatio(DNBR)criteriaarecriica.

f By assuming PORV mance1 actuation; the primary pressure remains below the high pressurizer pressore trip setpoint; thus, the DNBR l calculation

_ _ m a . 4 . ,.i,s more

..a.....m__ conse.evative.La;.;r.t:,th:t

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Pressurizer PORVs satisfy Criterion 3 of th; '"; "cli;y St:t;;;r.t .

b cmt so.36(4W)Ud.

1 LCO The LCO requires the PORVs and their associated block valves b5 to be OPERABLE for manual operation to mitigate the effects associated with an SGTR. U By maintaining two PORVs and their associated block valves i

OPERABLE, the single failure criterion is satisfied. e

-SI B e fa do P or a R e s en ae

$ Satisfying the LCO helps minimize challenges to fission product barriers.

l (continued)

WOG STS B 3.4-51 lRev 1, 04/07/9S Red T

)

BASES INSERT (S) l

-q .SECTION 3.4 l

L) >

Bases 3.4.11 i l INSERT B 3.4 51A (Ca ) _

l

! As such, this actuation is not required to mitigate these events, and PORV

.l automatic operation is, therefore, not an assumed safety function.

1 l

d l--INSERT B 3.4 51B (Cn)-

An OPERABLE block valve may be either open, or closed and energized with the capability to be opened, since the required safety function is accomplished by !

manual operation. Although typically open to allow PORV o mration, the block valves may be OPERABLE when closed to isolate the flow pati of an inoperable l PORV that is capable of being manually cycled -(e.g. as in the case of- ,

excessive PORV leakage). Similarly, isolation of an OPERABLE PORV does not '

render that PORV or block valve inoperable provided the~ relief function l remains available with manual action.

l An OP5RABLE PORV is required to be capable of manually opening and closing.

' O and not experiencing excessive seat leakage. Excessive seat leakage, although

V 'not associated with a specific acceptance criteria, exists when conditions dictate closure of the block valve to limit leakage.

i INSERT B 3.4 51C Deleted in Revision T.-

I 1RSERT B 3.4 51D I Deleted in Revision.T.

( 12/7/98 Revision T i

l

Pressurizer PORVs j B 3.4.11 BASES(continued)

APPLICABILITY In MODES 1, 2, and 3, the PORY and its block valve are l required to be OPERABLE to limit the potential for a small ;

break LOCA through the flow path. The most likely cause for l 3 a PORV small break LOCA is a result of a pressure increase l

'h . huhaM*4 transient inat causes Ine runv toepen. Imbalances in the energy output of tne core an:i heat removal by the sec::ncary system can cause the RCS pressure to increase to the PORV opening setpoint. The most rapid increases will occur at the higher operating power and pressure conditions of

MODES 1 and 2. The PORVs are also required to be OPERABLE b in MODES 1, 2, and 3 t: =i-t:i:: :h:ll:r.;:: t: th:

i

.....4..,.

.<.n, 83'd Pressure increases are less prominent in MODE 3 because the core input energy is reduced, but the RCS pressure is hich.

Therefore, the LCO is applicable in MODES 1, 2, ard 3. The

/' 5 ' " 6' 'i gh LCD 1s not applicaDie in riuut 9Mahen both pressure and core energy are decreased and the pressure surges become much.

m.: " = :: n nt i: r d :d ' . . ' Cl i n I '. n MODE,i A late eionificant ,noots 41. anadwith the reactor vermal head in ILCO 3.4.72 addresses the PORV requirements)RE"31EEAEERQ d

( oad bloce. wivesh l An ACTICW).

\ ACTIONS L-* Note 7 has been added to clarify that all pressurizer PORVs & s are treated as separate entities, each with separate

Completion Times (i.e., the Completion Time is on a 3 component basis). The exception for LCO 3.0.4, Note 2, 8 permits entry into MODES 1, 2, and 3 to perform cycling of the PORVs or block valves to verify their OPERABLE status, Qgg Testing is not performed in lower MODES. tg b.

U 'f w be.] suma4ed]

/(..S. , e nuse. 4.e4 )

"ith the PORVs inoperable and / capable of being manuallyJs cycle 4either the PORVs mus be restored or the m ow path

(\co.iew l'"b'Pi * " butI isolat d within I hour. Th block valvet eheeW rbe closed power must be maintained to the associated block valves, since removal of power would render the block valve _

inoperable. lAlthough a PORV may be designated i e, p i fu . bl e to be manually opened an , and therefore, a form it on. PORY inoperabilitr may be due to seat 1 , ntation problems, automatic problems, or other c do not anual use and do not create a possibility ,

(continued) ,

WOG STS B 3.4-52 -Rev1,04/07/95-EeV T

+ - /C e

F

l. BASES INSERT (S) a SECTION 3.4 g

! . i I

Bases 3.4.11

+

.) INSERT B 3.4a52A .(Cg )

} - for manu'al actuation to mitigate a steam generator tube ru?ture event. f

',. + ,

..s-

4. .-

e a

Y, L

5 O .

l s.

l l

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,I

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12/7/98 Revision'T l

+

.wr,-.w,- -,.~e..w----n.--- - - - - - - . . - > . - . ---.---~-~-,w-.---,ama.--- ..+w,.m.. - . .~-e.. e- ,,mw -rw <.e- -,, .,,-r-1 en-- vwv.

)

1 Pressurizer PORVs i B 3.4.11 BASES i

ACTIONS L.1 (continued) i l- '

1 C s.;11 br::i LOCf.

_,- a u.. m F:r th::: re:::n:, the bleek ":he =y be g

g. W x p e h nu M M k d ;e. This C:r.iiti:n i: c n a ,, inten:::d to- permiGyoperation i

Q(Gea unbl> of the th t f:r ; li:ited p;ri;d ;f ti;; n;t t; used the next refueling outage (NODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition.

Oc n "m m.11.,, the P0ra'; ;h;;1d b; :=f hbi: f:r =te=at4e-- p miti;;ti= :f :=r;r==r: := t: : d :h=1d 5: ret.arn:d t: >

OP P,f.0L :t:t;; pri;r t; crt;rinii :t;rtup ("00: 2). g i

Quick access to the PORV for pressure control can be made when power remains on the closed block valve. The Completion Time of I hour is based on plant operating experience that has shown that minor problems can be '

corrected or closure accomplished in this time period.

B.1. B.2. and B.3 If one nr ,. ;; PORV@ 'is inoperable and not ca ble of f- l f @

being manua'ly cycled, it must be either restor r I > 1 isolated by closing the associated block valve an removing [

the power to the associated block valve. The Completion '

Times of I hour are reasonable, based on challenges to the I PORVs during this time period, and provide the operator ,

adequate time to correct the situation. If the inoperable valve, cannot be restored to OPERABLE status, it-mait be isolated within the specified time. Because there is at-least one PORY that remains OPERABLE, :: rdditi;c.a; 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

,, , is provided to restore the inoperable PORV to OPERABLE status. If the PORV cannot be restored within this h :dditi n:.1 time,.the p ent must be brought to a MODE in which the LCO does not" apply, as required by Condition D.' 'b

[EnZ ' >

w C.1 and C.2 E If one block valve is inoperable, then it is necessary to

' either restore the block valve to OPERABLE status within the Completion Time of I hour or place the associated PORV in manual control. The prime importance for the capability to close the block valve is to isolate a stuck open PORV.

Therefore, if the block valve cannot be restored to OPERABLE (continued)

WOG STS B 3.4-5L Rev:1,-04/01/.91 f.av T

BASES INSERT (S)

SECTION 3.4 Bases 3.4.11 i

INSERT B 3.4 53A i Deleted in Revision T.

J 1

1 0

d f

4 0

12/7/98 Revision T

1 Pressurizer PORVs

, , B 3.4.11 3

' BASES LO ACTIONS C.1 and C.2 (continued o O. , d.6eJ U status within I hour, the Required Action is to place the l

h PORV in manual control to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck a

' coen FORV at a time that tne clock valve is incoerable. The Completion Time of I hour is reasonaole, based on the small potential for challenges to the system during this time b period, and provides the operator time to correct the 'y

, situation.(tBecause at least one PORV remains OPERABLE, the g ,

' iT%e inopvalle.brestore operator theisinoperablie permitted a Completion block valve to OPERABLE Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months status...to The time allowed to restore the block valve is based upon the i 3 bha.

no& -r.ilvalve.n) pen Completion Time for restoring an inoperable PORV in rlmw no+ bg,

NCondition B, since the PORVs acemetscapable of mitigating i an: =gr;;;.c; eventtt= ;hrd ir :==' retr:L If the Y g

block valve is restored within the Completion Time of '

, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the power will be restored and the PORV. restored

[T,nced to OPERABLE stattrs. If it cannot be restored within this ). '

l

. g y ,4.g A h additional time... the$$Egh.must be brought to a MODE in whichtheLCOdoesnot[ apply,asrequiredbyConditionD. g s

Geit)

D.1 and D.2 %

i A i

p .If the Required [ Action of Condition A, B, or C is not met, :::

i then the plen Vmust be brought to a MODE in which the LCO +

i does not apply. To achieve this status, the 9 wih l brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months anc%x"'must E4 be i within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are @1 $$ 4 reasonable, based on operating experience, to reach the

! required plant conditions from full power conditions in an -

j orderly manner and without challenging plant systems. In b I

h h See LCO 3.4.12.MODEJ av+e4 =%.)

anakk ="t:i-'r;; PORV OPERA 1

I w & ou.

Ih L.aA fd E .1.,

M M C'*W

! ~.wo Fbus A b mo [Clb d h E d b W IWJ".k i

h If r re the er P09" 3: inopedie ana not capable or oeing manually cycled, it i.; :=rmNeither restore at least p

. one valve within the Completion Time of I hour or isolate .,,

the flow path by closing and removing the power to the {

l- -

associated block valves. The Completion Time of I hour is reasonable, based on the small potential for challenges to j the system during this time and provides the operator time (

i 3

(continued) tO WOG STS B 3.4-54 Rev-1, 04/07/95 l hT

Pressurizer PORVs B 3.4.11

. \

BASES E .1, ACTIONS MD E (continued) to correct the situation. If ::: "0"3 i: ruta ed end una b-j-

C, P0"" r ::i : S:;:r:ble, tM, th: ;;hnt will b: ir ?

Snditi:n r eitt th: tim: :loek-star d :: th -criginal- 2 1 i

... ... ..i:n :f hn 't; tre [:r thrt:] POP >!: ine?:r:ble. If no PORVs are restored within the Completion Time, then the a ghnt must be brought to a MODE in which the LCO does not apply. To achieve this status, the';::n Imust be brought to !

5 i-i at least ODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within 'M 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, #2 i

i based on operating experience, to reach the required q 3d conditions from full power conditions in an orderly manner i; @ and without challenging' plant systems. In MOD 4 end4; d

' :: int:f =";1PORY OPERABILITY may be required. See b.

i @. LCO 3.4.12. M E. g i

f, fu t.u:SD lN$rf4- ]M F.1y_r._. .__

enu r 3 (Nle=I*m**$9 j ,

If pere t i ere block valv@ie hinoperable, it is necessary y j t

' ,1pu rI hour, restore In DioCK Valves W in Ine bump i 1me or ace the actoci ed PORVs in m

! anty 1 andirestore at least one block valve w

[end re;;;r: th: r;;; inia; bh :h /: h : ritM - ??thin 2 'houQ' Seur The Completion Time potential for challe)SEi!Elreasonable, based )

i nges to the system during this on timethe smali.

and j provide t!)e operator time 4

correct the situation 3 is -

G.1 and G.2 5

If the Required Actions.of Condition F a not met, en the e

" Q WEEEFaust be brought to a MODE in which he LCO does not apply. To achieve this status, thelnlmaW aust be brought to 4 i

!' at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 within I*

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .t The allowed Completion Times are reasonable 9, m" " based on operating experience, to reach the required M, 4

conditions from full power conditions in an orderly manner

PMB -

and without challenging plant systems. ,',Ih MODEJf 4 and Cr-- p

--i-t ! i ; ORV n OPERABILITY may be required. See > l LCO 3.4.12. %ag E

s. c i l 'u.A L O y 9 ,, w ,

1

) (continued)

- WOG STS B 3.4-55 Revr l,-04/07]95 i

te.v T

I-Pressurizer PORVs i B 3.4.11 l

. BAS:S (continued)-

SURVEILLANCE SR 3.4.11.1 REQUIREMENTS Gerad ed) L Q

dV Block valve cycling verifies that the valve (s) can be+ closed if needed. The basis for the Frequency of 92 days is the l?E ASME Code,Section XI (Ref. 3). [If the block vaiv i e . 1solate a ruxv Inat is ca .' ing manually l O

cycled, the ock valve is of importance, Y."/

. because ock va ar to permit used for manual control of reac o __a - 41f I-1 the block valve is closed to isolate an 44mHE238 inoperable >

'tratiwicaeW " PORW the maximum Completion Time to restore the PORV and $

j

! L of CyCben lCd , tmdy] open the block all0wable limitsvalve (25%)isto72extend hours,thewhich blockisvalvewell Frequency within the of 92 days. Furthermore, these test requirements would be

. completed by the reopening of a recently closed block valve upon restoration of the PORV to OPERABLE status (i.e.,

completion of the Required Actions fulfills the SR).

The Note.. modifies this-SR by stating that it is not required I /g <

to be met with the ock valve close in accordance with f tthe Required Actio f this LCO.

I-SR 3.4.11.2 , 4 J SR 3.4.11.2 requires a complete cycle of each PORV.

Operating a PORV through one complete cycle ensures that the l-PORY can be manually actuated for mitigation of an SGTR4 -

%d"Ef The Frequency ofM18kmonths is based on a typical refueling E 33,4- s1, A cycle and industry accepted practice.

NThe Alofej

. SR 3.4.11.3 Operating the solenoid air control valves and check valves

! on the air accumulators ensures the PORY control system Q actuates properly when called upon. The Frequency of W l

/,M18Tmonths is based on a typical refueling cycle and the l Frequency of the other Surveillances used to demonstrate PORY OPERABILITY. l l

h SR 3. . -

h This Surveillan gpr .upp. ies to the valves.

require ts with permanent-

_ g d

- b (continued)

O 2 WOG STS B 3.4-56 Rev-1,04/07/95 ku T .

1

.- . - .- . . - - . , . _ -. . - -- - .- ,, l

BASES INSERT (S)

SECTION 3.4 y

~

? Bases 3.4.11 V

q l INSERT B 3.4 56A (Pu )

h 3 l Theperforming Note modifies the SR.the This SR to allowtheentry test intoto beand operation in MODE 3 prior to

" allows performed in MODE 3 unaer operating temperature and pressure conditions prior to entering MODE 1 or 2.

. In accordance with Reference 4, this test should be performed in HODE 3 or 4 to adequately simulate operating temperature and pressure effects on PORV operatioi; INSERT B 3.4 568 Deleted in Revision T.

1 1

I 12/7/98 Revision T i

Pressurizer PORVs B 3.4.11 BASES '

SURVEILLANCE .11.4 -

REQUIREMENTS The Surveillance N (continued) ates tha ency power can be

% provided and is performe to emergency su

, ansferring power from normal cycling tae7 atves The Frequency pt r c 1 e.

RE[ERENCES -

1. Regulatory Guide 1.32, February 1977.

h 2. h AR, Section9 15.2 [

3. ASME, Boiler and Pressure Vessel Code,Section XI.

b 1

.B e

R Gw.E Wo. 9od, *Res.hk .( Gw rug ro, ' P,w o,m es,5vs. a w.*va- vaa%,w 0 G Gw<.Ju % % A .kJ L o -T*& Wu-u.m a tym: w w ~,o3; \j(.

(%L 2 5, M90, 9

4 WOG STS B 3.4-57 . Rey 1704/07/95 kJ T

i I

d.

1 i

BASES JFDS o

t a

'f S.

, . .; , 7.2 _ .-

Y a

f 1-

.i

'I i

i I

!, . E, =

1 r

3 .

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d i

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J il .

1

)

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i

o JUSTIFICATION FOR DIFFERENCES TO NUREG 1431 BASES SECTION 3.4 REACTOR COOLANT SYSTEM (RCS)

J Pg Details of the type of analyses required to be performed on grab samples 5 of containment atmosphere have been added to the Bases for ITS 3.4.15.

q Action B. The additional words are consistent with the relocation of g the existing requirements from the CTS 3/4.4.6.1 Action a. and is A consistent with the existing licensing basis of the facility.

lP g hot used.

P2 ITS SR 3.4.11.2 Note (and Bases) is added to provide an allowance for the PORV cycling to be deferred until reaching (prior to entering)

MODE 2 (note that the requirement stating "only required to be performed in MODES 1 and 2" has the effect of allowing the performance to be .

deferred when not in MODES 1 and 2). This is essentially consistent with the CTS requirement to aerform the cycling during MODE 3 or 4.

Since the Applicability for 30RV OPERABILITY is MODES 1. 2. and 3. ITS convention would not normally specify requirements for MODE 4 (outside of the Applicability). Therefore, given normal ITS conventions, and the

, CTS requirements, this ITS Note to SR 3.4.11.2 is based on CLB.

9

' P2 The Actions for LCO 3.4.18 have been divided into two Conditions that are consistent with the two requirements of the LCO, a. and b. The Required Actions are similarly divided, and the Notes that were utilized N to distinguish between the a3propriate Required Actions have been H eliminated. This change is aeing made to more clearly direct the 4 operating staff to the appropriate Required Action.

Pu The Bases for NUREG LCO 3.4.18 Actions A.1 and B.1 have been modified to comply with NUREG LCO deleting the Note for both Required Action A.1 and B.1.

BYRON /BRAIDWOOD UNITS 1 & 2 3.4 12a 12/7/98 Revision T

i i

i ENCLOSURE 2

O ITS REVISION T ITS SECTION 3.7 l

4 i

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(

BYRON AMENDMENT 106 T

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Figure 3.7.16-2 (page 1 of 1)

Region 2 3-out-of-4 Checkerboard Configuration Burnup Credit Requirements O,

L BYRON - UNITS 1 & 2 3.7.16-4 Amendment 106

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Figure 3.7.16-3 (page 1 of 1)

Region 2 2-out-of-4 Checkerboard Configuration Burnup Credit Requirements

\

-BYRON - UNITS 1 & 2 3.7.16-5 Amendment 106

SX System B 3.7.8 B 3.7 PLANT SYSTEMS f3 )

l

')

B 3.7.8 Essential Service Water (SX) System

\

I l

BASES l

BACKGROUND The SX System provides a heat sink for tr.e removal o, process and operating heat from safety related components l l

during a Design Basis Accident (DBA) or transient. During l normal operation. and a normal shutdown, the SX System also i provides this function for various safety related and nonsafety related components. The safety related function is covered by this LCO.

1 The unit-specific SX System consists of two separate, electrically independent. 100% capacity, safety related, cooling water trains. Each train consists of a 100%

capacity pump, piping, valving, and instrumentation. The pumps and valves are remote and manually aligned. except in the unlikely event of a Loss Of Coolant Accident (LOCA).

The pumps are automatically started upon receipt of a safety injection signal or an undervoltage on the ESF bus, and all essential valves are aligned to their post accident positions (Diesel Generator (DG) supply valves are opened p) u once the DG has reached sufficient rpm). The SX System is the backup water supply to the Auxiliary Feedwater System.

The SX System includes provisions to crosstie the trains (unit-specific crosstie), as well as provisions to crosstie the units (opposite-unit crosstie). The opposite-unit crosstie valves (1SX005 and 2SX005) must both be open to accomplish the opposite-unit crosstie. The system is normally aligned with the unit-specific crosstie valves open and the opposite-unit crosstie valves closed.

Additional information about the design and operation of the SX System, along with a list of the com)onents served, is presented in the UFSAR. Section 9.2.1 (Ref. 1). Some of the functions served by the SX System are the removal of decay heat from the reactor via the Component Cooling Water (CC)

System, the removal of heat from containment via the reactor containment fan coolers and cooling of the DGs.

l BYRON - UNITS 1 & 2 B 3.7.8 - 1 Amendment 106

BRAIDWOOD AMENDMENT 98 O

9 O

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Spent Fuel Assembly Storage 3 7.16 r3 45000 9 - - . _ _ _ . - - . . . . . _ . - - . . . _ - -

DECAY

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TIME'

-40000 o 0 YEARS

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Region 2 3-out-of-4 Checkerboard Configuration Burnup Credit Requirements

,m

(

BRAIDWOOD - UN!.TS 1 & 2 3.7.16-4 Amendment 98

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4.0 4.2 4.4 4.6 4.8 5.0 INITIAL U-235 ENRICHMENT (w/o)

Figure 3.7.16-3 (page 1 of 1)

Region 2 2-out-of-4 Checkerboard Configuration Burnup Credit Requirements BRAIDWOOD - UNITS 1 & 2- 3.7.16-5 Amendment 98

SX System !

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B 3.7 PLANT SYSTEMS B 3.7.8 Essential Service Water (SX) System !

I BASES 1

BACKGROUND The SX System provides a heat sink for the removal of l process and operating heat frca safety related components l during a Design Basis Accident (DBA) or transient. During l normal operation, and a normal shutdown, the SX System also l provides this function for various safety related and ;

nonsafety related components. The safety related function l is covered by this LCO. l The unit-specific SX System consists of two separate.

electrically independent.100% capacity, safety related. l cooling water trains. Each train consists of a 100%

capacity pump, piping, valving, and instrumentation. The pumps and valves are remote and manually aligned, except in ;

the unlikely event of a Loss Of Coolant Accident (LOCA). '

The pumps are automatically started upon receipt of a safety injection signal or an undervoltage on the ESF bus, and all essential valves are aligned to their post accident positions (Diesel Generator (DG) supply valves are opened once the DG has reached sufficient rpm). The SX System is O)

(, the backup water supply to the Auxiliary Feedwater System.

The SX System includes provisions to crosstie the trains (unit-specific crosstie), as well as provisions to crosstie the units (opposite-unit crosstie). The opposite-unit crosstie valves (ISX005 and 2SX005) must both be open to accomplish the opposite-unit crosstie. The system is normally aligned with the unit-specific crosstie valves open and the opposite-unit crosstie valves closed.

Additional information about the design and operation of the SX System, along with a list of the com)onents served, is presented in the UFSAR, Section 9.2.1 (lef. 1). Some of the functions served by the SX System are the removal of decay heat from the reactor via the Component Cooling Water (CC)

System, the removal of heat from containment via the reactor containment fan coolers, and cooling of the DGs.

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BRAIDWOOD - UNITS 1 & 2 B 3.7.8 - 1 Amendment 98

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5 Figure 3.7.16-2 (page 1 of 1)

.@l Region 2 3-out-of-4 Checkerboard Configuration Burnup Credit Requirements 7

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4 l BYRON - UNITS 1 & 2 3.7.16-4 12/10/98 Revision T i

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, b h Figure 3.7.16-3 (page 1 of 1)

$l Region 2 2-out-of-4 Checkerboard Configuration Burnup Credit Requirements

'N (O %

3.7.16-5 12/10/98 Revision T kl BYRON-UNITS 1&2

SX System B 3.7.8 qg B 3.7 PLANT SYSTEMS 3

k l B 3.7.8 Essential Service Water (SX) System BASES BACXGROUND The SX System provides a heat sink for the removal of process and operating heat from safety related components during a Design Basis Accident (DBA) or transient. During normal operation and a normal shutdown the SX System also provides this function for various safety related and nonsafety related components. The safety related function is covered by this LCO.

R The unit-specific SX System consists of two separate.

3 electrically independent.100% capacity, safety related, g cooling water trains. Each train consists of a 100%

capacity pum.p piping, valving, and instrumentation. The pumps and valves are remote and manually aligned except in the unlikely event of a Loss Of Coolant Accident (LOCA).

The pumps are automatically started upon receipt of a safety injection signal or an undervoltage on the ESF bus, and all essential valves are aligned to their post accident positions (Diesel Generator (DG) supply valves are opened (N once the DG has reached sufficient rpm). The SX System is V the backup water supply to the Auxiliary Feedwater System.

The SX System includes provisions to crosstie the trains (unit-specific crosstie), as well as provisions to crosstie the units (opposite-unit crosstie). The opposite-unit crosstie valves (1SX005 and 2SX005) must both be open to accomplish the opposite-unit crosstie. The system is normally aligned with the unit-specific crosstie valves open and the opposite-unit crosstie valves closed.

Additional information about the design and operation of the SX System, along with a list of the com)onents served, is presented in the UFSAR. Section 9.2.1 (lef.1). Some of the functions served by the SX System are the removal of decay heat from the reactor via the Component Cooling Water (CC)

System the removal of heat from containment via the reactor containment fan coolers, and cooling of the DGs.

p d

BYRON - UNITS 1 & 2 B 3.7.8 - 1 12/10/98 Revision T

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( j. Region 2 3-out-of-4 Checkerboard Configuration-Burnup Credit Requirements n

(v)%s c@lBRAIDWOOD-UNITS 1&2 3.7.16-4 12/10/98 Revision T

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.k Figure 3.7.16-3 (page 1 of 1)

Ul Region 2 2-out-of-4 Checkerboard Configuration Burnup Credit Requirements j O

xJ%

D 3.7.16-5 12/10/98 Revision T

% l BRAIDWOOD - UNITS 1 & 2

SX System B 3.7.8 pb B 3.7 PLANT SYSTEMS l

l B 3.7.8 Essential Service Water (SX) System BASES l

BACKGROUND The SX System provides a heat sink for the removal of ;

process and operating heat 1 rom safety related components '

during a Design Basis Accident (DBA) or transient. During normal operation, and a normal shutdown, the SX System also provides this function for various safety related and nonsafety related components. The safety related function is covered by this LCO.

2 The unit-specific SX System consists of two separate, 3 electrically independent,100% capacity, safety related, u cooling water trains. Each train consists of a 100%

4- capacity pump, piping, valving, and instrumentation. The pumps and valves are remote and manually aligned, except in the unlikely event of a Loss Of Coolant Accident (LOCA).

The pumps are automatically started upon receipt of a safety injection signal or an undervoltage on the ESF bus, and all essential valves are aligned to their post accident p.

d positions (Diesel Generator (DG) supply valves are opened once the DG has reached sufficient rpm). The SX System is the backup water supply to the Auxiliary Feedwater System.

The SX System includes provisions to crosstie the trains (unit-specific crosstie), as well as provisions to crosstie the units (opposite-unit crosstie). The opposite-unit crosstie valves (ISX005 and 2SX005) must both be open to accomplish the opposite-unit crosstie. The system is normally aligned with the unit-specific crosstie valves open and the opposite-unit crosstie valves closed.

Additional information about the design and operation of the SX System, along with a list of the com)onents served, is presented in the UFSAR. Section 9.2.1 (Ref.1). Some of the l functions served by the SX Sy. stem are the removal of decay

. heat from the reactor via the Component Cooling Water (CC)

System, the removal of heat f'om containment via the reactor containment fan coolers, and cooling of the DGs.

BRAIDWOOD - UNITS 1 & 2 B 3.7.8 - 1 12/10/98 Revisic:,T

1 1

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~t LCO 3.7.16 1 INSERT 3.7-39A (continued) (P,) !

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['i l 12/7/98 Revision T U

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