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1 INSERT THIS PAGEIN FRONT OF VOLUME 6 Volume 6 SECTION 3.5 Remove Replace 3.5.1 ITS pg 3.5-3 Rev 0 3.5.1 ITS pg 3.5-3 Rev 7 3.5.1 ITS pg 3.5-4 Rev 0 3.5.1 ITS pg 3.5-4 Rev 7 3.5.1 ITS pg 3.5-5 Rev 0 3.5.1 ITS pg 3.5-5 Rev 7 3.5.1 ITS pg 3.5-6 Rev 0 3.5.1 ITS pg 3.5-6 Rev 7 3.5.1 ITS pg 3.5-7 Rev 0 3.5.1 ITS pg 3.5-7 Rev 7 3.5.1 ITS pg 3.5-8 Rev 0 -- | |||
B3.5.1 ITS pg B 3.5.1-3 Rev 0 B3.5.1 ITS pg B 3.5.1-3 Rev 7 B3.5.1 ITS pg B 3.5.19 Rev 0 B3.5.1 ITS pg B 3.5.1-9 Rev 7 B3.5.1 ITS pg B 3.5.1-11 Rev 0 B3.5.1 ITS pg B 3.5.1-11 Rev 7 B3.5.1 ITS pg B 3.5.1-13 Rev 0 B3.5.1 ITS pg B 3.5.1 13 Rev 7 B3.5.1 ITS pg B 3.5.1-17 Rev 0 B3.5.1 ITS pg B 3.5.1-17 Rev 7 3.5.1 CTS M/U (3/4 3-23) pg 1 of 10 3.5.1 CTS M/U (3/4 3-23) pg i of 10 Rev 7 3.5.1 CTS M/U (3/4 4-2) pg 2 of 10 3.5.1 CTS M/U (3/4 4-2) pg 2 of 10 Rev 7 3.5.1 CTS M/U (3/4 5-3) pg 5 of 10 3.5.1 CTS M/U (3/4 5 3) pg 5 of 10 Rev 7 3.5.1 CTS hW (3/4.7-3) pg 8 of 10 3.5.1 CTS M/U (3/4 7-3) pg 8 of 10 Rev 7 3.5.1 DOCS pg 6 Rev 0 3.5.1 DOCS pg 6 Rev 7 3.5.1 DOCS pg 7 Rev .0 3.5.1 DOCS pg 7 Rev 7 3.5.1 DOCS pg 8 Rev 0 3.5.1 DOCS pg 8 Rev 7 3.5.1 DOCS pg 9 Rev 0 3.5.1 DOCS pg 9 Rev 7 3.5.1 DOCS pg 10 Rev 0 3.5.1 DOCS pg 10 Rev 7 3.5.1 DOCS pg 11 Rev 0 3.5.1 DOCS pg 11 Rev 7 j 3.5.1 DOCS pg 12 Rev 0 3.5.1 DOCS pg 12 Rev 7 3.5.1 NUREG M/U pg 3.5-2 3.5.1 NUREG M/U pg 3.5-2 Rev 7 3.5.1 NUREG M/U pg 3.5-3 3.5.1 NUREG M/U pg 3.5-3 Rev 7 3.5.1 NUREG M/U pg 3.5-4 (insert) Rev 0 3.5.1 NUREG M/U pg 3.5-4 (insert) Rev 7 3.5.1 NUREG M/U pg 3.5-5 3.5.1 NUREG M/U pg 3.5-5 Rev 7 B3.5.1 NUREG M/U pg B3.5-3 B3.5.1 NUREG M/U pg B3.5-3 Rev 7 B3.5.1 NUREG hW pg B3.5-8 B3.5.1 NUREG hW pg B3.5-8 Rev 7 ' | |||
B3.5.1 NUREG M/U pg B3.5 9 (insert) Rev 0 B3.5.1 NUREG M/U pg B3.5-9 (insert) Rev 7 B3.5.1 NUREG M/U pg B3.5-11 B3.5.1 NUREG M/U pg B3.5-11 Rev 7 | |||
! B3.5.1 NUREG hW pg B3.5-12 B3.5.1 NUREG hW pg B3.5-12 rev 7 B3.5.1 NUREG M/U pg B3.5-15 B3.5.1 NUREG M/U pg B3.5-15 Rev 7 9906290213 990624 PDR ADOCK 05000341 _ | |||
P PDR Rev 7 06/18/99 m | |||
t Volume 6 SECTION 3.5 (cont'd) . | |||
Remove Replace 3.5.1 JFD's pg 2 Rev 0 3.5.1 JFD's pg 2 Rev 7 3.5.1 JFD's pg 3 Rev 0 3.5.1 JFD's pg 3 Rev 7 3.5.1 NSHC pg 10 Rev 0 3.5.1 NSHC pg 10 Rev 7 3.5.2 ITS pg 3.5-8 Rev 7 3.5.2 ITS pg 33 9 Rev 0 3.5.2 ITS pg 3.5-9 Rev 7 3.5.2 ITS pg 3.5 10 Rev 0 3.5.2 ITS pg 3.5-10 Rev 7 3.5.2 ITS pg 3.5-11 Rev 0 3.5.2 ITS pg 3.5-11 Rev 7 3.5.2 ITS pg 3.5-12 Rev 0 - | |||
B3.5.2 ITS pg B 3.5.2-4 Rev 0 B3.5.2 ITS pg B 3.5.2-4 Rev 7 B3.5.2 ITS pg B 3.5.2-5 Rev 0 B3.5.2 ITS pg B 3.5.2-5 Rev 7 B3.5.2 ITS pg B 3.5.2-6 Rev 0 B3.5.2 ITS pg B 3.5.2-6 Rev 7 3.5.2 GS M/U (3/4 5-3) pg 1 of 8 3.5.2 GS M/U (3/4 5-3) pg 1 of 8 Rev 7 3.5.2 CTS M/U (3/4 5-4) pg 2 of 8 3.5.2 GS M/U (3/4 5-4) pg 2 of 8 Rev 7 3.5.2 CTS M/U (3/4 5-6) pg 3 of 8 3.5.2 CS M/U (3/4 5-6) pg 3 of 8 Rev 7 3.5.2 CTS M/U (3/4 5-8) pg 5 of 8 3.5.2 CS M/U (3/4 5-8) pg 5 of 8 Rev 7 3.5.2 CTS M/U (3/4 8-15a) pg 8 of 8 3.5.2 GS M/U (3/4 8-15a) pg 8 of 8 Rev 7 3.5.2 DOCS pg 2 Rev 0 3.5.2 DOCS pg 2 Rev 7 3.5.2 DOCS pg 3 Rev 1 3.5.2 DOCS pg 3 Rev 7 3.5.2 DOCS pg 4 Rev 0 3.5.2 DOCS pg 4 Rev 7 3.5.2 DOCS pg 5 Rev 0 3.5.2 DOCS pg 5 Rev 7 3.5.2 DOCS pg 6 Rev 0 3.5.2 DOCS pg 6 Rev 7 3.5.2 DOCS pg 7 Rev 0 3.5.2 DOCS pg 7 Rev 7 3.5.2 DOCS pg 8 Rev 0 3.5.2 DOCS pg 8 Rev 7 l 3.5.2 DOCS pg 9 Rev 7 3.5.2 NUREG M/U pg 3.5-9 3.5.2 NUREG M/U pg 3.5-9 Rev 7 3.5.2 NUREG M/U pg 3.5-9 (insen) Rev 0 3.5.2 NUREG M/U pg 3.5-9 (insen) Rev 7 3.5.2 NUREG M/U pg 3.5-10 3.5.2 NUREG M/U pg 3.510 Rev 7 3.5.2 NUREG M/U pg 3.5-20 3.5.2 NUREG M/U pg 3.5-20 Rev 7 { | |||
3.5.2 NUREG M/U pg 3.5-21 3.5.2 NUREG M/U pg 3.5 21 Rev 7 3.5.2 NUREG M/U pg 3.5-21 (insen) Rev 0 3.5.2 NUREG M/U pg 3.5-21 (insen) Rev 7 f | |||
3.5.2 NUREG M/U pg 3.5-22 3.5.2 NUREG M/U pg 3.5-22 Rev 7 3.5.2 JFD's pg i Rev 0 3.5.2 JFD's pg i Rev 7 ; | |||
3.5.2 NSHC pg 3 Rev 7 l | |||
l Rev 7 06/18/99 a | |||
i Volunae 6 SECTION 3.5 (cont'd) | |||
Reasove Replace 3.5.2 NSHC pg 4 Rev 7 3.5.2 NSHC pg 5 Rev 7 3.5.2 NSHC pg 6 Rev 7 3.5.3 ITS pg 3.5-12 Rev 7 3.5.3 ITS pg 3.5-13 Rev 0 3.5.3 ITS pg 3.5-13 Rev.7 3.5.3 ITS pg 3.5-14 Rev 0 3.5.3 ITS pg 3.5-14 Rev 7 l 3.5.3 ITS pg 3.5-15 Rev 0 -- | |||
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i l \ | |||
i i | |||
l Rev7 06/18/99 | |||
(_ | |||
1 ECCS-Operating 3.5.1 1 | |||
ACTIONS (continued) I CONDITION REQUIRED ACTION COMPLETION TIME H. One ADS valve H.1 Restore ADS valve to 72 hours inoperable. OPERABLE status. | |||
AND @ | |||
D Condition A or H.2 Restore .cw pressure 72 hours 4 Condition B entered. ECCS injection / spray 4 subsystem (s) to OPERABLE status. | |||
I. Two or more ADS valves I.1 Be in MODE 3. 12 hours inoperable. | |||
AND 2 | |||
I.2 Reduce reactor steam 36 hours Required Action and come pressure to associated Completion s 150 psig. | |||
Time of Condition E, F. G or H not met. | |||
I J. Two or more low J.1 Enter LC0 3.0.3. Immediately 1 pressure ECCS injection / spray subsystems ino>erable for reasons otler than Condition B or C. | |||
2 HPCI System and one or more ADS valves p inoperable. | |||
& 5 Condition C and Condition G entered. | |||
_l FERMI - UNIT 2' 3.5 3 Revision 7 06/18/99 | |||
) | |||
ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify correct voltage and breaker 7 days i alignment to the LPCI swing bus. | |||
SR 3.5.1.2 - ---- - -- - | |||
NOTE------ - -- --- - -- | |||
When LPCI is placed in an inoperable status solely for performance of this SR. or when the LPCI swing bus automatic throwover scheme is inoperable due to EDG-12 being paralleled to the bus for required testing. | |||
entry into Conditions and Required Actions | |||
}l may be delayed up to 12 hours for completion of the required testing. | |||
Perform a functional test of the LPCI swing 31 days bus automatic throwover scheme. | |||
SR 3.5.1.3 Verify for each ECCS injection / spray 31 days subsystem the piping is filled with water from the pump discharge valve to the injection valve. | |||
(continued) l FERMI UNIT 2 3.5 4 Revision 7 06/18/99 | |||
l.' | |||
L l | |||
ECCS-Operating l 3.5.1 ; | |||
f r | |||
SURVEILLANCE REQUIREMENTS (cor.tinued) | |||
{ | |||
SURVEILLANCE FREQUENCY SR 3.5.1.4 -- - -- ------ | |||
NOTE---- -- ---- - ---- | |||
Low pressure coolant injection (LPCI) | |||
. subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3. and for 4 hours after exceeding the RHR cut-in permissive pressure in MODE 3. | |||
if capeble of being manually realigned and not otherwise inoperable. | |||
Verify each ECCS injection / spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | |||
I SR 3.5.1.5 Verify primary containment pneumatic supply 31 days pressure is a 75 psig. | |||
I SR 3.5.1.6 Verify the RHR System power operated cross 31 days tie valve is open. | |||
?>R 3.5.1.7 04l Verify each recirculation pump discharge valve cycles through one comr':'e cycle of 18 months full travel or is de-energiz;d n the closed position. | |||
(continued) l l FERMI UNIT 2 3.5 5 Revision 7 06/18/99 | |||
p l | |||
l. | |||
ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY l | |||
SR 3.5.1.8 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head with the | |||
; corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RAE PUMPS PRESSURE OF Core Spray = 6350 gpm 2 = 100 psig LPCI = 10.000 gpm 1 = 20 psig SR 3.5.1.9 - - ---- -- | |||
NOTE - - - --- -- | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify, with reactor pressure s 1045 and In accordance | |||
= 945 psig, the HPCI pump can develop a with the flow rate = 5000 gpm against a system head Inservice corresponding to reactor pressure. Testing Program SR 3.5.1.10 - - - | |||
- NOTE - ---- -- | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify with reactor pressure s 215 psig. 18 months the HPCI pump can develop a flow rate | |||
= 5000 9pm against.a system head corresponding to reactor pressure. | |||
(continued) l g l. FERMI. . UNIT 2 3.5-6 Revision 7 06/18/99 j | |||
ECCS - Operating 3.5.1 | |||
. SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.5.1.11 -- --- -- NOTE -- - - - -- --- | |||
Vessel injection / spray may be excluded. | |||
i Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated automatic initiation signal. | |||
1 SR 3.5.1.12 - - ----- ----- | |||
-NOTE- ----- ------ ---- | |||
Valve actuation may be excluded. | |||
Verify the ADS' actuates on an actual or 18 months simulated automatic initiation signal. | |||
1 SR 3.5.1.13 ---- | |||
-- -- - -- NOTE - -- - --- - - | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify each ADS valve opens when manually 18 months actuated. | |||
SR 3.5.1.14 ----- - - -- | |||
--NOTE-- - - ----- | |||
ECCS instrumentation response times are not required to be measured. | |||
Verify ECCS RESPONSE TIME is within limits. 18 months s | |||
i FERMI UNIT 2 3.5 7 Revision 7 06/18/99 | |||
ECCS -Operating B 3.5.1 BASES BACKGR0lA4 (continued) provided for the four LPCI pumps to route water from the suppression pool, to allow testing of the LPCI pumps without l injecting water into the RPV. These test lines also provide. | |||
. suppression pool cooling capability, as described 'in LCO 3.6.2.3,."RHR Suppression Pool Cooling." | |||
^ | |||
The HPCI System (Ref. 3) consists of a steam driven turbine pus) unit, piping, and valves to provide steam to the tur)ine, as well as piping and valves to transfer water from the suction source to the core via the feedwater system line, where the coolant.is distributed within the RPV through the feedwater sparger. Suction piping for the system is provided from the CST and the suppression pool. | |||
Pump suction for HPCI is normally aligned to the CST source to minimize injection of suppression pool water into the RPV. However, if the CST water supply is low, or if the suppression pool level is high, an automatic transfer to the suppression pool water source ensures a water supply for continuous operation of .the HPCI System. The steam supply to the HPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve. | |||
The HPCI System is designed to provide core cooling for a wide range of reactor pressures ~ (165 psig to 1146 psig). | |||
Upon receipt of an initiation signal, the HPCI turbine stop valve and turbine control valve open simultaneously and the turbine accelerates to a specified speed. As the HPCI flow increases, the turbine governor valve is automatically adjusted to maintain design flow. Exhaust steam from the ! | |||
HPCI turbine is discharged to the suppression pool. A full flow test line is provided to route water to the CST to allow tcsting of the HPCI System during normal operation j without injecting water into the RPV. | |||
i The ECCS pumps are provided with minimum flow bypass lines, which discharge to the suppression pool. The valves in these lines automatically o>en to prevent pump damage due to overheating when other disc 1arge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, all ECCS pump discharge lines are filled with water. The LPCI and CS System discharge lines i are kept full of water using a " keep fill" system. The core l spray lines are kept charged with demineralized water and the RHR lines are kept charged with condensate water by a pressure regulating valve. The HPCI System is normally l | |||
l l FERHI > UNIT 2 B 3.5.1-3 Revision 7. 06/18/99 i | |||
m_ . -. - ___ | |||
l l | |||
1 ECCS-Operating B 3.5.1 i | |||
BASES | |||
' ACTIONS-(continued) i L1 ' | |||
The LC0 requires five ADS valves to be OPERABLE in order to provide the ADS function. - The ECCS analyses'are performed with the initial condition of one ADS valve out of service (Ref. 13). Per this analysis, operation of only four ADS volves will provide the required depressurization. However, , | |||
.overall reliability of the ADS is reduced, because a single . | |||
failure in the OPERABLE ADS valves could result in a ! | |||
reduction in depressurization capability. Therefore. ! | |||
operation is only allowed for a limited time. The 14 day Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience. ' | |||
7 any on low Itj one LPCI' pump i ressureECCSinjection/skraysubsystem,or both LPCI subsystems. i inoperable in W addition to one inoperable ADS valve. adequate core cooling is ensured by the OPERABILITY of HPCI and the remaining low pressure ECCS injection / spray subsystem. However, overall ECCS reliability is reduced because a single active component failure concurrent with a design basis LOCA could result in the minimum required ECCS equipment-not being available. Since both a high pressure system (ADS) and low pressure subsystem (s) are inoperable, a more restrictive Completion Time of 72 hours is required to restore either 4 the low pressure ECCS subsystem (s) or the ADS valve to i OPERABLE status. This Completion Time is based on a ! | |||
reliability study cited in Reference 12 and has been found to be acceptable through operating experience. | |||
L 1 and I .2 | |||
, 'If any Required Action and associated Completion Time of ; | |||
Condition E. F. G or H is not met, or if two or more ADS , | |||
L valves are inowrable, the plant must be brought to a ' | |||
condition in w11ch the LCO does not apply. To achieve this l status, the plant must be brought to at least MODE 3 within l 12 hours and reactor steam dome pressure reduced to i s 150 psig within 36 hours. 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. | |||
u i | |||
:l-FERMI' UNIT 2 83.5.1-9' Revision 7-. 06/18/99 | |||
ECCS - Operating B 3.5.1 i | |||
BASES | |||
-SURVEILLANCE REQUIREMENTS (continued) discharge valves, and LPCI cross tie valve. The swing bus automatic throwover- scheme must be OPERABLE for both LPCI subsystems-to be OPERABLE. The 31 day Frequency has been found acceptable based on engineering judgment and operating experience. | |||
This SR is modified by a Note to indicate that when this test results in LPCI inoperability solely for performance of this required Surveillance, or when the LPCI swing bus automatic throwover scheme is inoperable due to EDG 12 being paralleled to the bus for required testing, entry into associated Conditions and Required Actions may be delayed. | |||
-si .for up to 12 t m until the required testing is completed. | |||
Upon completion vi the Surveillance or expiration of the | |||
: g. - 12 hour allowance the swing bus must be returned to OPERABLE | |||
-status or the applicable Condition entered and Required Actions taken. | |||
SR 3.5.1.3 The flow path piping has the potential to develop voids and pockets of entrained air. Maintaining the pump discharge lines of the HPCI System, CS System, and LPCI subsystems full of water ensures that the ECCS will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent a water hammer following an ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. The 31 day Frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls | |||
. governing system operation, and operating experience. | |||
SR 3.5.1.4 LVerifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal'is allowed to be in a non accident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation: rather, it involves | |||
.y | |||
;[ FERMI UNIT 2 B 3.5.1- 11 Revision 7 06/18/99 | |||
u ECCS-Operating B 3.5.1 BASES | |||
- SURVEILLANCE REQUIREENTS (continued) | |||
SR 3.5.1.6 Verification every 31 days that the Rm System power' 1 | |||
operated cross tie valve is open ensures that each LPCI . | |||
subsystem remains ca recirculation loop. pable A valveof injection into the- selected that is inaccessible may be verified by administrative controls. If a RHR System cross-tie valve is not o)en. both LPCI subsystems must be considered inopera)le. The 31 day Frequency has been found acceptable, considering that these valves are under strict administrative controls that will ensure the valves continue to remain open. | |||
SR 3.5.1.7 Cycling the recirculation pump discharge valves through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will close when required. | |||
Upon initiation of an automatic LPCI subsystem injection signal, these valves are required to be closed to ensure full LPCI subsystem flow injection in the reactor via the recirculation jet pumps. De energizing the valve in the closed position will also ensure the proper flow path for the LPCI subsystem. Acceptable methods of de ener valve include de energizing breaker control power,gizing racking the out the breaker or removing the breaker. | |||
' The specified Frequency is 18 months. Verification each 18 months is an exception ~to the normal Inservice Testing Program generic valve cycling Frequency of 92 days, but is considered acceptable due to the demonstrated reliability of these valves. If the valve is inoperable and in the open position, both LPCI subsystems must be declared inoperable. | |||
l-FERMI UNIT 2- B 3.5.1 - 13 Revision 7 06/18/99 | |||
ECCS -Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) which this SR is to be performed is a 850 psig (the pressure recommended by the valve manufacturer). Adequate steam flow is represented by turbine bypass valves open at least 20%. | |||
O/}] Reactor startup is allowed prior to performing this SR because valve OPERABILITY and the setpoints for overpressure. | |||
protection are verified, per ASME requirements ~. prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. The 12 hours allowed for manual actuation after the required 3ressure and flow are reached is sufficient to achieve sta)le conditions and l provides adequate time to complete the Surveillance. | |||
{ | |||
SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TEST performed ' | |||
in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function. | |||
The Frequency is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a )lant outage. Operating | |||
~ experience has shown that t1ese components usually pass the SR when performed at the 18 month Frequency, which is based i on the refueling cycle. Therefore, the Frequency was l concluded to De acceptable from a reliability standpoint. | |||
SR 3.5.1.14 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Response time testing acceptance criteria are included in Reference 15. This SR is modified by a Note stating that the ECCS instrur,entation response times are not required to be measured. The contribution of the instrument response times to the over all ECCS response time are assumed based on guidance of Reference 16. I The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. | |||
Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency. | |||
l FERMI UNIT 2 B 3.5.1 - 17 Revision 7. 06/18/99 l | |||
5pecuFimou 2. S'. I SoSu.SpecNc4Nm.3.35./) | |||
INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMEN T ON tiMITING CONDITION FOR OPERATION 6 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2. | |||
APPLICABILITY: 'As shown in Table 3.3.3-1. | |||
ACTION: | |||
: a. Vith an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted g consistent with the Trip Setpoint value, | |||
: b. With one or more ECCS actuation instrumentation channels M 4 3l inoperable, take the ACTION required by Table 3.3.3-1. | |||
Q c. With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within: | |||
: 1. 7 days, provided that the HPCI and RCIC systems are OPERABLE, otherwise, | |||
: 2. 72 hours. | |||
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours. | |||
SURVEILLANCE REOUTREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK', CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1. | |||
4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of l1 channels shall be perfomed at least once per 18 months.* | |||
fR3.5.l.N 4.3.3.1 The ECCS RESPONSE TIME of each ECCS trip function ** shall be j demonstrated to be within the limit at least once per 18 months. g i | |||
I l | |||
@ for the diesel generator output breakers: Completion of logic system Sf *"g h% , functional testing, for the loss of power function, to positively verify that l the breaker reclosure permissive relay'(52xx) is re-energized by the ' | |||
3Od*i associated bus load shedding logic contact closing, rather than the 52XX t being re-energized by a parallel path, may be deferred and must be completed l no later than during the first plant outage after September 29, 1995. | |||
_ j SR 3.5.1.19 **ECCS actuation instromantation resoonto time need not be measured and may be (aisumeg to be tne/ design instrpfhentation respoffse time] | |||
-'y l poTE | |||
- FERMI - UNIT 2 3/4 3-23 Amendment No.199, JM,lli PAGE I 0F 10 8'" 7 | |||
specir-,cenW 5. 5 / | |||
[#so sce $cclOor4% 5.% / ) | |||
REACTOR COOLANT SYSTEM SURVETLLANCE RFOUIREMENTS 4.4.1.1.1 Each pump discharge valve shall be demonstrated OP8RABLE by ,th | |||
.st 3.5.l.'? cycling each valve through at least one complete cycle of full travel at least once per 18 months. | |||
h.1.1.2 DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in Su. operation, at least once per 12 hours verify that: ' | |||
SpeciMenh% | |||
3'4 8 i a. THERMAL POWER is less than or equal to 67.2% of RATED THERMAL POWER, and | |||
: b. The individual recirculation pump flow controller for the operating recirculation pump is in the Manual mode, and | |||
: c. The speed of the operating recirculation pump is less than | |||
( or equal to ~5% of rated pump speed. | |||
I 4.4.1.1.4 With one reactor coolant system loop not in operation with THERMAL POWER les:: than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase: | |||
M \q a. Less than or equal to 145*F between reactor vessel steam I"f space coolant and bottom head drain line coolant, and | |||
: b. Less than or equal to 50*F between the reactor coolant 3.'I. ! within the loop not in operation and the coolant in the | |||
/ reactor pressure vessel **, and | |||
: c. Less than or equal to 50*F between the reactbr coolant | |||
( within the loop not in operation and the operating loop.** | |||
5 | |||
' Joe-creT. | |||
l g u. [*Reouirement does not apply when the recirculation loop not ih operation is Grenfim kS isolated from the reactor pressure vessel. | |||
3M.t FERMI . UNIT 2 3/4 4-2 Amendment No. 83. 59, 87, DB,1 w | |||
PAGE d 0F 10 | |||
Sp&c. lFacAT704 3,F.1 LSO See Spet\CcuWer. B.C.2 EMERGENCY CORE COOLING SYSTEMS tIMITING CONDITION FOR OPERATION (Continued) | |||
ACTION: (Continued) | |||
: 3. F.1_ d. For the ADS: (ADOAcliersll) 1. | |||
Mc7,on r (HPCI systeQ Oe CSS and the iPEIWith one of the a_bove reautred ADS system are OPERABLE, restore the A C '/7a d Ci inoPeraDie ADS valve to OPERABLE status within 14 days or be in at dCDON I least HOT SHUTDOWN within the next 12 hours and reduce reactor steam dome pressure to 4 150 psig within the next 24 hours. | |||
MC7 tom I 2. | |||
With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam dome pressure to s 150 psig within the next 24 hours. | |||
: e. With a CSS h sder AP, instrumentation channel inoperable annel to OPERABLE status with operable, restore d' k CSS head AP locally at least once per 72 hours hours; or detern ethh otherwise. | |||
tthe as ciated CSS subsystem inoperabl f clare/ | |||
f.~ | |||
f ith an LPCI or 5 system discharge line " keep / filled" al M (,R,) | |||
instrumentatio operable. Derfom Surveillante Requirement) | |||
.5.1.a.1.a. | |||
g. | |||
, the event an tcc5 system is ctuated and injects water into the eactor Coolant System, a Sp tal Report shall be prep ed and I' submitted to the Connissio pursuant to Specification .9.2 within 90 days describing the circ stances of the actuation d the total accumulated actuation c es to date. The current alue of the usage factor for each affee safety injection nozzle hall be provided in j | |||
_Special Report enever its value exceeds .70 7 | |||
$URVElllANCE REOUTREMENTS 4.5.1 The emergency core cooling systems shall be demonstrated OPERABLE by: | |||
: a. At least once per 31 days: | |||
: 1. For the CSS, the LPCI system, and the HPCI system: | |||
sA 3613 a) Verifying b entino Et the hiah 011nt lents that the system piping from the. pump discharse valve to t e system isoiation valve is filled with water. | |||
.5R35.t.f b) Verifying that each valve, manual, power operated or automatic, in the flow path that is not lockedi sealed, or othentise secured in { | |||
i position, is in its correct | |||
* position. | |||
g 3,q ,),6 2. For the LPCI system, verifying that the ross tie vaTve is open. | |||
l | |||
.(6/1165} [iExcept t%t an autytnatic valve r,dpable of automafic return tofts ECCS position g 3g,g,4when arJ/ CCS sion41 is present.4ay be in positi4n for another mode of operation]/ g l | |||
FERMI - UNIT 2 3/4 5-3 PAGE 5 0F 10 ggy 7 1 | |||
) | |||
) | |||
SPgccprc&noid 5.s .( | |||
PLANT SYSTEMS MioSc66fcc)hfdMA--3,7) | |||
/ | |||
.. EMERGENCY EDUfPMENT COOLING WATER SYSTEM , | |||
A [so 6 4 fjou ) b'da d dh 8 ' | |||
tINITING CONDITION FOR OPERATION 3.7.1.2 'fwo independent emergency equipment cooling water (EECW) system subsystems shall be OPERABLE with each subsystem comprised of: , | |||
p6 ap "a. One OPERABLE EECW pump, and g'Qc | |||
: b. An OPERABLE flow path capable of removing heat from the associated 3,9 safety-related equipment. | |||
APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. 3, 4, and 5. | |||
6(IlDE: | |||
L | |||
: a. In OPERATIONAL CONDITION 1. 2 or 3, with one EECW system subsystem Aoperable: | |||
.g 1. Within 2 hours: | |||
68 L a) Verify that all required systems, subsystems, trains, N . | |||
components and devices that depend upon the remaining s, OPERABLE EECW system subsystem are also OPERABLE, and AC.Tto d d - | |||
[lb) Verify that s OPERABLE. d.k | |||
' 5g (Otherwise", be in at least HOT SHUTDOWri within the next 12 hours and in COLD SHUTOOWN within the following 24 hours. | |||
5pocikcAlh < | |||
3.7 2. Declare the associated safety related equipment inoperable and take the ACTIONS required by the applicable Specifications. | |||
Ac r7og C, 3. a-4aoperabh EEC" ;y M ubsystem to OPERABLE Restore status w [itnin 14 hours or be in at least HOT SHU ACT70V D the next 12 hours and in COLD SHUTDOWN within the following 24 hours. | |||
: b. In OPERATIONAL CONDITION 4 or 5, determine the OPERABILITY of the safety-related equipment associated with an inoperable EECW system 5fecibcaNon subsystem and take any ACTIONS required by the applicable J.7 Specifications. | |||
A. | |||
'Y[l;g,W/;yADSisnotrequiredtobeOPERABLEwhenreactorsteamdomepressureisless | |||
/ than or equal to 150 PSIG. | |||
"Except for an inoperable Drywell Cooling Unit, required by Specification 8 | |||
[QC#y 3.7.11 channel, or.an inoperable required primary by Specification containment 3.3.7.S, that depends oxygen raonitoring instrumentatio on the remaining U | |||
gE OPERABLE EECW system subsystem. In these cases, take the ACTION required by , | |||
6[ Specification 3.7.11 for the inoperability of both required Drywell Cooling Units or Specification 3.3.7.5 for the inoperability of both required primary containment oxygen monitoring instrumentation channels. | |||
I FERMI UNIT 2 3/4 7 3 Amendment No. JJ Ef,132 PAGE F 0F 10 gev '7 | |||
,.i - - | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating M.2 CTS 4.5.1.d.1 requires only a functional test of the low pressure alarm circuit for the ADS pneumatic supply (refer to Discussion of lh Change "LR.2" for relocation of this requirement). However, no CTS requirement exists for verification of the necessary pneumatic supply pressure to assure ADS function. ITS SR 3.5.1.5 provides a more restrictive requirement by requiring verification of the | |||
&ctual supply pressure once per 31 days. This change will have no negative impact on safety. and will provide increased assurance of ADS Operability. | |||
TECHNICAL CHANGES LESS RESTRICTIVE | |||
" Generic" LA.1 CTS LCO 3.5.1 includes details relating to system design, function, and Operability for the Core Spray System. the Low Pressure Coolant Injection System and the High Pressure Coolant Injection System. ITS 3.5.1 includes only a requirement for Operability and does not include the details of system design and specific Operability requirements. This is acceptable because these details do not impact the requirement to maintain the equipment Operable and the ITS definition for Operability ensures T that all equipment required to maintain Operability is o functioning. These details will be adequately defined and o , | |||
controlled in the Bases which require change control in - ' | |||
accordance with ITS 5.5.10. Bases Control Program. These details k j are not required to be in the ITS to provide adequate protection ; | |||
of.the public health and safety acceptable because these details ; | |||
do not impact the requirement to maintain the equipment Operable. | |||
LA.2 Not used. | |||
LA.3 Not used. l i LA.4 The following CTS details for performing Surveillances are not included in the ITS. These detailed methods for performing l Surveillances are moved to the Bases: ; | |||
: a. CTS 4.5.1.a.1.a details a requirement for verifying that , | |||
the system is filled with water. "by venting at the high point vents": | |||
I | |||
: b. CTS 4.5.1.a.1.b contains a footnote "*~ which details a ' | |||
requirement for the correct position of ECCS valves: | |||
FERMI - UNIT 2 6 REVISION 7, 06/18/99l , | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating LA.4 -(continued) | |||
: c. CTS 4.5.1.a.3 details a requirement for the HPCI pump flow controller to be in the correct position. The function of the flow controller is to provide the control signal to ensure correct positioning of the HPCI steam governor valve. 'ITS SR 3.5.1.4. requires all system valves be in their correct position, without separately detailing the HPCI pump flow controller. Therefore, as deta.iled in the Bases, the verification of the " correct position" of the governor valve is accomplished by proper flow controller positioning: | |||
: d. CTS 4.5.1.b.1 and 4.5.1.b.2 details test line pressure requirements for the CSS and LPCI pumps:. | |||
e.' CTS 4.5.1.b.3 and 4.5.1.c.2.a details requirements for verifying HPCI pump flow "in the test flow path" with a system head " including injection line losses": | |||
: f. . CTS 4.5.1.c.2.b details requirements for verifying automatic HPCI system transfer: | |||
: g. CTS 4.5.1.d.2.b details requirements for ADS pressure i testing: | |||
: h. CTS 4.5.1.d.2.b.1'and 4.5.1.d.2.b.2 details requirements for verifying ADS valve open; and | |||
: 1. CTS 4.8.3.1.2 details requirements for verifying automatic. j throwover scheme'for the AC power distribution system swing l bus. | |||
These details can be ' adequately defined and controlled in the Bases, which require change control in accordance with Chapter 5 ) | |||
of the ITS. These details are not required to be in the ITS to provide adequate protection of.the public health and safety since the details in the ITS are adequate for assuring proper i performance of the required Surve111ances. | |||
1 J | |||
FERMI' - | |||
UNIT 2 7 REVISION 7 06/18/99l | |||
l DISCUSSION OF CHANGES ITS: SECTION 3.5.1 - ECCS-Operating | |||
.'LA.5 CTS 4.3.3.3. note **. allows the response time for ECCS actuation instrumentation to be exempted from being tested with the value | |||
" assumed to be.the design instrumentation response time." ITS | |||
~ | |||
'SR 3.5.1.14 includes.a Note to specifically detail this allowance, however, the specific method of accounting for the response time (assuming the design sensor response) is relocated to the Bases. - | |||
, This detail'of performance can be adequately controlled in k accordance With ITS 5.5.10. Bases Control Program. The relocation continues to provide adequate protection of the public health and safety since the requirement for the ECCS response time testing remains a Technical Specification requirement. | |||
LR.1 The following Actions and Surveillances of alarm only functions are not assumed in any accident analysis. Alarm only functions do not relate directly to the Operability requirements for the system. ITS does not specify indication-only or alarm-only to be Operable to support Operability of a system or component: | |||
: a. CTS 3.5.1.e details a requirement for restoring an | |||
!- inoperable CSS header differential pressure alarm; | |||
: b. CTS 3.5.1.f details a requirement for performing an SR when a LPCI or CSS system " keep filled" alarm is inoperable: and ) | |||
: c. CTS 4.5.1.c.3 and 4.5.1.c.4 details requirements for performing Channel Calibrations on CSS and LPCI instrumentation. | |||
Regulatory control of changes to these requirements (e.g.. | |||
Technical. Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since alarm-only functions do not relate directly to the l Operability requirements for the system or analysis assumptions. | |||
1 _/ | |||
1 l. | |||
L l FERMI UNIT 2 8' REVISION 7 06/18/99l 1 | |||
I I 1 | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 - ECCS-Operating LR.2 CTS 4.5.1.d.1 and 4.5.1.d.2.c require surveillance tests of ADS l pneumatic supply pressure alarm channels. ITS SR 3.5.1.5 replaces ! | |||
these with a requirement directly related to Operability of ADSi a l Surveillance to verify greater than a minimum supply pressure, which assures ADS Operability. The alarm only functions are not ! | |||
assumed in any accident analysis. Alarm-only functions do not j relate directly to the Operability requirements for the system. I These details of alarm surveillances are not required to be in the ITS to provide adequate protection of the public health and safety i since alarm only functions do not relate directly to the Operability requirements for the system. The replacement of these 3 Surveillances with ITS SR 3.5.1.5 is a more restrictive change (which is discussed here for clarity), which provides a more ) | |||
direct Surveillance of ADS Operability with no impact on safety. | |||
LR.3 CTS 3.5.1. Action 9. requires submitting a special report to the NRC following any ECCS actuation and injection of water into the j reactor coolant system. ITS does not retain the requirement for l this special report because reporting requirements are adequately l addressed by 10 CFR 50.73(a)(2)(iv). 10 CFR 50.73(a)(2)(iv) l requires an LER to be submitted for any event or condition that resulted in manual or automatic ECCS " actuation." Therefore, an ] | |||
a LER will cover any " actuation and injection" as is currently ! | |||
required by CTS 3.5.1. Action 9 An LER is required to be O f submitted within 30 days which also meets the Special Report J. j requirement of 90 days. CTS 3.5.1. Action 9. requirements governing the tracking and reporting to the NRC of accumulated Q l actuation cycles and the current value of the usage factor are accomplished in accordance with plant procedures. Compliance with ! | |||
10 CFR 50.73(a)(2)(iv) and plant procedures will ensure that the NRC is informed of events as required. These details are not required to be in the ITS to provide adequate protection of the public health and safety because reporting requirements are adequately addressed by 10 CFR 50.73(a)(2)(iv). | |||
l TECHNICAL CHANGES - LESS RESTRICTIVE "Speci fic" l L.1 CTS 3.5.1. Action a.2 (loss of both CS subsystems). Action b.3 (LPCI cross connect closed) and Action b.4 (loss of both LPCI subsystems), require that the reactor be in Mode 3 within 12 hours and Mode 4 within 36 hours. Under the same conditions. ITS 3.5.1 Condition J. requires immediate entry into LC0 3.0.3. LC0 3.0.3 FERMI - UNIT 2 9 REVISION 7 06/18/99l | |||
DISCUSSION OF CHANGES | |||
-ITS: SECTION 3.5.1 - ECCS-Operating allows.13 hours to reach Mode 3 and 37 hours to reach Mode 4 and, therefore, is less restrictive. However, the ITS LC0 3.0.3 actions also include a more restrictive requirement: to be in' Mode 2 within 7 hours. The requirement to enter LCO 3.0.3 following the loss of both CS subsystems or the loss of both LPCI subsystems recognizes that a significant plant transient (reactor shutdown and cooldown)' will be performed without the required complement of emergency core cooling systems. Under these circumstances, entry into LC0 3.0.3 and the resulting associated requirements is appropriate. The additional hour allowed to reach Mode 3 and Mode . | |||
4 is not significant and has no impact on the level of plant safety. Furthermore, any impact is offset by the associated more restrictive requirement to be in Mode 2 in 7 hours. | |||
. L.2 . ITS 3.5.1 includes two new Actions. Action F is added for the condition of HPCI Inoperable coincident with: 1) one low pressure ECCS injection / spray. subsystem inoperable: 2) one LPCI pump in one or both LPCI subsystems inoperable: or 3) one CSS and one LPCI subsystem inoperable. Action H is added for.the condition of one ADS valve inoperable coincident with: 1) one low pressure ECCS , | |||
i_njection/ spray subsystem ~ inoperable: 2) one LPCI pump in one or l both LPCI subsystems inoperable: or 3) one CSS and one LPCI l subsystem inoperable. Both Action F and Action H require restoration.of either the inoperable high pressure (HPCI or ADS) , | |||
'or the inoperable low pressure ECCS system within 72 hours. This ! | |||
change is less restrictive than the same conditions addressed in ' | |||
CTS 3.5.1. Actions c and d, which would default to LC0 3.0.3. and require Mode 3 within 13 hours and Mode 4 within 37 hours. (Note ; | |||
that some specific combinations of ECCS inoperability addressed in this change are allowed in CTS action c. in accordance with footnote #. However, all combinations' are discussed as part of this overall'less restrictive change for completeness.) This change is acceptable because ITS 3.5.1. Condition F and Condition H. result in adequate ECCS systems available to respond to a design basis LOCA although the ability to tolerate a single failure may be lost. In Condition F, adequate core cooling is ensured by the Operability of the ADS and the remaining low pressure ECCS subsystems. However. ECCS reliability is reduced because a single failure in one of the remaining Operable subsystems concurrent with a LOCA may result in the ECCS not being r able to perform its' intended safety function. In Condition H, adequate core cooling is ensured by the Operability of HPCI and the remaining low pressure'ECCS injection / spray subsystems. | |||
However. ECCS reliability is reduced because a single failure | |||
~ | |||
FERMI UNIT 2- -10 REVISION 7 06/18/99 | |||
l DISCUSSION OF CHANGES ITS: SECTION 3.5.1 - ECCS-Operating l | |||
concurrent with a LOCA could result in the minimum required ECCS equipment not being available. Therefore. ITS 3.5.1. Action F and Action H. require restoration of either the inoperable high pressure (HPCI or ADS) or the inoperable low pressure ECCS system within 72 hours. This Completion Time is based on a reliability study cited in memorandum from R.L. Baer (NRC) to V. Stello. l Jr.(NRC). " Recommended Interim Revisions to LCOs for ECCS l Components." December 1. 1975. This change is consistent with NUREG 1433. Rev. 1. | |||
L.3 CTS Actions (LCO 3.7.1.2. Action a.3 and LCO 3.5.1 Actions. Footnote | |||
"#") for one CSS subsystem and one LPCI subsystem inoperable due to lack of EECW cooling, allow 72 hours to restore the inoperable EECW (and therefore the inoperable CSS and LPCI subsystems). However. , | |||
the CTS Actions for one CSS subsystem and one LPCI subsystem I inoperable for any other reason, requires immediate shutdown. The l ITS eliminate the restriction on the inoperabilities of CSS and LPCI l having to be due to lack of EECW cooling: allowing 72 hours for one CSS subsystem and one LPCI subsystem inoperable for any reason. In the condition of one CSS and one LPCI subsystem inoperable. provided all other safety related equipment is available to perform its function (which is assured by other ITS Specifications and the ITS Safety Function Determination Program). the remaining ECCS subsystems are adequate to perform the assumed ECCS function in the event of an accident. | |||
L.4 CTS 4.5.1.b.3 (HPCI high pressure flow verification). CTS 4.5.1.c.2.a (HPCI low pressure flow verification), and CTS 4.5.1.d.2.b (ADS valve manual operation) are modified by a footnote ~ allowing performance to be deferred until ~12 hours after reactor steam pressure is adequate to perform the test" but also states that the test is performed at 2 150 psig. This allowance to defer testing is based on the need to establish appropriate conditions for testing. The corresponding ITS SRs. 3.5.1.9. | |||
3.5.1.10 and 3.5.1.13 are modified by a similar Note that allows deferring the performance of these tests until reactor steam pressure "and flow" are adequate to perform the test. This change is necessary because the CTS allowance to reach only the required reactor steam pressure only partially addresses the issue of | |||
-adequate test conditions. Requiring performance of these tests before adequate steam flow can be maintained creates the potential I for an undesired reactor depressurization. This change is less | |||
~ | |||
, restrictive because it may allow additional time before the tests are required to be performed. This change is acceptable because FERMI - UNIT 2 11 REVISION 7 06/18/99h | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating the-allowance permits the test to be delayed until appropriate conditions are established and will not normally result in a significant delay in performing these tests. Additionally, the' | |||
- Bases which detail the conditions defining " adequate pressure and flow" specify adequate pressure as 2 850 psig. This pressure is that recommended by the valve manufacturer and. represents clarification of the CTS presentation that states testing is done at 2 150 psig after " adequate pressure" to perform the test has been achieved. | |||
L.5 CTS 4.8.3.1.2 and ITS SR 3.5.1.2. requires demonstration of the LPCI swing bus automatic transfer scheme. Performance of this test requires that the swing bus (and therefore both LPCI subsystems) be made inoperable. Additionally, performance of EDG surveillances that require the EDG to be paralleled to its bus, render the automatic throwover scheme inoperable. As a result. | |||
these tests would result in ITS requiring an intentional entry into LC0 3.0.3 (LC0 3.5.1. Condition J). To preclude this intentional LC0 3.0.3 entry, the ITS adds a Note to SR 3.5.1.2 allowing a 12 hour delay in entering the actions for the lq inoperability caused by performing these required Surveillances. | |||
Since this test: 1) is not expected to de-energize the swing bus: T | |||
: 2) is performed under control of a dedicated individual in communication with the control room operator: and 3) results in the period of inoperability being much less than 12 hours. an l+d avoidance of an intentional entry into LC0 3.0.3 will not significantly affect safety. | |||
RELOCATED SPECIFICATI0NS' None TECHNICAL SPECIFICATION BASES The CTS Bases for this Specification have been replaced by Bases that reflect the format and applicable content of ITS 3.5.1 consistent with the BWR STS. | |||
NUREG-1433. Rev. 1. | |||
.s FERMI - UNIT 2. 12 REVISION 7 06/18/99l ! | |||
ECCS-Operating 3.5.1 ACTIONS (continued) | |||
CONDITION. REQUIRED ACTION COMPLETION TIME HPCI System Restore HPCI System. 72 hours inoperable. to OPERABLE status. | |||
poc /, .2 ) | |||
f. | |||
P = | |||
(.ondifim R h e 1e. ;-;;;ere CCC, Restore low pressure 72 hours pr fond; Hon, -injedier./;prq ECCS injection / spray c L .2 g, g su g a. Ie- subsyste to OPERABLE ddic a t...,....,... status. | |||
C, eniere . | |||
h One ADS valve inoperable. | |||
1 Restore ADS valve to 14 days (3,f,/ 3agg,a d, OPERABLE status. | |||
One ADS valve Restore ADS valve to inoperable. | |||
1 72 hours (2)ocL,") | |||
OPERABLE status. | |||
{ | |||
m a & | |||
E: ::e pressure ECC^ Restore low pressure Q(ond,mg ' | |||
injection / spray 2 | |||
ECCS injection / spray 72 hours (poc L,2 (ubsystem-inoperabi 6 eng subsyste to OPERABLE status. | |||
[3 7.1,'2. Adrn o.l. b) | |||
Two or more ADS valves 1 Be in MODE 3. 12 hours inoperable. | |||
g g3,3,g,ocg,,,l,g) e c.s. i,ar- a .2) 2 Reduce reactor steam 36 hours Required Action and dome pressure to ' | |||
associated Completion | |||
[ (3, S , /,q c-li.n c- If Ti Conditio 5g50gpsig. . | |||
y Enr-F not-met | |||
[ o r // (continued) flot rnc f . | |||
-- M/4 STS - - 3.5-2 - Rev-1 ;-0+/0NSE.- | |||
RW 7 | |||
ECCS-Operating 3.5.1 ACTIONS (continued) < C 75 h CONDITION REQUIRED ACTION COMPLETION TIME Two or more low Enter LC0 3.0.3. Isenediately | |||
, pressure ECCS injection / spray subsystemsinoperable.( [o f., f ea raft 3 gg other f/ G /L HPCI System and one or *E ' ##4 ## ' | |||
'># ##U #' | |||
more ADS valves inoperable. | |||
4 b3> | |||
P, l ( 6. Q 77 < c.> | |||
/ < 87 f,x are C.s.3.i m c > | |||
c.am.,c a s o | |||
( oas c{ i$ e'a #1 G ert if l~C | |||
~ ' | |||
W ! | |||
2 ) | |||
9""./' !TS - 3.5-3 - | |||
R., 1, 04/07/05 | |||
ECCS-Operating 3.5.1 INSERT 3.5.1 02 SR 3.5.1.1 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. | |||
LH.s.5.lb SR 3.5.1.2 - - ---- --- - | |||
NOTE---- ---- - --- | |||
When LPCI is placed in an inoperable status solely for performance of this SR. or when [ Doc L.5) the LPCI swing bus automatic throwaver scheme is inoperable due to EDG 12 being paralleled to the bus for required testing. | |||
entry into Conditions and Required Actions | |||
?'ty be delayed up to 12 hours for y | |||
completion of the required testing, lb Perform a functional test of the LPCI swing 31 days bus automatic throwover scheme. | |||
497,3./.O l | |||
l l | |||
1 f | |||
FERMI UNIT 2 Page 3.5 4 (Insert) REVISION 7 06/18/99l | |||
p .i . - . . , | |||
ECCS-Operating 3.5.I SURVEILLANCE REQUIREB.VTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.5.I.E - - - - - - - | |||
NOT ------ | |||
(I. [ /* /* / <L ot quire o be rf d if rfo d | |||
,l w 'hin he pr ous da . | |||
[4, e/ /, / . / foe &o{e | |||
* Verify each recirculation pump discharge ITnt %S n .ee valve [=d typ::: :.h ] cycles through one ta up r r complete cycle of full travel tpr is t e ee n de-energized in the closed positiony'.*- 25 R | |||
'8 =W - | |||
SR 3.5. I 3. Verify the following ECCS pumps develop the ''' | |||
In accordance specified flow rate (against a system head with the corresponding to the specified reactor Inservice pressuret.- Testing b(SYSTEMHEAD Program-se=- | |||
NO. CORRESPONDING Of A _- g 0F TO A REACTOR - | |||
-P SYSTEM FLOW RATE ft2iPJ PRESSURE OF:# | |||
Core 6350 Spray 2-, | |||
gpm 2[ | |||
too sig g, g,f, g, j ) | |||
LPCI 2 [I7,00P gpm , 2S sig / | |||
Qo,ooo (g, p, /. f . p p SR '.5.I. | |||
3 -----------------NOTE------------------ ( f, ,/. b. 3 h Not required to be performed until 12 hours after reactor steam pressure and flow are adequa.te to perform the test. | |||
hl Ve ty , ,,with Treactor pressurefs v u20)- U sys -_ | |||
and 2 {e20t psig, the HPCI pump can develop [In accordanc4 + | |||
a flow rate 2- 42 gpm fagainst a system w;& ik l.nservice. | |||
headcorrespon{dingtoreactorpressureJ. 4,- | |||
Prop (continued) | |||
(4, fr, l. 6. 3) | |||
-DWRpW, 3.5-5 %'kv-4,- Ci/07/Z ' | |||
I ECCS-Optrating B 3.5.1 BASES BACKGROUND hjecftcl.)ing arer;rf recirculation loop, begins. The water then ! | |||
(continued) enters the reactor through the jet pumps. Full flow test ' | |||
lines are provided for the four LPCI pumps to route water p'g from the suppression pool, to allow testing of the LPCI i pumps without injecting water into the RPV. These test p lines also provide suppression pool cooling capability, as- i i described in LCO 3.6.2.3, 'RHR Suppression Pool Cooling." | |||
g ; | |||
The HPCI System (Ref. 3) consists of a steam driven turbine pump unit, piping, and valves to provide steam to the 5 | |||
turbine, as well as piping and valves to transfer water from the suction source to the core via the feedwater system line, where the coolant is distributed within the RPV through the feedwater sparger. Suction piping for the system is provided from the CST and the suppression pool. i Pump suction for HPCI is normally aligned to the CST source l to minimize injection of suppression pool water into the RPV. However, if the CST water supply is low, or if the suppression pool level is high, an automatic transfer to the suppression pool water source ensures a water supply for continuous operation of the HPCI System. The steam supply to the HPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve. | |||
The HPCI System is designed to provide core cooling for a g O f'I f, wide range of reactor pressures (15? Mid te !!?! arid - | |||
UVff8/3 | |||
# m ee' te 7 P t Ma). Upon receipt of an initiation signal, the HPCI turbine stop valve and turbine control N | |||
~ | |||
valve open simultaneously and the turbine accelerates to a specified speed. As the HPCI flow increases, the turbine governor valve is automatically adjusted to maintain design fl ow. Exhaust steam from the HPCI turbine is discharged to the suppression pool. A full flow test line is provided to route water fr= =d to the CST to allow testing of the HPCI bb System during normal operation without injecting water into the RPV. | |||
The ECCS pumps are provided with minimum flow bypass lines, which discharge to the suppression pool. The valves in these lines automatically open to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, all ECCS pump discharge' lines are filled with water. The LPCI and CS System discharge lines are kept full of water using a " keep fill" system,(-jockey M _ ystan). The HPCI System is normally alioned to the Ilus r.re Qray Mcs a re k e C /u r g rv:/ f4e RHR /.kes are keM c/pt a rg ed ,fAf edcude,uate e r ith c{er,,,; | |||
a f e e-c ra t, teal Mfer ] k2_ | |||
a p rm e.re e c m In ton 9 Volve- f- -b yy(continued) | |||
_.___ j WD/' STS | |||
* B 3.5-3 Rc.- 1, 04/07/35-ffe7 | |||
I ECCS-Operating B 3.5.1 l BASES t, p- . | |||
/ . Th El C S | |||
* M' \ ' 5' a re rr k a'' I ACTIONS | |||
/g j L1 (continued) fhc {fc.'Icom],f'yoi~ > | |||
(2rfl3 T | |||
* d-awnebW *+ eva'"O=d the effech:f one ADS valve Detag out of service" Per this analysis, operation of only l | |||
-fove +4* ADS valves will provide the required depressurization. | |||
However, overall reliability of the ADS is reduced, because | |||
/% a single failure in the OPERABLE ADS valves could result in i | |||
/Q a reduction in depressurization capability. Therefore, operation is only allowed for a limited time. The 14 day l | |||
Completion Time is based on a reliability study cited in Reference 12 and has been f nd to be accentable throuah _ | |||
operating experience. | |||
,oc one g.per, p p ;n j ag j.g to S a bS piru s I N | |||
/.1and/.2 -- | |||
If any one low pressure ECCS injection / spray subsystem is inoperable in addition to one inoperable ADS valve, adequate core cooling is ensured by the OPERABILITY of HPCI and the remainin However,g low pressure overall ECCS is ECCS reliability injection reduced/ spray becausesubsystem. | |||
a single active component failure concurrent with a design basis LOCA could result in the minimum required ECCS equipment not be available. Since both a high pressure system (ADS) and ow pressure subsystem 4are inoperable, a I'$ | |||
more restrictive pletion Time of 72 hours is required to restore either the low pressure ECCS subsystemgor the ADS 4(5) valve to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience. | |||
1 l % $.1 and d.2 ' | |||
E, h 6 | |||
/ | |||
If any Required Action nd associated Completion Time of Condition ($, n L er is not met, or if two or more ADS b | |||
valves are inoperable %e plant must be brought to a condition in which the LCO does not apply. To achieve this | |||
' status, the plant must be brought to at least MODE 3 within 12 hours nd reactor steam dome pressure reduced to s 150 psig within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. | |||
l (continued) | |||
'"R/f STSm B 3.5-8 L ;, 0;/C7/h Re 1 | |||
[ | |||
L l | |||
ECCS Operating B 3.5.1 LNSERT B 3.5.13 l SR 3.5.1.1 The LPCI System injection valves, recirculation pump discharge valves, and LPCI cross tie valve are powered from the LPCI swing bus, which must remain energized to support OPERABILITY of both LPCI subsystems. Therefore, verification of proper voltage and correct breaker alignment to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate separation and independence of the electrical power sources are maintained and appropriate sources of electrical power are available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability ensures that the required voltage is readily available for critical system loads connected to this bus. The 7 day Frequency takes into account the redundant capability of the AC, DC, and AC swing bus electrical power sources - and other indications available in the control room that alert the operator to subsystem malfunctions. | |||
SR 3.5.12 The LPCI System injection valves, recirculation pump discharge valves, and LPCI cross tie valve are powered from the LPCI swing bus, which must remain energized during any single failure, including loss of power from the normal feed to the swing bus. Therefore the automatic throwaver scheme is functionally tested (by manually opening position 3C of bus 72C) to verify the capability of the throwover scheme to detect loss of normal power, and initiate an automatic transfer to the swing bus emergency power source. | |||
Verification every 31 days that the LPCI swing bus automatic throwover scheme functions properly demonstrates that AC electrical power is available to ensure proper operation of the associated LPCI injection valves, recirculation pump discharge valves, and LPCI cross-tie valve. The swing bus automatic throwover scheme must be OPERABLE for both LPCI subsystems to be OPERABLE. The 31 day Frequency has been found acceptable based on engineering judgment and operating experience. | |||
This SR is modified by a Note to indicate that when this test results in LPCI inoperability solely for performance of this required Surveillance, or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG 12 being paralleled to the bus for required testing, entry into associated Conditions and Required Actions may be delayed for up to 12 hours l l until the required testing is completed. Upon completion of the %g | |||
! Surveillance, or expiration of the 1 hour allowance, the swing bus must be | |||
~ | |||
, returned to OPERABLE status or the applicable Condition entered and Required Actions taken. | |||
FERMI - UNIT 2 Page B 3.5 9 (Insert) REVISION 7. 06/18/99 l l | |||
~ | |||
Avalve,Yhef[S ,1 ECCS-Operating in a ccessahlt i'uay k B 3.5.1 Veri' fled b gg5g5- | |||
&inis t'ra% .fIve. Lo d ro h SURVEILLANCE SR 3.5.1 (continued) | |||
REQUIREMENTS g, removing-ths breaker., f-tae RHR System cross tie valve is p,p oo en er a-- hu aa+ k-- = = -d <--- +ke s'-- ape ste , | |||
th LPCI subsystems must be considered inoperable. The 31 day Frequency has been found acceptable, considering that these valves are under strict administrative controls that will ensure coa +*a' a- the valves continue to remain 'e: P ith efther | |||
=at4": ;::::r -- :::d. | |||
SR -3%1 , | |||
Veriff to | |||
[has vo ge r[31 days,that each I inverter p[570)fV and 5 [63 Ywhilejup/tput plying it r pe ve bus delmonstrates that the AC electrical power is; f, l l v abledojtisure p' f roper operdion of the'' associated E),CI ard'inj(ction nd mini rec.i(culgionp discha flow valves'and the / | |||
OPERABkE for valve. Ea'ch invert r'eust be I associal d LPCI subsfystem to OPE . | |||
'The,21 day F quency has been fou_nd accepta bas n ggineeri judgment /and operatirig experijffce. | |||
7 SR 3. 5.1.1t ) | |||
i Cycling the recirculation pump discharge in.d L,r.ee] valves through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will close when required. Upon initiation of an automatic LPCI subsystem injection signal, these valves are required to be closed to ensure full LPCI subsystem flow injection in the reactor via the recirculation jet pumps. De-energizing the valve in the closed position will also ensure the proper flow path for the LPCI subsystem. Acceptable methods of de-ener valve include de-energizing breaker control power,gizing racking the out the breaker or removing the breaker. | |||
The specified Frequency is-once tr'_ t :- e- *={/8'ntoni S | |||
+ e -+ S-- | |||
b:fx. THERMAt-POWE" i; , 25% "'". Howev:r, thi. ^e si modified i,, . Net, thet stet;; the-Sur":il':::: i: tr f,3 T**uir'.d4*-b*-pedon"'d i f th' '''' "*"'a"-""" r*' Ay **r* | |||
t than 31. days-age- "*-afe-:, imp'::::tet t en .T tMs-Note-- | |||
l | |||
~ requires-th4s-tast- te k perJormed-during reecter ittrtup-- | |||
-before-eweeedhg 2",% "Th Verification d"rf ; eset_. l l | |||
l | |||
'k I | |||
(continued) I | |||
'BWRTt''ST3 ' B 3.5-11 i | |||
-Rev-17-04/07f95.-- i l | |||
i Rev 7 \ | |||
L ECCS-Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1 (continued) | |||
REQUIREMENTS Ai | |||
:tir r. ;., .. x d ; ' * "T" is an exception to the W normal Inservice Testing Program generic valve cycling Frequency of 92 days, but is considered acceptable due to the demonstrated reliability of these valves. If the valve is inoperable and in the open position, t " :: ht '' LPCI f, 'd. | |||
subsyste must be declared inoperable. | |||
SR 3.5. SR 3.5. and SR 3.5.1 The performance requirements of the low pressure ECCS pumps are determined through application of the 10 CFR 50, Appendix K criteria (Ref. 8). This periodic Surveillance is | |||
* performed (in accordance with the ASME Code, Section XI, - | |||
requirements for the ECCS pumps) to verify that the ECCS i pumps will develop the flow rates required by the respective y analyses.- The low pressure ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of Reference 10. The pump flow ratestere verified p 6,. c against a system head equivalent to the RPV pressure = Spro y, 2 , | |||
j expected during a LOCA. The total system pump outlet pressure is adequate to overcome the elevation head pressure pa rkmr5 raille'n( | |||
between the pump suction and the vessel discharge, the aferaf,%) ) | |||
i | |||
__. piping LOCA. | |||
friction losses, and RPV pressure present during a ; | |||
testing These a values may be established during preoperational 5 | |||
l ygj-The flow tests for the HPCI System are performed at two different pressure ranges such that system capability toL6 3 f'I' b ' | |||
l provide rated flow is tested at both the higher and lower i | |||
operating ranges of the system. Additionally, adequate - | |||
i steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor W pressure when the HPCI_ System diverts steam flow. Reacto steam pressure must ce Z W psig and 2.4,140] psig to perform SR 3.5.1 form SR 3.5.1 | |||
/6 dequate steam f ow is represented by 4*t-lepst-h25-tur ,= Li v >> vabu e or-to t aT-s team 41 ow-t--10-l b/h e}r Therefore, sufficientve n I time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal , | |||
(continued) } , | |||
BWR/4 STS I B 3.5-12 Rev 1, 04/07/95 l | |||
l inain tubine. y erseca % on line or t41.a b y p ss. | |||
p skdves open a t les s+ | |||
i ia, Rufo press 4 ec. | |||
(S'7s ce> <, tro I , | |||
~ | |||
Rev7 | |||
ECCS-Operating B 3.5.1 | |||
< BASES | |||
~ | |||
SURVEILLANCE SR 3.5.1.1' continued) | |||
REQUIREMENTS that no blockage exists in the V discharge lines. This is demonstrated by the response of the turbine control or bypass valve or by a change in the measured flow or by any other method suitable to verify steam flow. Adequate. | |||
reactor steam done pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when j the ADS valves divert steam flow upon opening. Sufficien )# S'o time is therefore allowed after the required pressure and Ofeb flow are achieved to perform this SR. dequate pressure at which this SR is to be performed is psig):-(the pressure recommended by the valve manufacturer). Adequate steam flow is represented by | |||
'' [- t lep t 1.25 L.. M;.e L.w.n vaivas | |||
.htbe,hfa55 er--teta! -+- - | |||
- 1Lj;n '' . Reactor startup is u,,.u, g(ges , p.am d allowed prior to performing this SR because valve , | |||
lea 5 D ,I' OPERABILITY and the setpoints for overpressure protection A. | |||
-- ^ are verified, per ASME requirements, prior to valve installation. Therefore, this SR is modified by a Note that , | |||
states the Surveillance is not required to be performed until 12 hours adequate after reactcr to perform the test.steam The 12pressure and flow hours allowed for_ are Q.p)g 1 | |||
manual actuation after the required pressureMeached is | |||
* sufficient to achieve stable conditions and adequate time tn complete the Surveillance. providesSR 3.5.1 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function. | |||
P,2- Me T..yuancy of is , nth: :: : !T*00E"E0 T[ T "'S!? -aenre | |||
= =. 2 :u: # - er ,:l= = lte-t:ly | |||
*testar The Frequency is based on the need to perform the n,{ N r | |||
Survei31aate under the conditions that apply just prior ta or duriag a startup from a plant outage. Operating experience has shown that these components usually pass the jy$67 SR when performed at the 18 month Frequency, which is based BMM7 g on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. | |||
r REFERENCES 1. FSAR,Sectionp.3.2.2.3A 2. | |||
l FSAR,Sectiong.3.2.2.4g i 1 | |||
(continued) ! | |||
BWR/4 STS B 3.5-15 Rev 1, 04/07/95 l | |||
{ | |||
W i | |||
StN ] | |||
l | |||
I | |||
* JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.5.1 - ECCS Operating P.1 -(continued) | |||
: c. ITS SR 3.5.1.4 Note is modified to include a provision from CTS 3.5.1. Action b.5 that provides 4 hours after entering the ECCS Applicability. This CTS provision is modified by DOC "M.1" to the CTS markup. repeated below for reference: | |||
, CTS Action b.5 provides an allowance for Mode changes | |||
(" provisions of Specification 3.0.4 are not applicable") when LPCI is not correctly aligned for the LPCI' mode of operation. | |||
This allowance provides 4 hours after reactor vessel pressure exceeds the RHR cut-in permissive prior to having to establish the correct LPCI alignment. The allowed Mode changes could include Mode 2 as well as Mode 3 (even Mode 1 if sufficient time were available to proceed from Mode 2 to Mode 1). The Note to ITS SR 3.5.1.4 provides this same 4 hour allowance, but limits its application to Mode 3 only. Therefore the ITS is more restrictive in requiring the proper LPCI alignment prior to entr. ng Mode 2. This is a more restrictive change with no impact on safety. | |||
d. | |||
ITS includes new SRs (SR 3.5.1.1 and SR 3.5.1.2) that result from CTS surveillances 4.8.3.1.1 and 4.8.3.1.2. These reflect the Fermi-specific design equivalent to the standard design reflected in NlREG 1433 SR 3.5.1.5 (for LPCI inverter). Additionally. CTS 4.8.3.1.2 is modified by DOC "L.5" to the CTS markup (repeated below for rettrence): | |||
CTS 4.8.3.1.2 and ITS SR 3.5.1.2. requires demonstration of the LPCI swing bus automatic transfer scheme. Performance of this test requires that the swing bus (and therefore both LPCI subsystems) be made inoperable. As a result, this test would result in ITS requiring an intentional entry into LCO 3.0.3 (LC0 3.5.1. Condition J). To preclude this intentional LCO 3_.0.3 entry, the ITS adds a Note to SR 3.5.1.2 allowing a 12 , | |||
hour' delay in entering the actions for the inoperability caused by performing this required Surveillance. Since this test: 1) is not expected to de-energize the swing bus: 2) is performed 3 | |||
,4 ) | |||
under control of a dedicated individual in communication with the control room operator; and 3) results in the period of q | |||
.inoperability being much less than 12 hours. A 12 hour avoidance of an intentional entry into LCO 3.0.3 will not lQ l significantly affect safety. | |||
FERMI UNIT 2 2 REVISION 7 06/18/99l ! | |||
1 | |||
JUSTIFICATION FOR DIFFERENCL3 FROM NUREG 1433 i ITS: SECTION 3.5.1' ECCS - Operating i | |||
: e. ITS SR 3.5.1.6 is modified to reflect the CTS 4.5.1.a.2 requirement for the LPCI cross connect valve to be open. This CTS Surveillance is implicitly addressing the power operated cross connect valve (note the singular form " valve"). There is however, a second valve: a locked open manual maintenance valve, that is not explicitly addressed with a periodic CTS (or . , | |||
ITS) surveillance. _ Therefore, as an editorial clarification ! | |||
(refer also to DOC "A.13") " power operated" is added to ITS SR 3.5.1.^6 to a.fferentiate the valve required to be surveilled each 31 days. As further clarification, the manual maintenance valve is also addressed in the Bases for this SR. | |||
P.2 Bases changes are made to reflect plant specific design details. , | |||
equipment terminology, and analyses. Some of these changes are specifically discussed below: | |||
: a. Backaround. Anolicable Safety Analysis. LCO. and Surveillances: | |||
Specific ECCS response to large break DBAs is revised to reflect i | |||
Fermi 2 design of " loop selection logic." The change to ITS SR l 3.5.1.7 reflects the loop selection logic design (which includes both LPCI subsystems being cross tied such that the inability to isolate one recirculation loop may result in both LPCI-subsystems injecting into the broken loop and therefore neither performing their intended function). I | |||
- b. Surveillances: Since ADS is designed with only one solenoid, the | |||
" Staggered Test Basis" is not applicable. | |||
P.3 Bases changes are made to reflect changes made to the Specification. | |||
Refer to the Specification change (and associated JFD) for additional detail. | |||
P.4 Not used. | |||
l u | |||
i FERMI UNIT 2 3 REVISION 7, 06/18/99l l | |||
NO SIGNIFICANT HAZARDS EVALUATION I ITS: SECTION 3.5.1 ECCS - Operating 4 | |||
TECHNICAL CHANGES LESS RESTRICTIVE | |||
. (Soecification 3.5.1 "L.5" Labeled Comments / Discussions) 4 | |||
: 2. Does the change create the possibility of a new or different kind of l accident from any accident previously evaluated? | |||
This proposed change will not involve any physical changes to plant i systems, structures, or components (SSC). nor changes in normal plant i operation. The test will continue to be conducted as previously i required, with the expected result being confirmed Operability of the : | |||
system. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. | |||
: 3. Does this change involve a significant reduction in a margin of safety? | |||
- The proposed change does not involve a significant reduction in a margin of safety because this test: 1) is not expected to de energize the swing bus: 2) is performed under control of a dedicated individual in communication with the control room operator: and 3) results in the period of delayed Actions being less than 12 hours (i.e., a reasonably T I minimal period of time). Additionally, the expected result is a satisfactory demonstration of Operability, with no impact on safety. | |||
f W | |||
9 FERMI . UNIT 2 10 REVISION 7. 06/18/99l | |||
ECCS -Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2' ECCS-Shutdown i LCO 3.5.2 Two low pressure ECCS injection / spray subsysteris shall be . | |||
OPERABLE. | |||
i APPLICABILITY: MODE 4 MODE 5. except with the spent fuel storage pool gates removed and water level = 20 ft 6 inches over the top of the reactor pressure vessel flange. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A, One required ECCS A.1 Restore required ECCS injection / spray 4 hours injection / spray subsystem inoperable. subsystem to OPERABLE status. | |||
B. Required Action and B.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not met, draining the reactor vessel (OPDRVs). | |||
C. Two required ECCS C.1 Initiate action to Immediately injection / spray suspend OPDRVs. | |||
subsystems inoperable. | |||
MQ C.2 Restore one ECCS 4 hours injection / spray subsystem to OPERABLE status. | |||
_ (continued) l FERMI - UNIT 2 3.5 8 Revision 7. 06/18/99 | |||
ECCS-Shutdown 3.5.2 ACTIONS (continued) | |||
C0leITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status. | |||
M D.2 Initiate action to Immediately restore one standby gas treatment i subsystem to OPERABLE status. | |||
M D.3 Initiate action to Immediately ; | |||
restore isolation capability in each ! | |||
required secondary ; | |||
containment | |||
', penetration flow path not isolated. | |||
i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each re 12 hours coolant injection (quired low pressure LPCI) subsystem, the ! | |||
suppression pool water level is | |||
= 66 inches. , | |||
(continued) l' FERMI UNIT 2 3.5 9 Revision 7. 06/18/99 k | |||
*f:. . | |||
ECCS -Shutdown 3.5.2 , | |||
I I | |||
SURVEILLANCE REQUIREMENTS (continued) | |||
{ | |||
. SURVEILLANCE FREQUENCY | |||
) | |||
J i | |||
SR 3.5.2.2 Verify. for each required core spray (CS) 12 hours subsystem, the: l | |||
: a. Suppression pool water level is | |||
= 66 inches: or | |||
: b. . -.-..........- N0TE--. - ---.... .- | |||
Only one required CS subsystem may take credit for this option during OPDRVs. | |||
Condensate storage tank water level is l = 19 ft. | |||
SR 3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus, ! | |||
i l | |||
SR 3.5.2.4 Verify. for each required ECCS injection / 31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. | |||
(continued) j FERMI - UNIT 2 3.5 10 Revision 7 06/18/99 | |||
m | |||
) | |||
1 . | |||
1 i | |||
l ECCS - Shutdown j 3.5.2 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY l SR 3.5.2.5 -- -- - | |||
. NOTE -- - -- | |||
LPCI subsystem (s) may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. | |||
Verify each required ECCS injection / spray 31 days subsystem manual, power operated, and | |||
. automatic valve in the flow path, that is not locked, sealed, or otherwise secured in j position, is in the correct position. | |||
1 SR 3.5.2.6 Verify each required ECCS pump develoas the In accordance Ogl specified flow rate against a system wad with the j | |||
l l corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program N0. CORRESPONDING 0F TO A REACTOR SYSTEM FLOW RATE PQMPS PRESSURE OF l CS = 6350 gpm 2 = 100 psig i LPCI = 10,000 gpm 1 = 20 psig l | |||
SR 3.5.2.7 : ---- - NOTE - -- - - | |||
Vessel injection / spray may be excluded. | |||
I Verify each required ECCS injection / spray 18 months I subsystem actuate s on an actual or simulated automecic initiation signal. | |||
l 1 . | |||
l | |||
: j. FERMI UNIT 2 3.5 11 Revision 7 06/18/99 l | |||
l- | |||
ECCS-Shutdown B 3.5.2 BASES ACTIONS (continued) to OPERABLE status. In this case, the Surveillance may need l to be performed to restore the component to OPERABLE status. l Actions must continue until all required components are OPERABLE. | |||
. The 4 hour Completion Time to restore at least one low pressure ECCS injection / spray subsystem.to OPERABLE status ensures that prompt action will be taken to provide the required cooling capacity or to initiate actions to place the plant in a condition that minimizes any potential fission product release to the environment. l SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 REQUIREMENTS The minimum water level indication of 66 inches (9 ft 0 inches actual level) required for the suppression pool is periodically verified to ensure that the su)pression pool will provide adecuate net positive suction lead (NPSH) for the CS System anc LPCI subsystem pumps, recirculation volume, and vortex prevention. With the suppression pool water level less than the required limit, all ECCS injection / spray subsystems are inoperable unless they are aligned to an OPERABLE CST. | |||
When suppression pool level is < 66 inches, the CS System is considered OPERABLE only if it can take suction from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a verification that either the suppression pool water level is = -66 inches or that CS is aligned to take suction from the CST and the M CST contains = 300.000 gallons of water, equivalent to 19 ft T/ plus margin to preclude vortex formation, ensures that the CS System can supply at least 150.000 gallons of makeup water to the RPV. The CS suction is uncovered at the 150.000 gallon level. However, as noted, only one required CS subsystem may take credit for the CST option during OPDRVs. During OPDRVs. the volume in the CST may not provide adequate makeup if the RPV were completely drained. | |||
Therefore, only one CS subsystem is allowed to use the CST. | |||
This ensures the other required ECCS subsystem has adequate makeup volume. | |||
The 12 hour Frequency of these SRs was developed considering operating experience related to suppression pool water level l FERMI UNIT 2 B 3.5.2 -4 Revision 7. 06/18/99 | |||
ECCS- Shutdown B 3.5.2 BASES | |||
. SURVEILLANCE REQUIREMENTS (continued) and CST water level variations and instrument drift during i | |||
^ | |||
the applicable MODES. Furthermore, the 12 hour Frequency is I considered adequate in view of other indications available in the control room, including alarms, to alert the operator i to an abnormal suppression pool or CST water level i condition. | |||
SR 3.5.2.3 The LPCI System injection valves, recirculation pump discharge valves, and LPCI cross-tie valve are powered from the LPCI swing bus, which must remain energized to support OPERABILITY of any required LPCI subsystem. Therefore, verification of proper voltage and correct breaker alignment to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate electrical power sources are available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability ensures that the required voltage is readily available for critical system loads connected to this bus. The 7 day Frequency takes into i account the redundant capability of the AC. DC. and AC swing 4 bus electrical power sources, and other indications avail 6ble in the control room that alert the operator to subsystem malfunctions. | |||
SR 3.5.2.4. SR 3.5.2.6. and SR 3.5.2.7 : | |||
I The Bases provided for SR 3.5.1.3. SR 3.5.1.8. and SR 3.5.1.11 are applicable to SR 3.5.2.4. SR 3.5.2.6. and SR 3.5.2.7. respectively. | |||
l_ FERMI - UNIT 2 B 3.5.2-5 Revision 7 06/18/99 | |||
1 l | |||
* l l | |||
i i | |||
ECCS - Shutdown B 3.5.2 , | |||
1 | |||
' BASES SURVEILLANCE REQUIREMENTS (continued) | |||
SR 3.5.2.5 Verifying the correct alignment for manual, power operated. | |||
and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS I operation. This SR does not apply to valves that are ) | |||
locked, sealed, or otherwise secured in position, since i | |||
- these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation: rather, it involves verification that those valves capable of potentially being mispositioned are-in the correct position. | |||
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is appropriate because the valves are o)erated under procedural control and the probability of t1eir being mispositioned during this time period is low. | |||
In N0 DES 4 and 5, the RHR System may operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal. | |||
Therefore, this SR is modified by a Note that allows one or both LPCI subsystems of the RHR System to be considered OPERABLE for the ECCS function if all the required valves in the LPCI flow path can be manually realigned (remote or local) .to allow injection into the RPV, and the system is not otherwise inoperable. This will ensure adequate core cooling if an inadvertent RPV draindown should occur. | |||
REFERENCES 1. UFSAR, Section 6.3.2. | |||
l FERMI - UNIT 2 B 3.5.2-6 Revision 7, 06/18/99 | |||
W /c /2. 8, 5,1 | |||
(#so see spwmdun e.s.O g[RGENCY COE.E COOLING SYSTD!$ | |||
llM111NG t'ONDITION FOR OPf pATION (Continued) | |||
ACTION': (Continued) | |||
: d. For the ADS: | |||
: 1. With one of the above required ADS valves inoperable, provided the HPCI system, the CSS and the LPCI system are OPERABLE, restore the inoperable ADS valve to OPERABLE status within 14 days or be in at least HOT SIAITDOWN within the next 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours. | |||
: 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours. 1 | |||
: e. With a CSS header AP instrumentation channel inoperable, restore the | |||
<g | |||
* inoperable channel to OPERABLE status within 72 hours or determine the CSS header AP locally at least once per 12 hours; otherwise, declare ggfr. 80 the associated CSS subsystem inoperable. | |||
3,6,I f. With an LPCI or CSS system discharge line " keep filled' alarm instrumentation inoperable, perform Surveillance Requirement 4.5.1.a.1.a. | |||
9 In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.10. | |||
SUPVElllANCE REQUTREMENTS r | |||
yC C-l 4.5.1 The emergency core cooling systeias shall be demonstrated OPERABLE by: | |||
~ | |||
*h a. At least once per 31 days: | |||
$fff$ | |||
: 1. For the CSS, the LPCI system, and the HPCI system h. | |||
a) Verifying [by v/ntino at the dah noint untDthat the system SR35oq ** pipin from the pump otscharge valve to'the system isolation valve is ft led with water, f b) Verifying that each valve, manual, power operated or automatic, in 0R 3.5 7-( the flow path that is not locked, sealed, or otherwise secured in , | |||
position, is in its correct | |||
* position. l M,4 | |||
: 2. For the LPCI system, verifying that the cross-tie valve is open. | |||
SP( [ | |||
*Except fhat an automati valve capable of automat c return to its ECCS po/ tion for another mode of op(ration. | |||
when af ECCS signal is present may be in positt FERMI - UNIT 2 3/4 5 3 PAGE l OF 08 Rev 7 | |||
;. ,_...... P. . | |||
. . . . .. ..A . . | |||
......v. . C.' ,a .1 Spec 4ca.bo n. 35.2 (Als see spee;.sca-(sn. e. s.O Al EMERGENCY CORE COOLING . SYSTEMS SURVEILLANCE REQUIREMENTS (continued) | |||
: 3. For the FCI system, verifying that the HPCI pump flow controller is gc(,,[i&p | |||
~, ' in the correct position. | |||
: b. Verifying that, when pursuant to Specification 4.0.5: | |||
SR =;*E 2* /g 11. The two CSS pumps uala flow[ of~ | |||
,Q 7ressur.e.pf a in,each irefhubs stem together develop | |||
~~ | |||
J3:335j0 1 jus 4Tspst ' te no 270 Aigy.colVesinin' din'g to a reac6r~ vessel pressure of a 100 psig. | |||
: 2. Each LPCI pump in each subsystem develops a[ low of at least 10,000 gpm(Ana'tht Go 'line.pftstarftf a nuAsi esponding to a ressure of a 20 | |||
~ | |||
reactor vessel o pri ri con 6ai. .d d iii.. ...o a psig. - /l, / O | |||
$CO 3. The HPCI pump develops a flow of at least 5000 gpm in the test flow | |||
*t path with a system head corresponding to reactor vessel operating gflQ;Mion, 3' | |||
l pressure including injection line losses when steam is being supplied | |||
( Q o the turbine at 1025 +20. -80 psig.* | |||
i | |||
: c. At least once per 18 months g-[g ( o f- M./f | |||
: 1. FortheCSS,theLPCIsystem,ddtheHPCIsystem)performinga G R, 5.E.2 7 system functional test which includes, simulated automatic actuation gg of the system throughout its emergency operating sequence and , | |||
verifying that each automatic valve in the flow path actuates t.9 its correct position. Actual injection of coolant into the reactor vessel may be excluded from this test. | |||
: 2. or the HPCI system verifying that: | |||
a) The systes develops a flow of at least 5000 gpa in the test flow path with a system head corresponding to reactor vessel operating pressure including injection line losses when steam is being supplied to the turbine s | |||
at 165 + 50. ,0 psig.* | |||
$" 60' , | |||
I b) The suction for the HPCI system is automatically transferred from gyCO {', gat /ou the condensate storage tank to the suppression chamber on a bq ,) condensate storage tank water level - low signal and on a suppression chamDer - water levei high signal. | |||
: 3. Performing a CHANNEL CAllBRATION of the CSS and the LPCI system discharge line ' keep filled" alarm instrumentation. | |||
4 Performing a CHANNEL CAllBRATION of the CSS header AP instrumentation and verifying the setpoint to be s the allowable value of 1.0 psid. | |||
L qcd | |||
*The provisions of Specification 4.0.4 are not appitcable provided the th.e surveillance is performed within 12 hours after reactor steam pressure is sfeCII 3,6,I adequate to perforu the test. | |||
FERMI - UNIT 2 3/4 5 4 Amendment No. 87 PAGE c2 0F 08 kel 7 | |||
: ji ' f. h . g.S r- . | |||
\ | |||
$fECtF1cAnerl 55.2-rMrRCfNEY r0Rr root TNG SVUFNS 3/4 5 7 F rrS - SHUTD alN ' | |||
IIMITING CONDITION FOR OPERATION | |||
/ | |||
3.5.2 At least two f the f lowing (subsystemsshallbeOPERABLE: | |||
[ a. re spray syst (CSS) subsyst with a subsystem rised of: | |||
: 1. At leas two OPERABLE C5 p g s and | |||
: 2. An E ficw path apable of taking s tion from at 1 st one f the following ater sources and t nsferring the t ths spray = caer to the reacto vessel f q | |||
-4 %Lew,;;;;; it, e l' i 1 When the suppression chamber water level is less than h SR 3.6,7.7- limit required in Specification 3.5.3 or is drained. rom the condensate storage tank with an indicated level of at least 19 ft. | |||
. Low essure coolant inj ion u.P w system uusmcm. . m . | |||
su ystem conprised of: LA.l At least two OP LE LPCI (RHR) , and l | |||
. An OPERABLE path capable of aking suction from t suppression amberandtransferingthewatertothefeactor | |||
, cem1** | |||
APPL TrARfl ITY: OPERATIONAL CONDITION 4 cnd $*. | |||
ACIIDti: | |||
4 Cries A .<r- Witn one of the above required subsystem (s) inoperable, restore at least two subsystem (s) to OPERABLE status within 4 hours or suspend ' I AGD# D all operations with a potential for draining the reactor vessel. | |||
AcTto4 C / ,With both of the | |||
;Xn=:""U:nd allabove required operations withsubsystem a potential(s)for inoperable. suspen 40RE, draining the rearte: vessel. Restore at least one subsyntem to OPERABLE 4tatus Mod p wi's.m 4 hours or tabli h(5ECONDARY CONTA' mirNT Ihi hlTDyithin. | |||
v- - - : r .. in;4;a . | |||
'~~.. usm ro - | |||
g;V The ECCS is not required to RABLE provided that t R c: r'r- = ' | |||
pplW f -heart-trymurramrr the cavity is flooded, the spent fuel pool cates are T .2O | |||
,. removed.andwaterlevelismaintainedwithinthelimitsof(SmiGiet;E e JZ. | |||
.) "1 E1 et -J in in | |||
**Ni's'ubsyith[s)maybeconsideredOPERABLEduringalignmentandoperation | |||
$235.2.E for decay heat removal if capable of being manually realigned and not NN otherwise inoperable. | |||
FERMI - UNIT 2 3/4 5 6 Amendment No. 226.131 PAGE 3' 0F 08 /fev '7 | |||
I I | |||
l SPecSic+ nod 3.5 2-(Aiso n %,n 3.c. 2.2) \ | |||
6 ' | |||
LINf71NS CONDfTION FOR OPERATION 3.5.3 The suppression chamber shall be OPEMBLE: | |||
f *-c a. In OPEMTIONAL CON 0!TIONS 1, 2, and 3 with a contained water volume of LLo 3,6.2 2 <(at least 121.080 fts, equivalent to a level of 24'4' (.! inches i | |||
findication). 44.3 | |||
$ 4 3 5'.2 .I b. In W aa"t m i m a m m a w se e a 4 dnad 4 une ofit led car saaj ;e. -- ^'elent to agevel af t'0"_A.55 < nches ' natcat1on), | |||
g4 3 5,2 2.cl 'except taat the suppression enameer sevel may be less than the limit or may be drained provided that: cJ SCT!pA) 6 .h Nooperationsareperformedthathaveapotentialfordrainingf s 8. 35 2.2.b Nole. the reactor vessel, T or switch is kedinthe5[tdownorfj pt3 5.2.~1.b 4 The condensate storage tank water level is at least 19 ft., and | |||
-4. The core spray system is OPEMBLE per Specification 3.5.Z with g g'g,1 an OPEMBLE flow path capable of taking suction from the 4 g g, 3,g,2,? . h conjensate storace tank ano sr.nsp.. mv uir -- J -- --- snur l | |||
-rar soarnerAo the reattor vesstl.1 L n. | |||
APPLICARILITY: OPERATIONAL CON 0!T10N$(I, 2, 3h4, and 5*} l | |||
: g. Sa.c Lt.h 3.G.7..'L L g3,gy g* In OPEMTIONAL CONDIT!0N 1. 2. or 3 with the suppression chamber water | |||
: a. (level less than the above limit, restore the water level to within the | |||
/Lo 34 2.'2- limit within I hour or be in at least HOT SHLTTDOWN within the next 1 N i 1@/ rs and in CDLD SHL1TDOWN w thin t ollowing 24 hqurs. | |||
9 bas i .lC5s encsy) | |||
,3 1 | |||
{ | |||
: b. In OPERATIONAL CONDITION or5'withthesuppression)chamberwater Acy;ndC,O level less than the above limit orJrained and the ahnve reevired l'l conditions not satisfied, suspendkDKt ALnRATIDNS andlall operations that have a potential for draining the reactor vesse' M M ' '' 14 A.I Ir I(I i( .Y. FhT{I' ~* j GniBay ufn W | |||
*The sunoressten e"=h-r is not required to be OPERABLE provided that the h | |||
g'3 MgcaYg dyactor vessel head is removeTJthe cavity is flooded, or being flooded j rom the . ,,sssion pool, the spent fuel pool gates are .. - .. wnen tne cavity is flooded, and the water level is maintained within the limits of g (Specif'Ications 3.3.5 and 3.3.v. 3 , | |||
FERMI . UNIT 2 3/4 5 8 Amendment No.131 PAGE 5' 0F 08 Rev 7 | |||
Sgec/ka t/o 7; 7. S. '_ | |||
(h5O MC SPecMed to rt y.3.y) | |||
ELECTReCAL A,yj D STEMS Ccc . | |||
SURVEf ttANCE REOUIREMENTS / | |||
crec$cdr.oh 3 8. B '/ | |||
g o.5.2.3 4 .8.3.2. t least the bove reauired a~-- Mistribution system division)and the swing bus snais ou cetermined energized at least once per 7 days by ~~ | |||
verifying correct breaker alignment and voltage on the busses / cabinets, f4.8.3. 2 The A.C. power distribution system swi g bus automatit throw i sch shall be demonstr ted OPERABLE at least ce per 31 days by man 11y | |||
* ope ng position 3C bu 72C and verifying that he automatic transfe scheme df3 } | |||
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i FERMI UNIT 2 3/4 8-15a Amenament No. 29 | |||
.) | |||
PAGE F 0F 08 | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 - ECCS-Shutdown A.5 CTS 4.5.3.2.b requires verification every 12 hours that footnote | |||
"*" to the' Applicability of CTS 3.5.3. Suppression Chamber, is satisfied. ' Footnote "*" is a list of the conditions required before the suppression pool may be made inoperable. When plant conditions are in accordance with CTS 3.5.3. footnote "*". the LC0 i is not required to be met, and therefore CTS 4.5.3.2.b is not required to be performed. As such this surveillance is never required to be performed. Therefore, deletion of CTS 4.5.3.2.b is an administrative change. I A6 CTS 4.5.3.2.a requires verification every 12 hours that the conditions of CTS 3.5.3.b are satisfied whenever the suppression chamber is drained or less than the required level. If the suppression pool is at less than the required level. Core Spray must be lined up to the Condensate Storage Tank. Additionally, in l accordance with CTS 3.5.3.b. operations with a potential to drain the reactor vessel (0PDRVs) are prohibited under these conditions and the CST level must be maintained within required limits. ITS SR 3.5.2.2 verifies the same requirements at the same Frequency as ' | |||
CTS 4.5.3.2.a. Therefore, this is an administrative change with no impact on safety. | |||
A.7 In Modes 4 and 5, with the suppression pool drained or less than the required limit CTS LCO 3.5.2 allows the two Operable ECCS l systems to be satisfied by two CS subsystems with suction aligned to the CST. In the event one of the two CS subsystems becomes ! | |||
inoperable. Action a requires suspending operations with a potential for draining the vessel (0PDRV) after 4 hours, but i allows unrestricted continued operation with only one Operable CS subsyste'm once OPDRV are suspended. Similarly CTS 3.5.3.b ! | |||
permits both CS subsystems to be Operable when lined up to the CST. but only if no OPDRV are in progress (CTS 3.5.3 b.1). ITS I implements the same requirements: LC0 3.5.2. Actions A and B. | |||
provide the same 4 hours as CTS 3.5.2 to suspend OPDRV when one of b l the required CS subsystems becomes inoperable: and the Note to SR 3.5.2.2.b precludes OPDRV while the two required ECCS subsystems d consist of two CS subsystems aligned to the CST. This is an ' | |||
administrative change with no impact on safety because the ITS requirement is consistent with the requirements of CTS 3.5.2. The j k | |||
additional 4 hours compared to CTS 3.5.3 is addressed by DOC L.3. | |||
FERMI.- UNIT 2 2 REVISION 7 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown A8 CTS LC0 3.8.3.2.a.3 requires the LPCI swing bus to be Operable, and I the associated Action c requires declaration of LPCI inoperability with the swing bus-inoperable (i.e.. not energized or automatic ^ | |||
throwover scheme inoperable). The ITS provides this intent within the ECCS Specification, without separately specifying Operability of the swing bus in another Specification. The ITS recognizes that LPCI is inoperable with the swing bus inoperable (ITS Bases specifically discusses). Therefore both the ITS ar.d CTS Actions for an inoperable swing bus are the same. This administrative presentation preference does not result in any technical changes. | |||
Therefore, this is an administrative change with no impact on safety. | |||
C A.9 Not used. | |||
e | |||
) | |||
A.10 CTS 4.5.1.b.2 specifies that the LPCI pump flow verification test " | |||
be performed at a pressure corresponding to a reactor vessel to primary containment differential pressure (psid) greater than or equal to the value assumed in the safety analysis. ITS SR 3.5.1.8 and SR 3.5.2.6 specify that the LPCI pump flow test be performed l at a system head corresponding to a reactor pressure greater than or equal to the value assumed in the safety analysis. This change was made to make the test description for the LPCI test the same as that currently used for the CS test. Both tests are intended to verify the flow rates at the reactor pressures assumed in the safety analysis, NEDC 32071P. . Table 4 3. NEDC 32071P, Table 4-3 footnote (1), indicates that the pressures assumed for LPCI or CS pump injection and the values at which the pumps are tested is expressed in' " vessel to drywell differential pressure." The acceptan~ce criteria used for ITS SR 3.5.1.8 (and ITS SR 3.5.2.6) l A> l 1s expressed as minimum flow rate against a system head j corresponding to reactor pressure. This criteria is clarified in the Bases which states that pump flow rates are verified against a system head equivalent to the elevation head pressure between the pump. suction and the vessel discharge, the piping friction losses, and RPV pressure present during a LOCA. The SR acceptance criteria is presented in "psig" (instead of psid) and clarified in the Bases to ensure that the flow verification test .is not I | |||
l I | |||
I FERMI UNIT 2 3 REVISION 7 06/18/99l 1 | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown performed based on pump differential pressure alone. This is an administrative change because there is no change to the existing requirement to test the CS and LPCI pumps at the pressures and flows assumed in the safety analysis. | |||
A.11 CTS 4.5.1.c.1 requires the performance of a system functional test that includes " simulated automatic actuation." ITS SR 3.5.2.7 permits the system functional to be initiated by an " actual or lh simulated" automatic initiation signal. This change allows satisfactory automatic system initiations to be used to fulfill the system functional Surveillance Requirement. Operability is adequately demonstrated because the ECCS subsystem can not discriminate between " actual" or " simulated" initiation signals. | |||
This is an administrative change with no impact on safety because it is a reasonable interpretation of the existing requirement. | |||
A.12 CTS 3.5.2 and 3.5.3, Applicability footnote "*", provides an allowance for ECCS to be not required when the refueling cavity water level is "within the limits of Specification 3.9.8 and 3.9.9." l The ITS simply states this provision as a single required water level. Since the allowance only applies when the spent fuel pool gates are removed, the water level can be referenced from a single point, and be known to satisfy both CTS 3.9.8 and 3.9.9. This bounding level is presented in the ITS. This is a presentation , | |||
preference only, with no technical change. Therefore, this change is administrative. | |||
A.13 CTS 4.8.3.2.2 requires demonstration of the LPCI swing bus automatic throwover scheme; however the associated LC0 only requires ~ that the LPCI swing bus be energized from the one required energized division. In this condition (only one division energized), the automatic throwover performs no safety function since there is not a second division to throwover to. | |||
Furthermore, the associated actions only provide for actions to be taken if the swing bus is de energized: no action is provided for an inoperable throwover scheme, and the provisions of LCO 3.0.3 are also not applicable. Therefore, the CTS presentation for LPCI swing bus automatic throwover scheme while in the shutdown Modes, does not contain any functional requirements or limitations. As such. ITS provides an enhanced presentation by not including the superfluous Surveillance wording. Therefore, this change is solely an administrative presentation preference. | |||
FERMI UNIT 2 4 REVISION 7 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 - ECCS-Shutdown TECHNICAL CHANGES - MORE RESTRICTIVE j M.1 CTS 3.5.2 and 3.5.3. Action b. require that secondary containment integrity be established "within 8 hours" when both required ECCS | |||
' subsystems are inoperable while shutdown. ITS 3.5.2. Action D. | |||
requires operators to " Initiate action" immediately to establish the essential elements of secondary containment but does not specify a completion time. The CTS establishes completion times for Required Actions that, depending on plant conditions, may not be achievable in the required time. Conversely, plant conditions may be such that the actions could be accomplished in c shorter time than is required. Therefore. CTS Required Actions appear to I provide a period of time in which it is not necessary to establish the desired plant conditions even if those conditions can be readily established. Conversely, if plant status is such that the desired plant conditions cannot be established in the required time the CTS required actions result in non compliance with the Technical Specifications and an Licensee Event Report will be required. ITS rore appropriately establishes the required actions as " Initiate action" immediately to establish the desired plant conditions. | |||
This change eliminates an CTS allowance to delay establishing the condition for up to the specified action time and replaces it with a requirement to establish the desired condition as quickly as is reasonably achievable. However, by eliminating the CTS completion times, an LER is not required if best efforts to establish the condition take longer than the time specified in the CTS. This is a more restrictive change with no negative impact on safety. | |||
r I | |||
TECHNICAL CHANGES LESS RESTRICTIVE l | |||
" Generic" LA.1 CTS LC0 3.5.2 and 3.5.3 include details relating to system design. ' | |||
function, and Operability for the core spray system and the LPCI System while shutdown. ITS 3.5.2 includes only a requirement for ! | |||
Operability and moves details of Operability and system design d ! | |||
requirements to the Bases. This is acceptable because these bE/ | |||
details do not impact the ITS requirement to maintain the systems l Operable. Therefore, these details can be adequately defined and I controlled in the Bases which require change control in accordance | |||
~ | |||
, with ITS 5.5.10. Bases Control Program. These details are not required to be in the ITS to provide adequate protection of the FERMI UNIT 2 5 REVISION 7 06/18/99l l i | |||
l l 4 DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown public health and safety acceptable because relocating these details does not impact the requirement to maintain the equipment Operable. ) | |||
) | |||
LA.2' CTS 4.5.2.1 refers to the ECCS Operating surveillances that also apply to ECCS Shutdown, and also provides an exception for the position of the LPCI cross tie valves. This exception is a detail of the " correct position" of the system's valves and is relocated to the ITS LC0 3.5.2 Bases. ITS SR 3.5.2.5 includes only a l requirement for valves to be aligned to their correct position and moves details of the position needed to support Operability and system design requirements to the Bases. This is acceptable because the these details do not impact the ITS requirement to maintain the valves properly aligned and the system Operable. | |||
Therefore, these details can be adequately defined and controlled in the Bases which require change control in accordance with ITS l 5.5.10. Bases Control Program. These details are not required to be in the ITS to provide adequate protection of the public health and safety acceptable because relocating these details does not impact the requirement to maintain the equipment Operable. | |||
LA.3 CTS 3.5.3.b and CTS 4.5.3.1.b include details that relate required suppression pool volume to its respective indicated level. ITS (T | |||
T/ | |||
l i | |||
3.5.2 includes only the required level and moves details of system design to the B9ses. The Bases require change control in accordance with ITS 5.5.10. Bases Control Program. These details ! | |||
are not required to be in the ITS to provide adequate protection l of the public health and safety acceptable because relocating ' | |||
these details does not impact the requirement to maintain the equipment Operable. | |||
LA.4 The following CTS details for performing Surveillances are not j included in the ITS. These detailed methods for performing l | |||
Surve111ances are moved to the Bases l: | |||
: a. CTS 4.5.1.a.1.a details a requirement for verifying that ' | |||
the system is filled with water. "by venting at the high point vents": | |||
: b. CTS 4.5.1.a.2 contains a footnote "*" which details a requirement for the correct position of ECCS valves: | |||
: c. CTS 4.5.1.b.1 and 4.5.1.b.2 details test line pressure requirements for the CSS and LPCI pumps: and ! | |||
FERMI UNIT 2 6 REVISION 7 06/18/99l l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown These details can be adequately defined and controlled in the Bases, which require change control in accordance with Chapter 5 of the ITS. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the details in the ITS are adequate for performing the required Surveillances. | |||
LR.1 CTS 3.5.3.b.2 and CTS 3.5.3. Action b. requires locking the mode switch in Shutdown or Refuel when ECCS is not available because of l insufficient water inventory in the Suppression Pool in Modes 4 or 5. Under the same conditions. ITS 3.5.2. Action B takes appropriate actions which do not include locking the mode switch in shutdown or refuel. This change is acceptable because the action to place the mode switch in the proper position remains a Technical Specification requirement, while the requirement to lock i the mode switch in shutdown or refuel to prevent reactor startup I when the suppression pool is drained is an administrative control intended to prevent violation of other Technical Specifications. | |||
Therefore, the requirement to lock the mode switch to prevent violating requirements is an administrative control that is not necessary to be controlled by license amendment or 10 CFR 50.59. ; | |||
This detail is not required to be in the ITS to provide adequate l protection of the public health and safety and is acceptable because the action to place the mode switch in the proper position l remains a Technical Specification requirement. ! | |||
TECHNICAL _ CHANGES LESS RESTRICTIVE | |||
''Speci fi c" | |||
~ | |||
L.1 CTS 3.5.2. Action b and CTS 3.5.3. Action b. require the suspension of Core Alterations when no ECCS is available. ITS 3.5.2 does not retain this requirement because ITS refueling LCOs provide requirements to ensure safe operation during Core Alterations including required water level above the RPV flange ' | |||
and the position of the mode switch. The ECCS function enforced by ITS 3.5.2 is intended to provide protection for loss of vessel inventory events. However, a loss of vessel water inventory is ' | |||
not initiated by Core Alterations and the response to a loss of vessel water inventory is not hampered by Core Alteration operations. Therefore, this change has no impact on safety. , | |||
FERMI UNIT 2 7 REVISION 7 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown L.2 Not used. | |||
lh L.3 CTS 3.5.2 requires two low pressure emergency core cooling subsystems to be operable. If one of the required systems is inoperable. Action a. allows 4 hours to get back to two operable subsystems. Otherwise. it requires the licensee to suspend operations with a potential for draining the reactor vessel (0PDRVs). CTS 3.5.3 requires the suppression pool to be operable but allows the level to be below the limit (including completely drained) in Modes 4 and 5 provided certain conditions are met. | |||
One of these conditions is that no OPOWs are performed. The two TS are related because the suppression pool is.the suction source for the LPCI subsystems and one of the possible suction sources for the CSS subsystems. If the suppression pool level is below l | |||
the limit in CTS 3.5.3.b. the LPCI subsystems would be inoperable l and the CSS subsystems would be operable only if there was adequate water in the condensate storage tank (CST) and the CSS subsystems were aligned to take suction from the CST. With both CSS subsystems operable with suction from the CST CTS 3.5.2 would i not prohibit performing OPDRVs. However. CTS 3.5.3.b would prohibit OPDRVs because the suppression pool level is below the limit. | |||
In ITS 3.5.2. the aspects of CTS 3.5.2 and 3.5.3 related to the operability of ECCS are combined. . SR 3.5.2.2 requires the i licensee to verify that the suppression pool level is within g limits or that adequate volume is available in the CST. However, k a note to this SR indicates that only one CSS subsystem can take credit for the CST as a suction source during OPDRVs. Under these circumst'ances (performing OPDRVs). Action A is entered for one of the two required subsystems inoperable. This would allow 4 hours to restore a second subsystem. If this time is not met (which would happen if the suppression pool is intentionally drained). | |||
Action B. requires actions to suspend OPDRVs. | |||
This 4 hour extension to the requirements of CTS 3.5.3 when the operability of only one ECCS subsystem is impacted. does not result in a significant impact on safety due to the following: | |||
: 1) the allowance is consistent with that approved in CTS 3.5.2 Actions: 2) the availability of the remaining operable subsystem: | |||
; and 3) the low probability of an event during this limited time. | |||
I FERMI UNIT 2 8 REVISION 7 06/18/99l | |||
e DISCUSSION OF CHANGES ITS: SECTION 3.5.2 - ECCS-Shutdown i I | |||
l | |||
(. RELOCATED SPECIFICATIONS-None- | |||
+ | |||
TECHNICAL SPECIFICATION BASES The CTS Bases for this Specification have been replaced by Bases that reflect the. format.and applicable content of ITS 3.5.2 consistent with the BWR STS. | |||
NUREG 1433. Rev. 1. | |||
i l 'i l | |||
l 1 | |||
3 l | |||
. FERMI'-' UNIT 2 9 REVISION 7 06/18/99l | |||
) | |||
ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY (C T$ ) | |||
SR 3.5.2.2 Verify, f or each required core spray (CS) 12 hours i subsystem, the: 4. '/, p , 2 , Q (35.3,b) l i a. Suppression pool water level is P.I (3.5,5.6.l) i - -- | |||
TE---- - | |||
l Only one required CS subsystem may | |||
{j g g a edit for this option during 7,g,3, f 4 ) | |||
l 3* | |||
i i | |||
Condensate storage tank water level is [ 3.6.3. 6 3) f 2 f4 M +]. | |||
M'- | |||
l m h3..s5.. 2,,6 n >, f ') @)' | |||
i SR 3.5.2. Verify, for each required ECCS injection / | |||
l spray subsystem, the piping is filled with 31 days N /g* g,7,/ l\ 'b Y water from the pump discharge valve to the I injection valve. | |||
d4.5./.a..LQ | |||
- A SR 3.5.2.4' | |||
--9;w LPCI subsysteg may be considered | |||
<45J,fh L h,l O6 OPERABLEduringaTIgnmentandoperationfor decay heat removal if capable of being Q.T.2 b 4Y) manually realigned and not otherwise inoperable. | |||
Verify each required ECCS injection / spray 31 days ,3, p. / j subsystem manual, power operated, and l automatic valve in the flow path, that is 1 | |||
- not locked, sealed, or otherwise secured in ,[/. d . /. b) position, is in the correct position. | |||
(continued) | |||
-:ra/4 STS- 3.5-9 -P= 1 ^'/^7/05 | |||
_.s i | |||
i | |||
--,yc ECCS-Shutdown 3.5.2 l | |||
l J_NSERT 3.5.2-1 i \ | |||
l 1 | |||
SR.3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. | |||
6 l | |||
l 1 | |||
i e | |||
FERMI UNIT 2 Page 3.5 9 (Insert) REVISION 7. 06/18/99l | |||
o ECCS-Shutdown 3.5.2 SURVEILLANCE REOUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY ( C TS ) | |||
SR 3.5.2.f Verify each required ECCS pump develops the 5accordanc specified flow rate [against a system head with the , | |||
(7 corresponding to the specified reactor ;cInservice M I pressure). Testing Program ee-b | |||
[ SYSTEM HEAD NO. CORRESPONDING "2 2.,;- | |||
P.i Or TO 4 REACTOR - - | |||
SYSTEM FLOW RATE Bt!PJ PRESSURE OF1 | |||
, g, 7, j CS 2 gpu 2 psig LPCI 2-J300, gpa 1:1) 2 ( # =psig h'8e/*d/ i g @ { 4 5. l.f. 2 } | |||
SR 3.5.2.f NOTE ------- | |||
Vessel injection / spray may be excluded. | |||
/g,5,f./) | |||
\ | |||
/ | |||
(4.5. l. C.I} | |||
Verify each required ECCS injection / spray ;{18} months subsystem actuates on an actual or j simulated automatic initiation signal. ~ | |||
l | |||
- WR/, aTS-~ 3.5-10 au 1, W /; /S; --- | |||
@v7 | |||
i ECCS-Shutdown B 3.5.2 BASES ACTIONS C.1. C.2. D.1. D.2. and D.3 (continued) { | |||
necessary to perfom the Surveillances needed to demonstrate the OPERABILITY of the components. If, however, any required component is inoperable, then it must be restored i to OPERABLE status. In this case, the Surveillance may need ! | |||
to be performed to restore the component to OPERABLE status. | |||
Actions must continue until all required components are OPERABLE. | |||
l The 4 hour Completion Time to restore at least one low pressure ECCS injection / spray subsystem to OPERABLE status ensures that prompt action will be taken to provide the required cooling capacity or to initiate actions to place the plant in a condition that minimizes any potential fission product release to the environment. | |||
^ | |||
l | |||
~ | |||
) | |||
SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 id:ca+im of -4 inckes ( ! | |||
REQUIREME S O 9 dchaA hve O) l p't The minimum water level )Dt ft 1 inches equired for The suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for the CS System and LPCI subsystem pumps, recirculation volume, and vortex prevention. With the suppression pool water level less than the required limit, all ECCS injection / spray subsystems are inoperable unless they are aligned to an OPERABLE CST. | |||
- 4G in l When suppression pool level is < .. ._ _ -.,, e CS ! | |||
System is considered OPERABLE only if it can take suction l from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a | |||
-(4 verification that either the suppression pool water level 2 6 .i r inchesF or that CS is ali ged to take suction 'po ce from the esT mad ths. CST contains 2 "",-::L ailons of wate equivalent to N ft_. ensures that the CS System can upplyatleast{!!,^^^7gallonsofmakeupwa,terTtotheRPV ! | |||
The CS suction is uncovered at the i 00,000Nallon leve o 3^ | |||
- may ta %. | |||
However, as noted, only one required CS subsystem f N gin fo ke I credit for the CST option during OPDRVs. During OPDRVs, the precb4M N volume in the CST may not provide adequate makeup if the RPV )4 7.;,m Men were completely drained. Therefore, only one CS subsystem i , | |||
l is allowed to use the CST. This ensures the other required i ECCS subsystem has adequate makeup volume. | |||
(continued) | |||
- Mi ' E - B 3.5-20 L,1, ;;;;rja; w' | |||
I | |||
i ECCS-Shutdown B 3.5.2 ! | |||
BASES SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 (continued) | |||
REQUIREMENTS The 12 hour Frequency of these SRs was developed considering operating experience related to suppression pool water level and CST water level variations and instrument drift during ; | |||
the applicable MODES. Furthermore, the 12 hour Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the operator i to an abnormal suppression pool or CST water level ! | |||
.j g g rCT- condition. | |||
l 7 Y g,g O j p . | |||
I SR 3.5.2. . SR 3.5.2.$.andSR 3.5.2.4 ' | |||
W The laseg provided for SR 3.5.1 SR 3.5.1. and i | |||
// R 3.5.I3tr are applicable to SR 3.5.2 SR 3.5.2 A and SR 3.5.2 respectively. y gG, ; | |||
SR 3.5.2] | |||
Verifying the correct alignment for manual, power operated, I' ! | |||
and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves were verified to be in the correct position < | |||
prior to locking, sealing, or securing. A valve that i receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it | |||
' involves verification that thase valves capable of potentially being mispositioned are in the correct position. l This SR does not apply to valves that cannot be | |||
{ | |||
inadvertently misaligned, such as check valves. The 31 day , | |||
Frequency is appropriate because the valves are operated under procedural control and the probability of their being ' | |||
- mispositioned during this time period is low. | |||
In MODES 4 and 5, the RHR System may operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal Therefore, this SR LPCI subsystengof is modified the RHR bybeaconsidered System to Note thatOPERABL allows one or dofh g'j (continued) : | |||
BWR/ M T P B 3.5-21 ";. ;, ^'l0?/00 | |||
' mes8 | |||
l 1 | |||
ECCS Shutdc,wn B 3.5.2 INSERT B 3.5.2 1 l | |||
SR 3.5.2.3 i The LPCI System injection valves, recirculation pump discharge valves, and'LPCI cross tie valve are powered from the LPCI swing bus, which I must remain energized to support OPERABILITY of any required LPCI l subsystem. Therefore, verification of proper voltage and correct i breaker alignment to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate electrical power sources are j available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability j ensures that the required voltage is readily available for critical i system loads connecte'd to this bus. The 7 day Frequency takes into account the redundant capability of the AC, DC, and AC swing bus ' | |||
electrical power sources, and other indications available in the control room that alert the operator to subsystem malfunctions. | |||
i FERMI UNIT 2 Page B 3.5 21 (Insert) REVISION 7 06/18/99l | |||
.__ e. . .-...c.. .d . . . .. e ,, | |||
1 | |||
.. ......x....,..,. . ;...._.__.a _ __ | |||
l ECCS-Shutdown B 3.5.2 BASES | |||
- / | |||
SURVEILLANCE SR 3.5.2.4 (continued) b'3 REQUIREMENTS for the ECCS function if all the required valves in the LPCI ' | |||
flow path can be manually realigned (remote or local) to , | |||
allow injection into the RPV, and the system is not otherwise inoperable. This will ensure adequate core | |||
. cooling if an inadvertent RPV draindown should occur. | |||
REFERENCES | |||
: 1. (AFSAR, Section 16.3.2J. ! | |||
l I | |||
l 9 | |||
9 | |||
-BWR/41W B 3.5-22 Re@4lc7jo3-L l | |||
Aev 7 | |||
. t * | |||
< l% | |||
p: | |||
l JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.5.2 ECCS Shutdown | |||
'NON BRACKETED' PLANT SPECIFIC CHANGES | |||
, P.1 These changes are made to NUREG-1433 to reflect Fermi 2 current licensing basis:' including design features, existing license l r'equirements and comitments. Additional rewording, reformatting, l 'and revised numbering is made to incorporate these changes consistent j | |||
with Writer's Guide conventions. | |||
; P.2 Bases' changes are made to reflect plant specific oesign details. | |||
! . equipment terminology, and analyses. Some of these changes are specifically discussed below: | |||
; a. LCQ: In the NUREG (based on non LPCI loop select logic plants). | |||
l- the cross tie valves would be required to be closed during Modes l | |||
1, 2. and 3 and 3.5.2 Bases discuss how this is not required in | |||
! shutdown Modes. However, with the Fermi-2 LPCI loop select logic, the cross-tie valves are required to be open in Modes 1 | |||
: 2. and 3. Therefore the Bases for the shutdown Modes is revised to reflect the exception for the Fermi-specific design. | |||
1 FERMI - UNIT'2 1 REVISION 7. 06/18/99 l u | |||
] | |||
i NO SIGNIFICANT HAZARDS EVALUATION ITS:.SECTION 3.5.2.- ECCS - Shutdown l | |||
TECHNICAL CHANGES LESS RESTRICTIVE (Soccification 3.5.2 "L.2" Labeled Coments/ Discussions) | |||
/ | |||
Not used. l | |||
:s : | |||
d g | |||
I w | |||
FERMI UNIT 2 3 REVISION 7 06/18/99l | |||
NO SIGNIFICANT HAZARDS EVALVATION ITS: SECTION 3.5.2 - ECCS - Shutdown l | |||
TECHNICAL CHANGES - LESS RESTRICTIVE i (Scecification 3.5.2 "L.2" Labeled Comments / Discussions) ! | |||
l i | |||
+ | |||
Not used. | |||
l FERMI UNIT 2 4 REVISION 7, 06/18/99l | |||
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.5.2 ECCS - Shutdown TECHNICAL CHANGES - LESS RESTRICTIVE ISoecification 3.5.1 "L.3" Labeled Comments / Discussions) | |||
Detroit Edison has evaluated the proposed Technical Specification change identified is "Less Restrictive" in accordance with the criteria specified by 10 CFR 50.92 and has determined that the proposed change does not involve a significant hazards consideration. | |||
The bases for the determination that the proposed change does not involve a significant hazards consideration is an ovaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below. | |||
: 1. Does the change involve a significant increase in the probability or consequencc: of an accident previously evaluated? | |||
The proposed change allows 4 hours to restore two ECCS subsystems to operable status with at least one aligned to the suppression pool, prior to requiring suspension of OPDRVs. . This change will not significantly increase the probability of an accident previously evaluated because the amount of time allowed to restore equipment to 4 l s | |||
operable does not affect the initiators of any analyzed accident. This ' | |||
j change will not significantly increase the consequences of any accident previously evaluated because the remaining operable ECCS subsystem would k j be available to perform the core flooding function. | |||
: 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated? | |||
This proposed' change will not involve any physical changes to plant systems, structures or components (SSC). The changes in normal plant operation are not in conflict with any current safety analysis assumptions. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. | |||
FERMI - UNIT 2 5 REVISION 7 06/18/99l | |||
INSERT THIS PAGE IN FRONT OF VOLUME 6 , | |||
l Volume 6 SECT 1.ON 3.5. | |||
Remove Replace 3.5.1 ITS pg 3.5-3 Rev 0 3.5.1 ITS pg 3.5-3 Rev 7 3.5.1 ITS pg 3.5-4 Rev 0 3.5.1 ITS pg 3.5-4 Rev 7 3.5.1 ITS pg 3.5-5 Rev 0 - 3.5.1 ITS pg 3.5-5 Rev 7 3.5.1 ITS pg 3.5-6 Rev 0 3.5.1 ITS pg 3.5-6 Rev 7 3.5.1 ITS pg 3.5-7 Rev 0 3.5.1 ITS pg 3.5-7 Rev 7 3.5.1 ITS pg 3.5-8 Rev 0 -- | |||
B3.5.1 ITS pg B 3.5.1-3 Rev 0 B3.5.1 ITS pg B 3.5.1-3 Rev 7 B3.5.1 ITS pg B 3.5.1-9 Rev 0 B3.5.1 ITS pg B 3.5.1-9 Rev 7 B3.5.1 ITS pg B 3.5.1-11 Rev 0 B3.5.1 ITS pg B 3.5.1-1I Rev 7 B3.5.1 ITS pg B 3.5.1-13 Rev 0 B3.5.1 ITS pg B 3.5.1-13 Rev 7 B3.5.1 ITS pg B 3.5.1-17 Rev 0 B3.5.1 ITS pg B 3.5.1-17 Rev 7 3.5.1 CTS M/U (3/4 3-23) pg 1 of 10 3.5.1 CS M/U (3/4 3-23) pg 1 of 10 Rev 7 3.5.1 CS M/U (3/4 4-2) pg 2 of 10 3.5.1 GS M/U (3/4 4-2) pg 2 of 10 Rev 7 3.5.1 GS M/U (3/4 5-3) pg 5 of 10 3.5.1 CTS M/U (3/4 5-3) pg 5 of 10 Rev 7 3.5.1 CS M/U (3/4.7-3) pg 8 of 10 3.5.1 CS M/U (3/4 7-3) pg 8 of 10 Rev 7 3.5.1 DOCS pg 6 Rev 0 3.5.1 DOCS pg 6 R, 7 . | |||
3.5.1 DOCS pg 7 Rev .0 3.5.1 DOCS pg 7 Rev 7 3.5.1 DOCS pg 8 Rev 0 3.5.1 DOCS pg 8 Rev 7 3.5.1 DOCS pg 9 Rev 0 3.5.1 DOCS pg 9 Rev 7 3.5.1 DOCS pg 10 Rev 0 3.5.1 DOCS pg 10 Rev 7 3.5.1 DOCS pg 1I Rev 0 3.5.1 DOCS pg i1 Rev 7 3.5.1 DOCS pg 12 Rev 0 3.5.1 DOCS pg 12 Rev 7 3.5.1 NUREG M/U pg 3.5-2 3.5.1 NUREG M/U pg 3.5-2 Rev 7 ! | |||
3.5.1 NUREG M/U pg 3.5-3 3.5.1 NUREG M/U pg 3.5-3 Rev 7 3.5.1 NUREG M/U pg 3.5-4 (insen) Rev 0 3.5.1 NUREG M/U pg 3.5-4 (insen) Rev 7 3.5.1 NUREG M/U pg 3.5 5 3.5.1 NUREG M/U pg 3.5 5 Rev 7 B3.5.1 NUREG M/U pg B3.5-3 B3.5.1 NUREG M/U pg B3.5-3 Rev 7 B3.5.1 NUREG M/U pg B3.5-8 B3.5.1 NUREG M/U pg B3.5 8 Rev 7 B3.5.1 NUREG M/U pg B3.5-9 (insen) Rev 0 B3.5.1 NUREG M/U pg B3.5-9 (insen) Rev 7 B3.5.1 NUREG M/U pg B3.5-11 B3.5.1 NUREG M/U pg B3.5-11 Rev 7 I B3.5.1 NUREG M/U pg B3.5-12 B3.5.1 NUREG M/U pg B3.5-12 rev 7 B3.5.1 NUREG M/U pg B3.5-15 B3.5.1 NUREG M/U pg B3.5-15 Rev 7 Rev 7 06/18/99 | |||
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.5.2 ECCS - Shutdown TECHNICAL CHANGES - LESS RESTRICTIVE (Soecification 3.5.3 "L.3" Labeled Comments / Discussions) ; | |||
: 3. Does this change involve a significant reduction in a margin of safety? ! | |||
,The proposed change does not involve'a significant reduction in a margin of safety because: 1)<the allowance is consistent with that approved in CTS 3.5'2 Actions: 2) the availability of the remaining operable f | |||
subsystem; and 3) the low probability of an event during this limited time. | |||
6 k | |||
i | |||
' m# | |||
FERMI UNIT 2- 6 REVISION 7 06/18/99l | |||
L L | |||
RCIC System l 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LC0 3.5.3 The RCIC System shall be OPERABLE. | |||
' APPLICABILITY: MODE 1 MODES 2 and 3 with reactor steam done pressure > 150 psig. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant Injection System is OPERABLE. | |||
M A.2 Restore RCIC System 14 days to OPERABLE status. | |||
B. Required Action'and B.1 Be in MODE 3. 12 hours associated Completion Time not met. ' | |||
E B.2 Reduce reactor steam 36 hours dome pressure to s 150 psig. | |||
J kl' FERMI-UNIT 2 3.5 12 Revision 7 06/18/99 I | |||
l RCIC System i 3.5.3 l | |||
SURVEILLANCE REQUIREMENTS I SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to | |||
~ | |||
the injection valve. ! | |||
i i | |||
SR 3.5 3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or l otherwise secured in position is in the correct position. | |||
SR 3.5.3.3 - ------ | |||
--- --NOTE- ---- ---- --- | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify. with reactor pressure s 1045 psig 92 days and a 945 psig, the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure. | |||
SR 3.5.3.4 -- - - | |||
- ---- NOTE-- - - -- - - | |||
Not.' required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. j Verify. with reactor pressure s 200 psig. 18 months the RCIC pump can develop a flow rate a 600 gpm against a system head l corresponding to reactor pressure. ' | |||
(continued) | |||
I gl FERMI-UNIT 2 3.5 13 Revision 7 06/18/99 ] | |||
L t _ I | |||
RCIC System 3.5.3 | |||
. SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.5.3.5 --- --- - | |||
---- --NOTE- -- -- - - - -- | |||
Vessel injection may be excluded. | |||
Verify the RCIC System actuates on an 18 months actual or simulated automatic initiation signal. | |||
. g | |||
i l | |||
1 INSERT THIS PAGE IN FRONT OF VOLUME 9 Volume 9: SECTION 3.8 l Remove Replace 3.8.1 ITS pg 3.8-1 Rev 0 3.8.1 ITS pg 3.8-1 Rev 7 3.8.1 ITS pg 3.8-2 Rev 0 3.8.1 ITS pg 3.8-2 Rev 7 I 3.8.1 ITS pg 3.8-3 Rev 0 3.8.1 ITS pg 3.8-3 Rev 7 i | |||
3.8.1 ITS pg 3.8-4 Rev 0 3.8.1 ITS pg 3.8-4 Rev 7 3.8.1 ITS pg 3.8-6 Rev 0 3.8.1 ITS pg 3.8-6 Rev 7 i B 3.8.1 ITS pg B 3.8.1-6 Rev 0 B 3.8.1 ITS pg B 3.8.1-6 Rev 7 l | |||
B 3.8.1 ITS pg B 3.8.1-7 Rev 0 B 3.8.1 ITS pg B 3.8.1-7 Rev 7 i B 3.8.1 ITS pg B 3.8.1-8 Rev 0 B 3.8.1 ITS pg B 3.8.1-8 Rev 7 B 3.8.1 ITS pg B 3.8.1-9 Rev 0 B 3.8.1 ITS pg B 3.8.1-9 Rev 7 B 3.8.1 ITS pg B 3.8.1-10 Rev 0 B 3.8.1 ITS pg B 3.8.1 10 Rev 7 l | |||
B 3.8.1 ITS pg B 3.8.1-11 Rev 0 B 3.8.1 ITS pg B 3.8.1 11 Rev 7 l B 3.8.1 ITS pg B 3.8.1-12 Rev 0 B 3.8.1 ITS pg B 3.8.1 12 Rev 7 j B 3.8.1 ITS pg B 3.8.1-13 Rev 0 B 3.8.1 ITS pg B 3.8.1-13 Rev 7 B 3.8.1 ITS pg B 3.8.1-14 Rev 0 B 3.8.1 ITS pg B 3.8.1-14 Rev 7 B 3.8.1 ITS pg B 3.8.1-15 Rev 0 B 3.8.1 ITS pg B 3.8.1-15 Rev 7 i B 3.8.1 ITS pg B 3.8.1-16 Rev 0 B 3.8.1 ITS pg B 3.8.1 16 Rev 7 B 3.8.1 ITS pg B 3.8.1-17 Rev 0 B 3.8.1 ITS pg B 3.8.1-17 Rev 7 B 3.8.1 ITS pg B 3.8.1-18 Rev 0 B 3.8.1 ITS pg B 3.8.1-18 Rev 7 B 3.8.1 ITS pg B 3.8.1 19 Rev 0 B 3.8.1 ITS pg B 3.8.1-19 Rev 7 B 3.8.1 ITS pg B 3.8.1-20 Rev 0 B 3.8.1 ITS pg B 3.8.1-20 Rev 7 l 3.8.1 CTS M/U (3/4 7-5) pg 1 of 8 3.8.1 CTS M/U pg 1 of 8 Rev. 7 3.8.1 CTS M/U (3/4 8-1) pg 2 of 8 Rev 2 3.8.1 CTS M/U (3/4 8-1) pg 2 of 8 Rev 7 3.8.1 CTS M/U (3/4 8-2) pg 3 of 8 Rev 2 3.8.1 CTS M/U (3/4 8-2) pg 3 of 8 Rev 7 3.8.1 CTS M/U (3/4 8-3) pg 4 of 8 3.8.1 CTS M/U (3/4 8-3) pg 4 of 8 Rev 7 3.8.1 DOCS pg 2 Rev 0 3.8.1 DOCS pg 2 Rev 7 3.8.1 DOCS pg 4 Rev 0 3.8.1 DOCS pg 4 Rev 7 3.8.1 DOCS pg 8 Rev 0 3.8.1 DOCS pg 8 Rev 7 3.8.1 DOCS pg 9 Rev 0 3.8.1 DOCS pg 9 Rev 7 3.8.1 DOCS pg 10 Rev 0 3.8.1 DOCS pg 10 Rev 7 3.8.1 NUREG M/U pg 3.8-2 3.8.I NUREG M/U pg 3.8-2 Rev 7 3.8.1 NUREG M/U pg 3.8-3 3.8.1 NUREG M/U pg 3.8-3 Rev 7 3.8.1 NUREG M/U pg 3.8-6 3.8.1 NUREG M/U pg 3.8-6 Rev 7 Rev 7 06/18/99 | |||
Volume 9: SECTION 3.8 (cont'd) | |||
Remove Replace 3.8.1 NUREG M/U pg 3.8-8 3.8.1 NUREG M/U pg 3.8-8 Rev 7 3.8.1 NUREG M/U pg 3.8-11 3.8.1 NUREG M/U pg 3.8-11 Rev 7 3.8.1 NUREG M/U pg 3.8-13 3.8.1 NUREG M/U pg 3.8-13 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-9 B 3.8.1 NUREG M/U pg B 3.8-9 Rev 7 | |||
. B 3.8.1 NUREG M/U pg B 3.8-9 (Insen) Rev 7 ' | |||
B 3.8.1 NUREG M/U pg B 3.8-10 B 3.8.1 NUREG M/U pg B 3.8-10 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-10 (Insen) Rev 0 B 3.8.1 NUREG M/U pg B 3.8-10 (Insen) Rev 7 B 3.8.1 NUREG M/U pg B 3.8-16 B 3.8.1 NUREG M/U pg B 3.8-16 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-16 (Insen) Rev 0 B 3.8.1 NUREG M/U pg B 3.8-16 (Insen) Rev 7 B 3.8.1 NUREG M/U pg B 3.8-17 B 3.8.1 NUREG M/U pg B 3.8-17 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-17 (Insen) Rev 0 B 3.8.1 NUREG M/U pg B 3.8-17 (Insen) Rev 7 B 3.8.1 NUREG M/U pg B 3.8-18 B 3.8.1 NUREG M/U pg B 3.8-18 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-27 B 3.8.1 NUREG M/U pg B 3.8-27 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-27 (Insen) Rev 7 | |||
_B 3.8.1 NUREG M/U pg B 3.8-28 B 3.8.1 NUREG M/U pg B 3.8-28 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-34 B 3.8.1 NUREG M/U pg B 3.8-34 Rev 7 3.8.1 JFD's pg 2 Rev 0 3.8.1 JFD's pg 2 Rev 7 3.8.1 JFD's pg 3 Rev 0 3.8.1 JFD's pg 3 Rev 7 3.8.2 CTS M/U (3/4 7-5) pg i of 2 3.8.2 CTS M/U pg 1 of 2 Rev. 7 3.8.2 DOCS pg 3 Rev 0 3.8.2 DOCS pg 3 Rev 7 3.8.2 DOCS pg 4 Rev 0 3.8.2 DOCS pg 4 Rev 7 3.8.2 DOCS pg 5 Rev 0 3.8.2 DOCS pg 5 Rev 7 3.8.3 ITS pg 3.8-13 Rev 0 3.8.3 ITS pg 3.8-13 Rev 7 3.8.3 ITS pg 3.8-14 Rev 0 3.8.3 ITS pg 3.8-14 Rev 7 3.8.3 ITS pg 3.8-15 Rev 0 3.8.3 ITS pg 3.8-15 Rev 7 B 3.8.3 I. > pg B3.83-1 Rev 0 B 3.8.3 ITS pg B 3.8.3-1 Rev 7 B 3.8.3 ITS pg B3.8.3-2 Rev 0 B 3.8.3 ITS pg B 3.8.3-2 Rev 7 B 3.8.3 ITS pg B3.8.3-3 Rev 0 B 3.8.3 ITS pg B 3.8.3-3 Rev 7 i B 3.8.3 ITS pg B3.8.3-4 Rev 0 B 3.8.3 ITS pg B 3.8.3-4 Rev 7 B 3.8.3 ITS pg B3.8.3-5 Rev 0 B 3.8.3 ITS pg B 3.8.3-5 Rev 7 B 3.8.3 ITS pg B3.8.3-6 Rev 0 B 3.8.3 ITS pg B 3.8.3-6 Rev 7 B 3.8.3 ITS pg B3.8.3-7 Rev 0 B 3.8.3 ITS pg B 3.8.3-7 Rev 7 3.8.3 CTS M/U (3/4 8-1) pg 1 of 5 Rev 2 3.8.3 CTS M/U (3/4 8-1) pg 1 of 5 Rev 7 3.83 CTS M/U (3/4 8-3) pg 2 of 5 3.8.3 CTS M/U (3/4 8-3) pg 2 of 5 Rev 7 I | |||
Rev7 06/18/99 ! | |||
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Volume 9: SECTION 3.8 (cont'd) l Remove Replace 3.83 CTS M/U (3/4 8-4) pg 3 of 5 3.8.3 CTS M/U (3/4 8-4) pg 3 of 5 Rev 7 ) | |||
3.8.3 CTS M/U (3/4 8-7) pg 4 of 5 3.8.3 CTS M/U (3/4 8-7) pg 4 of 5 Rev 7 I 3.8.3 DOCS pg 1 Rev 0 3.8.3 DOCS pg 1 Rev 7 I 3.8.3 DOCS pg 2 Rev 0 3.8.3 DOCS pg 2 Rev 7 3.8.3 DOCS pg 3 Rev 0 3.8.3 DOCS pg 3 Rev 7 3.8.3 NUREG M/U pg 3.8-21 3.8.3 NUREG M/U pg 3.8-21 Rev 7 3.8.3 NUREG M/U pg 3.8-22 3.8.3 NUREG M/U pg 3.8-22 Rev 7 l 1 | |||
3.8.3 NUREG M/U pg 3.8-23 3.8.3 NUREG M/U pg 3.8-23 Rev 7 l l' | |||
B 3.8.3 NUREG M/U pg B 3.8-41 B 3.8.3 NUREG M/U pg B 3.8-41 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-42 B 3.8.3 NUREG M/U pg B 3.8-42 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-43 B 3.8.3 NUREG M/U pg B 3.8-43 Rev 7 B 3.8.3 NUREG M/Upg B 3.8-44 B 3.8.3 NUREG M/U pg B 3.8-44 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-45 B 3.8.3 NUREG M/U pg B 3.8-45 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-46 B 3.8.3 NUREG M/U pg B 3.8-46 Rev 7 l | |||
-B 3.8.3 NUREG M/U pg B 3.8-46 (Insen) Rev 0 B 3.8.3 NUREG M/U pg B 3.8-46 (Insen) Rev 7 l B 3.8.3 NUREG M/U pg B 3.8-47 B 3.8.3 NUREG M/U pg B 3.8-47 Rev 7 ! | |||
B 3.8.3 NUREG M/U pg B 3.8-47 (Insen) Rev 0 B 3.8.3 NUREG M/U pg B 3.8-47 (Insen) Rev 7 B 3.8.3 NUREG M/U pg B 3.8-48 B 3.8.3 NUREG M/U pg B 3.8-48 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-49 B 3.8.3 NUREG M/U pg B 3.8-49 Rev 7 I 3.8.3 JFD's pg 1 Rev 0 3.8.3 JFD's pg i Rev 7 3.8.3 JFD's pg 2 Rev 7 3.8.3 NSHC pg i Rev 0 3.8.3 NSHC pg i Rev 7 3.8.3 NSHC pg 2 Rev 0 3.8.3 NSHC pg 2 Rev 7 3.8.3 NSHC pg 3 Rev 7 3.8.3 NSHC pg 4 Rev 7 3.8.4 ITS pg 3.8-17 Rev i 3.8.4 ITS pg 3.8-17 Rev 7 B 3.8.4 ITS pg B 3.8.4-2 Rev 1 B 3.8.4 ITS pg B 3.8.4 2 Rev 7 B 3.8.4 ITS pg B 3.8.4-3 Rev i B 3.8.4 ITS pg B 3.8.4 3 Rev 7 B 3.8.4 ITS pg B 3.8.4-4 Rev i B 3.8.4 ITS pg B 3.8.4-4 Rev 7 B 3.8.4 ITS pg B 3.8.4-5 Rev 1 B 3.8.4 ITS pg B 3.8.4-5 Rev 7 3.8.4 DOCS pg i Rev 0 3.8.4 DOCS pg i Rev 7 3.8.4 DOCS pg 2 Rev 0 3.8.4 DOCS pg 2 Rev 7 3.8.4 NUREG M/U pg 3.8-25 Rev 1 3.8.4 NUREG M/U pg 3.8-25 Rev 7 B 3.8.4 NUREG M/U pg B 3.8-51 B 3.8.4 NUREG M/U pg B 3.8-51 Rev 7 Rev7 06/18/99 | |||
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Volume 9:' SECTION 3.8 (cont'd) | |||
Remove Replace B 3.8.4 NUREG M/U pg B 3.8-51 (Insen) Rev i -- | |||
B 3.8.4 NUREG M/U pg B 3.8-55 B 3.8.4 NUREG M/U pg B 3.8-55 Rev 7 B 3.8.4 NUREG M/U pg B 3.8-55 (Insen) Rev 0 B 3.8.4 NUREG M/U pg B 3.8-55 (Insen) Rev 7 3.8.5 DOCS pg 2 Rev 0 3.8.5 DOCS pg 2 Rev 7 3.8.5 JFD's pg 1 Rev 0 3.8.5 JFD's pg 1 Rev 7 l 3.8.6 ITS pg 3.8-22 Rev 0 3.8.6 ITS pg 3.8-22 Rev 7 3.8.6 ITS pg 3.8-23 Rev 0 3.8.6 ITS pg 3.8-23 Rev 7 B 3.8.6 ITS pg B 3.8.6-6 Rev 0 B 3.8.6 ITS pg B 3.8.6-6 Rev 7 l 3.8.6 CTS M/U (3/4 8-10) pg 1 of 3 Rev i 3.8.6 CTS M/U (3/4 8-10) pg I of 3 Rev 7 3.8.6 DOCS pg 3 Rev 0 3.8.6 DOCS pg 3 Rev 7 3.8.6 NUREG M/U pg 3.8-30 3.8.6 NUREG M/U pg 3.8-30 Rev 7 3.8.6 NUREG M/U pg 3.8-31 3.8.6 NUREG M/U pg 3.8-31 Rev 7 3.8.6 NUREG M/U pg 3.8-69 3.8.6 NUREG M/U pg 3.8-69 Rev 7 3.8.6 JFD's pg i Rev 0 3.8.6 JFD's pg i Rev 7 3.8.6 NSHC pg 5 Rev 7 3.8.6 NSHC pg 6 Rev 7 3.8.7 ITS pg 3.8-26 Rev 0 3.8.7 ITS pg 3.8-26 Rev 7 1 | |||
3.8.7 CTS M/U (3/4 8-14) pg 1 of 2 3.8.7 CTS M/U (3/4 8-14) pg i of 2 Rev 7 3.8.7 DOCS pg 1 Rev 0 3.8.7 DOCS pg 1 Rev 7 3.8.7 DOCS pg 2 Rev 0 3.8.7 DOCS pg 2 Rev 7 3.8.7 NUREG M/U pg 3.8-38 3.8.7 NUREG M/U pg 3.8-38 Rev 7 3.8.7 JFD's pg i Rev 0 3.8.7 JFD's pg i Rev 7 3.8.8 JFD's pg i Rev 0 3.8.8 JFD's pg i Rev 7 l Rev 7 06/18/99 l | |||
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AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-0perating | |||
) | |||
LC0 3.8.1 , The following AC electrical power sources shall be OPERABLE: | |||
: a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and i | |||
: b. Two emergency diesel generators (EDGs) per division. j APPLICABILITY: MODES 1, 2. and 3. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both EDGs in A.1 Perform SR 3.8.1.1 1 hour I one division for OPERABLE offsite inoperable. circuit (s). @ | |||
Once per 8 hours thereafter M-A.2 Declare required 4 hours from feature (s). supported discovery of an by the inoperable inoperable EDG EDGs inoperable when concurrent with the redundant . inoperability of required feature (s) redundant are inoperable. required feature (s) | |||
M A.3 Verify the status of Once per 8 hours CTG 11 1. | |||
} | |||
k M (continued) l FERMI UNIT 2 3.8 1 Revision 7 06/18/99 | |||
AC Sources-0perating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLET10N TIME A. (continued) A.4.1 Determine OPERABLE 24 hours Al EDG(s) are not inoperable due to I common cause failure. | |||
E l A.4.2 Perform SR 3.8.1.2 24 hours ! | |||
for OPERABLE EDG(s). | |||
7 E | |||
$ A.5 Restore availability of CTG 11-1. | |||
72 hours from discovery of Condition A concurrent with CTG 11 1 not available V l | |||
! A.'6 Restore both EDGs in 7 days the division to OPERABLE status. | |||
B. One or both EDGs in B.1 Restore both EDGs in 2 hours both divisions one division to inoperable. OPERABLE status. | |||
C. Dr.e or two offsite C.1 Be in H0DE 3. 12 hours circuits inoperable. | |||
E @ | |||
Required Action and C.2 Be in H0DE 4. 36 hours Associated Completion Time of Condition A or B not met. | |||
l FERMI UNIT 2 3.82 Revision 7 06/18/99 | |||
. I i | |||
1 AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS ; | |||
i SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify-correct breaker alignment and 7 days ) | |||
indicated power availability for each ; | |||
offsite circuit. 1 SR' 3.8.1.2 ----- - --- ------NOTES- - - ---- - - --- | |||
: 1. All EDG starts may be preceded by an 06 l engine prelube period and followed by a warmup period prior to loading. | |||
: 2. A modified DG start involving idling | |||
.d and gradual acceleration to 1 synchronous speed may be used for this 6 SR as recommended by the manufacturer. | |||
l Verify each EDG starts and achieves steady 31 days state voltage = 3740 V and s 4580 V and l frequency = 58.8 Hz and s 61.2 Hz. | |||
SR 3.8.1~.3 -- | |||
- --- ---- - NOTES.- -- ---- -- - | |||
: 1. EDG loadings may include gradual loading as recommended by the manufacturer. | |||
: 2. Momentary transients outside the load range do not invalidate this test. | |||
: 3. This Surveillance shall'be conducted on only one EDG at a time. | |||
Verify each EDG is synchronized and loaded 31 days l and operates for a 60 minutes at a load a 2500 kW. j (continued) l i | |||
l 1 | |||
l l FERMI UNIT 2 3.8 3 Revision 7, 06/18/99 J | |||
1 4 | |||
I J | |||
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FRE0VENCY SR 3.8.1.4 Verify each day tank contains a 210 gal of 31 days fuel oil. ~ | |||
SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank. | |||
I i | |||
1 SR 3.8.1.6 Verify each fuel oil transfer system 31 days i operates to automatically transfer fuel oil from storage tanks to the day tanks. | |||
l SR 3.8.1.7 - -- | |||
- - -- - NOTE- - - -- --- --- | |||
- All EDG starts may be preceded by an engine | |||
't prelube period and followed by a warmup EE period prior to loading. l nc ........................................... ' | |||
Verify each EDG starts from standby 184 days condition and achieves: | |||
: a. In s 10 seconds. voltage a 3740 V and frequency a 58.8 Hz: and | |||
: b. Steady state voltage a 3740 V and s 4580 V and frequency a 58.8 Hz and s 61.2 Hz. | |||
SR 3.8.1.8 Verify each EDG rejects a load greater than 18 months j or equal to its associated single largest i post accident load, and following load l rejection the frequency is s 66.75 Hz. ! | |||
1 1 | |||
(continued) j FERMI UNIT 2 3.8-4 Revision 7, 06/18/99 | |||
AC Sources-0perating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.8.1.11 - -- -- - --- | |||
- NOTE --- -- ------ --- | |||
All.EDG starts may be preceded by an engine prelube period. | |||
Verify on.an actual or simulated Emergency 18 months Core Cooling System (ECCS) nitiation signal each EDG auto starts and: | |||
: a. In s 10 seconds after auto start and during tests, achieves voltage 3 jl = 3740 V and frequency = 58.8 Hz: | |||
'O b. Achieves steady state frcluency I4 an s48dV an jl c. Operates for = 5 minutes. | |||
SR 3.8.1.12 Verify each EDG's automatic trips are 18 months bypassed on an actual or simulated ECCS initiation signal except: | |||
: a. Engine overspeed: | |||
: b. Generator differential current: | |||
: c. Low lube oil pressure; | |||
: d. Crankcase overpressure: and | |||
: e. Failure to start. | |||
(continued) l FERMI - UNIT 2 3.8-6 Revision 7 06/18/99 | |||
l l | |||
l | |||
! AC Sources-Operating B 3.8.1 BASES ACT!0NS (continued) | |||
I events existing concurrently is acceptable because it | |||
. minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown. | |||
The remaining OPERABLE EDGs and offsite circuits are l | |||
adequate to supply electrical power to the onsite Class 1E Distribution System. Thus, on a component basis, single failure protection for the required feature's function may have been lost: however, function has not been lost. The 4 hour Completion Time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required feature. Additionally, the 4 hour Completion Time takes into account the capacity and capability of the remaining AC sources, reasonable time for repairs, and low j probability of a DBA occurring during this period. | |||
/L3 To minimize the impact of operation with an inoperable EDG, it is necessary to periodically ensure the availability of CTG 11 1. The verification of the status of CTG 111 is performed by an administrative check of breaker and line availability, and the CTG 111 ability to supply Division I : | |||
loads. Since this Required Action only specifies " verify 1 6 the status." even when CTG 11 1 is not available it does not j result in this Required Actions being not met. However. l upon discovery that CTG 11 1 is unavailable, the limitations ! | |||
of Required Action A.5 are imposed. | |||
l A.4.1 and A.4.2 l 3l Required Action A.4.1 provides an allowance to avoid W | |||
W unnecessary testing of OPERABLE EDGs. If it can be determined that the cause of the inoperable EDG(s) does not exist on the OPERABLE EDGs, 9 3.8.1.2 does not have to be I performed. If the cause of inoperability exists on other ! | |||
EDG(s), they are declared ino>erable upon discovery, and ; | |||
Condition B of LC0 3.8.1 may />e entered. Once the failure < | |||
is repaired and the common cause failure no longer exists, i Required Action A.4.1 is satisfied. If the cause of the initial inoperable EDG cannot be confirmed not to exist on l the remaining EDG(s), performance of SR 3.8.1.2 suffices to provide assurance of continued OPERABILITY of those EDGs. | |||
y In the event the inoperable EDG(s) are restored to OPERABLE ; | |||
I status prior to completing either A.4.1 or A.4.2, the plant j l FERMI UNIT 2 B 3.8.1- 6 Revision 7 06/18/99 I | |||
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L AC Sources-Operating B 3.8.1 BASES ACTIONS (continued) corrective action program will continue to evaluate the | |||
, common cause possibility. This continued evaluation, however, is no longer under the 24 hour constraint imposed while in Condition A. | |||
According to Generic Letter 84 15 (Ref. 7). 24 hours is a reasonable time to confirm that the OPERABLE EDGs are not affected by the same problem as the inoperable EDG. | |||
4l A.5 and A.6 According to Regulatory Guide 1.93 (Ref. 6), operation may continue with no OPERABLE EDGs to one division for a period that should not exceed 72 hours. With one or both EDGs in one division inoperable, the remaining OPERABLE EDGs and offsite circuits are adequate to supply electrical power to | |||
- the onsite Class 1E Distribution System. Required Action 1 A.5 imposes this 72 hour Completion Time from the discovery | |||
( of the non availability CTG 11 1. However, if CTG 111 is available to sup)1y Division I loads-(determined by administrative c1eck of breaker, line availability, and CTG 111 status) Required Action A.5 would be met and Required Action A.6 would allow the restoration time of 7 days. | |||
The 72 hour Completion Time to restore to at least one EDG in the division in OPERABLE status takes into account the capacity and capability of the remaining AC sources, reasonable time for repairs, and low probability of a DBA yl occurring during this period. The 7 day Completion Time to restore all EDGs to OPERABLE status takes into account the capacity and capability of the remaining AC Sources, as well as the additional reliability afforded by the availability of CTG 11-1. | |||
IL1 With one or both EDGs on both divisions inoperable, there may be no remaining standby AC source. Thus, with an assumed loss of offsite electrical power, insufficient standby AC sources are available to power the minimum required ESF functions. Since the offsite electrical power system is the only source of AC )ower for a significant percentage of ESF equipment at t11s level of degradation, the risk associated with continued operation for a very short time could be less than that associated with an immediate controlled shutdown. (The immediate shutdown s_ | |||
l FERMI - UNIT 2 B 3.8.1 - 7 Revision 7 06/18/99 ) | |||
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I AC Sources-Operating B 3.8.1 BASES ACTIONS (continued) could cause grid instability, which could result in a total loss of AC power.) Since any inadvertent unit generator trip could also result in a total loss of offsite AC power, however, the time allowed for continued operation is severely restricted. The intent here is to avoid the risk associated with an immediate controlled shutdown and to minimize the risk associated with this level of degradation. | |||
According to Regulatory Guide 1.93 (Ref. 6), with both divisions with EDGs inoperable, operation may continue for a period that should not exceed 2 hours. | |||
C.1 and C.2 If the inoperable AC electrical power sources cannot be restored to OPERABLE status within the associated Completion Time, the unit must be brought to a MODE in which the LC0 1 does not apply. Furthermore, with one or both offsite ; | |||
circuits inoperable, the Fermi design and subsequent plant i response is such that power operation is not justified, and a plant shutdown is required. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are ! | |||
reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. | |||
SURVEILLANCE The AC sources are designed-to permit inspection and REQUIREMENTS testing of all important areas and features, especially those that have a standby function, in accordance with 10 CFR 50. GDC 18 (Ref. 8). Periodic component tests are supplemented by extensive functional tests during refueling outages (under simulated accident conditions). The SRs for demonstrating the OPERABILITY of the EDGs are based on the recommendations of Regulatory Guide 1.9 (Ref. 3), Regulatory Guide 1.108 (Ref. 9), and Regulatory Guide 1.137 (Ref.10), | |||
as addressed in the UFSAR. | |||
Where the SRs discussed herein specify voltage and frequency tolerances, the following summary is applicable. The minimum steady state output voltage of 3740 V is 90% of the nominal 4160 V output voltage. This value, which is k l FERMI - UNIT 2 B 3.8.1 - 8 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) specified in ANSI C84.1 (Ref.11), allows for voltage drop to the terminals of 4000 V motors whose minimum operating voltage is specified as 90% or 3600 V. It also allows for voltage drops to motors and other equipment down through the 120 V level where minimum operating voltage is also usually specified as 90% of name plate rating. The specified maximum steady state output voltage of 4580 V is equal to the maximum operating voltage specified for 4000 V motors. | |||
It ensures that for a lightly loaded distribution system, the voltage at the terminals of 4000 V motors is no more than the maximum rated operating voltages. The specified minimum and maximum frequencies of the EDG are 58.8 Hz and 61.2 Hz. respectively. These values are ecual to i 2% of the 60 Hz nominal frequency and are derivec from the recommendations found in Regulatory Guide 1.9 (Ref. 3). | |||
SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are connected to their preferred power source and that appropriate independence of offsite circuits is maintained. | |||
The 7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room. | |||
SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the, standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown condition. | |||
To minimize the mechanical stress and wear on moving parts that do not get lubricated when the engine is not running. | |||
l tr.ase SRs have been modified by a Note (Note 1 for SR 3.8.1.2 and Note 1 for SR 3.8.1.7) to indicate that all EDG starts for these Surveillances may be preceded by an g engine prelube period and followed by a warmup prior to | |||
, loading. | |||
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. UNIT 2 B 3.8.1- 9 Revision 7 06/18/99 l | |||
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l AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
For the purposes of SR 3.8.1.2 testing, the EDGs are started | |||
+ | |||
anywhere from standby to hot conditions by using one of the following signals: | |||
Manual. l Simulated loss-of offsite power by itself. l Simulated loss of offsite power in conjunction with an ESF actuation test signal, or An ESF actuation test signal by itself. | |||
In order to reduce stress and wear on diesel engines, the ! | |||
EDG manufacturer recommends a modified start in which the i starting speed of EDGs is limited, warmup is limited to this lower speed, and the EDGs are gradually accelerated to synchronous speed prior to loading. These start procedures yl 2 are the intent of Note 2, which is only allowed to satisfy q SR 3.8.1.2 but are not applicable when performing SR 3.8.1.7. | |||
i SR 3.8.1.7 requires that, at a 184 day Frequency, the EDG , | |||
starts from standby conditions and achieves required voltage ' | |||
and frequency within 10 seconds. Standby conditions for an EDG mean that the diesel engine coolant and oil are being continuously circulated and temperature is being maintained consistent with manufacturer recommendations. The 10 second start requirement supports the assumptions in the design basis LOCA analysis of UFSAR. Section 6.3 (Ref.12). The 10 second start requirement is not applicable to SR 3.8.1.2. | |||
Since SR 3.8.1.7 does require a 10 second start it is more restrictive than SR 3.8.1.2 and it may be performed in lieu of SR 3.8.1.2. In addition to the SR requirements, the time for the EDG to reach steady state operation, unless the 9 modified EDG start method is employed, is periodically monitored and the trend evaluated to identify degradation of E governor and voltage regulator performance. | |||
If The normal 31 day Frequency for SR 3.8.1.2 is consistent with Regulatory Guide 1.9 (Ref. 3). The 184 day Frequency E for SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7). These Frequencies provide adecuate assurance of EDG OPERABILITY, while minimizing cegradation resulting from testing. | |||
l FERMI - UNIT 2 B 3.8.1 - 10 Revision 7. 06/18/99 | |||
AC Sources-Operating B 3.8.1 BASES | |||
-SURVEILLANCE REQUIREMENTS (continued) | |||
SR 3.8.1.3 This Surveillance provides assurance that the EDGs are ' | |||
capable of synchronizing and accepting greater than or equal to the equivalent of the maximum expected accident loads al T | |||
y without the risk of overloading the EDG. The EDG is tested at approximately 90% of its continuous load rating which R provides margin to excessive EDG loading, while demonstrating the EDG capability to carry loads near the maximum expected accident loads. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the EDG is connected to the offsite source. | |||
Although no power factor requirements are established by this SR, the EDG is normally operated at a power factor between 0.8 lagging and 1.0. The 0.8 value is the design b rating of the machine, while 1.0 is an operational limitation to ensure circulating currents are minimized. | |||
D Routine overloading may result in more frequent teardown | |||
.1 inspections in accordance with vendor recommendations in | |||
( order to maintain EDG OPERABILITY. l The normal 31 day Frequency for this Surveillance is kll consistent with Regulatory Guide 1.9 (Ref. 3). | |||
Note 1 modifies this Surveillance to indicate that diesel engine runs for this Surveillance may include gradual loading, as recommended by the manufacturer, so that mechanical stress and wear on the diesel engine are minimized. | |||
Note 2 modifies this Surveillance by stating that momentary transients (e.g., because of changing bus loads) do not invalidate this test. Similarly, momentary power factor transients outside the normal range do not invalidate the test. | |||
Note 3 indicates that this Surveillance should be conducted on only one EDG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations. | |||
l FERMI. UNIT 2 B 3.8.1- 11 Revision 7 06/18/99 | |||
m AC Sources-Operating B 3.8.1 BASES-1 SURVEILLANCE REQUIREMENTS (continued) 1 | |||
; SR 3.8.1.4 This SR provides verification that the level of fuel oil'in the day tank is'at or above the level at which fuel oil is automatically added. The level.is expressed as an ecuivalent volume in gallons, and is selected to ensure acequate -fuel oil for a minimum of 1 hour of EDG operation at full load. | |||
The 31 day Frequency is adequate to ensure that a susficient supply of fuel oil is available, since low level alrrms are provided and facility operators would be aware of ray large uses of fuel oil during this period. | |||
SR 3.8.1.5 i Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive. Removal of water from the fuel oil day tanks once every 31 days eliminates the l | |||
necessary environment' for bacterial survival. This is the most effective means of controlling microbiological fouling. | |||
In addition, it eliminates the potential for water i entrainment in the fuel oil during EDG operation. Water may come from any of several sources. including condensation, ground water, rain water, contaminated fuel oil, and breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref.10). This SR is for preventive maintenance. The presence of water does not necessarily represent a failure of.this SR provided that accumulated water is removed during performance of this Surveillance. | |||
SR 3.8.1.6 This Surveillance demonstrates that each required fuel oil I transfer pump operates and transfers fuel oil from its | |||
) associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This Surveillance provides assurance that the fuel oil transfer pump is OPERABLE. the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the h l FERMI. UNIT 2 B 3'.8.1 - 12 Revision 7. 06/18/99 I | |||
y ! | |||
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AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) controls and control systems for automatic fuel transfer 3 systems are OPERABLE. | |||
The design of fuel transfer systems is such' that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG l testing. As such, a 31 day Frequency is appropriate, since ' | |||
proper operation of fuel transfer systems is an inherent part of EDG OPERABILITY. j SR 3.8.1.7 : | |||
1 See SR 3.8.1.2. | |||
SR 3.8.1.8 1 | |||
Each EDG is provided with an engine overspeed trip to ' | |||
prevent damage to the engine. Recovery from the transient ! | |||
caused by the loss of a large load could cause diesel engine i overspeed. which, if excessive, might result in a trip of the engine. This Surveillance demonstrates the EDG load response characteristics and capability to reject the i | |||
largest single load while maintaining a specified margin to ! | |||
the overspeed trip. The largest single load for each EDG is a residual heat removal pump (1684 kW). This Surveillance may be accomplished by: j | |||
: a. Tripping the EDG output breaker with the EDG carrying greater than or ecual to its associated single largest post accident loac while paralleled to offsite power, or while solely supplying the bus; or | |||
: b. Tripping its associated single largest post accident load with the EDG solely supplying the bus. | |||
As required by IEEE.308 (Ref.14), the load rejection test is acceptable if the increase in diesel s)eed does not ' | |||
exceed 75% of the difference between sync 1ronous speed and the overspeed trip set)oint. or 15% above synchronous speed, i whichever is lower. T1is represents 66.75 Hz, equivalent to 75% of the difference between nominal speed and the overspeed trip setpoint. | |||
8gi~ | |||
j ; FERMI UNIT 2 B 3.8.1- 13 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
The frequency tolerances specified in this SR are derived from Regulatory Guide 1.9 (Ref. 3) recommendations for response during load sequence intervals. The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9). | |||
SR 3.8.1.9 This Surveillance demonstrates the EDG capability to reject a full load without overspeed tripping or exceeding the predetermined voltage limits. The EDG full load rejection may occur because of a system fault or inadvertent breaker tripping. This Surveillance ensures proper engine generator load response under the simulated test conditions. This test simulates the loss of the total connected load that the EDG ex>eriences following a full load rejection and verifies that t1e EDG does not trip upon loss of the load. These acceptance criteria provide EDG damage ;rotection. While the EDG is not expected to experience t1is transient during an event, and continues to be available. this response ensures that the EDG is not degraded for future application, including reconnection to the bus if the trip initiator can be corrected or isolated. | |||
The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.100 (Ref. 9) and is intended to be consistent with expected fuel cycle lengths. 4 i | |||
SR 3.8.1.10 | |||
) | |||
As required by Regulatory Guide 1.108 (Ref. 9). | |||
paragraph 2.a.(1) this Surveillance demonstrates the as designed operation of the standby power sources during loss ; | |||
of the offsite source. This test verifies all actions I encountered from the loss of offsite power, including 1 shedding of the nonessential loads and energization of the i emergency buses and respective loads from the EDG, including - | |||
automatic start of the EDG cooling water pump. It further } | |||
demonstrates the capability of the EDG to automatically j achieve the required voltage and frequency within the a specified time. | |||
The EDG auto start time of 10 seconds is derived from requirements of the accident analysis for responding to a ! | |||
design basis large break LOCA. The Surveillance should be ! | |||
continued for a minimum of 5 minutes in order to demonstrate ! | |||
l FERMI - UNIT 2 B 3.8.1 - 14 Revision 7 06/18/99 | |||
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AC Sources-0perating i B 3.8.1 | |||
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BASES l | |||
SURVEILLANCE REQUIREMENTS (continued) I that all starting transients have decayed and stability has been achieved. | |||
The requirement to verify the connection and power supply of permanent and auto connected loads is intended to satisfactorily show the rel3tionship of these loads to the EDG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For | |||
. instance. Emergency Core Cooling Systems (ECCS) injection valves are not desired to be stroked open, or systems are not capable of being operated at full flow, or RHR systems | |||
)erforming a decay heat removal function are not desired to | |||
)e realigned to the ECCS mode of operation. In lieu of ! | |||
actual demonstration of the connection and loading of these ' | |||
loads, testing that adequately shows the capability of the EDG system to perform these functions is acceptable. This testing may include any series of sequential. overlapping, or total steps so that the entire connection and loading sequence is verified. | |||
The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). l paragraph 2.a.(1), takes into consideration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. | |||
This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the Note is to minimize wear and tear on the EDGs during testing. | |||
SR 3.8.1.11 | |||
' This Surveillance demonstrates that the EDG (including its associated cooling water pump) automatically starts and achieves the required minimum voltare end frequency within the specified time (10 seconds) from the design basis actuation signal (LOCA signal) and operates for a 5 minutes. | |||
The 5 minute period provides sufficient time to demonstrate stability. | |||
The Frequency of 18 months takes into consideration plant conditions required to perform the Surveillance and is intended to be consistent with the expected fuel cycle lengths. Operating experience has shown that these l FERMI UNIT 2 B 3.8.1 - 15 Revision 7 06/18/99 1 | |||
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l- AC Sources-Operating p B 3.8.1 BA ES SURVEILLANCE REQUIREMENTS (continued) components usually pass the SR when performed at the 18 month Frequency. Therefore. the Frequency is acceptable from a reliability standpoint. | |||
l This SR is modified by a Note allowing EDG starts to be l * | |||
) receded by an engine prelube period. The reason for the t)te is'to minimize wear and tear on the EDGs during testing. | |||
SR 3.8.1.12 This Surveillance demonstrates that EDG non critical l protective functions (e.g., high jacket water temperature) | |||
; are bypassed on an actual or simulated ECCS initiation l signal and critical protective functions (engine overspeed. | |||
l I | |||
generator differential current. low lubricating oil )ressure crankcase overpressure, and failure to start) trip t1e EDG to avert substantial damage to the EDG unit. The non-critical trips are bypassed during DBAs and provide an alarm on an. abnormal engine condition. This alarm provides the operator with sufficient time to react appropriately. 'The EDG availability to mitigate the DBA is more critical than protecting the engine against minor problems that are not 3 immediately detrimental to emergency operation of the EDG. j The 18 month Frecuency is based on engineering judgment. | |||
takes into consiceration l perform the Surveillance,and plant is conditions intended t) required to be consistent with ex>ected fuel cycle lengths. Operating experience has l J l , | |||
shown tlat these components usually pass the SR when | |||
)erformed at the 18 month Frequency. Therefore, the treguency was concluded to be acceptable from a reliability | |||
: standpoint. | |||
SR 3.8.1.13 Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(3). requires . ! | |||
l. | |||
demonstration once per 18 months that the EDGs can start and j run continuously at full load capability for an interval of ; | |||
not less than 24 hours-22 hours of which is at a load 4 equivalent to the continuous rating of the EDG, and 2 hours l of which is at a load equivalent to 110% of the continuous ! | |||
duty rating of the EDG. Fermi 2 has taken.an exception to ; | |||
this requirement and performs the 22 hour run at 1 approximately 90% of the continuous rating (2500 kW- ; | |||
2600 kW) ~ and performs the 2 hour run at approximately the j | |||
l FERMI UNIT-2 B 3.8.1 - 16 Revision 7 06/18/99 j | |||
c AC Sources-Operating B 3.8.1 | |||
' BASES SURVEILLANCE REQUIREMENTS (continued) continuous rating (2800 kW 2900 kW). The EDG starts for | |||
, this Surveillance can be performed either from standby or hot conditions. The provisions for prelube and warmup, discussed in SR 3.8.1.2, and for gradual loading, discussed | |||
'in SR 3.8.1.3, are applicable to this SR. | |||
Although no power factor requirements are established by l | |||
m this SR, the EDG is normally operated at a power factor i between 0.8 -lagging and 1.0.- The 0.8 value is the design R rating of the machine, while the 1.0.is an operational V limitation to ensure circulating currents are minimized. A load' band is provided to avoid routine overloading of the EDG. Routine overloading may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY. | |||
The 18 month Frequency is' consistent'with the recommendations of Regulatory Guide 1.108 (Ref. 9). | |||
paragraph 2.a.(3): takes'into consideration plant conditions required to perform the Surveillance: and is inPnded to be consistent with expected fuel cycle lengths. | |||
This Surveillance has been modified by a Note. The Note states that momentary transients due to changing bus loads do not invalidate this test. | |||
SR 3.8.1.14 This Surveillance demonstrates that the diesel engine can restart from a hot condition, such as subsequent to shutdown from normal Surveillances, and achieve the minimum required voltage and frequency within 10 seconds and maintain a steady state voltage and frequency range. The 10 second time is derived from the requirements of the accident | |||
-analysis-to respond to a design basis large break LOCA. The 18 month Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(5). | |||
This SR is modified by two Notes. Note 1 ensures that the | |||
. test is performed with the diesel sufficiently hot. The Y. requirement that the diesel has operated for at least i 2 hours near full load conditions prior to performance of 1 this Surveillance is based on manufacturer recommendations iTl -for achieving hot conditions. Routine overloads may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY. | |||
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-l FERMI . UNIT 2 8 3.8.1 - 17 Revision 7, 06/18/99 | |||
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L AC Sources-Operating B 3.8.1 L | |||
BASES- I SURVEILLANCE REQUIREMENTS (continued) | |||
Mcmentary transients due to changing bus loads do not | |||
. invalidate this test. Note 2 allows all EDG starts to be-l< preceded by an engine prelube period to minimize wear and L | |||
1 tear on the diesel during testing. | |||
SR 3.8.1.15 As required by Regulatory Guide 1.108 (Ref. 9). ) | |||
paragraph 2.a.(6). this Surveillance ensures that the manual ' | |||
synchronization and load transfer from the EDG to the offsite source can be made and that the EDG can be returned to standby status when offsite power is' restored. It also ; | |||
ensures that the. auto start logic is reset to allow the EDG ; | |||
to restart and reload if a subsequent loss of offsite power j occurs. The EDG is considered to be in standby status when the EDG is shutdown with the output breaker open, the load sequence timers are reset. and is able to restart and reload on a subsequent bus under voltage.. | |||
I L -The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). | |||
: paragraph 2.a.(6), and takes into consideration plant conditions desired to perform the Surveillance. | |||
SR 3.8.1.16 Under accident conditions with loss of offsite power loads I are sequentially-connected to the bus by the automatic load ' | |||
sequencer. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading of the EDGs due'to high motor starting currents. The 10% load sequence time interval tolerance' ensures that sufficient time exists for the EDG to restore frequency and voltage | |||
: i. . prior to^ applying the next load and that safety analysis L assumptions regarding ESF equipment time delays are not i violated. Reference 2 provides a summary of the automatic loading of ESF buses. | |||
The~ Frequency of 18 months is consistent with the . | |||
reconnendations of Regulatory Guide 1.108 (Ref. 9). ' | |||
paragraph 2.a.(2): takes into consideration plant conditions required to perform the Surveillance: and is intended to be consistent with expected fuel cycle' lengths. j q | |||
B 3.8.1 - 18 hiFERMIIUNIT'2- Revision 7. 06/18/99 k k L . | |||
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i AC Sources-Operating . | |||
B 3.8.1 l i | |||
BASES SURVEILLANCE REQUIREMENTS (continued) | |||
SR 3.8.1.17 In the event of a DBA coincident with a loss of offsite . | |||
power, the EDGs are required to supply the'necessary power l to ESF systems so that the fuel. RCS, and containment design ! | |||
limits are not exceeded. ' | |||
This Surveillance demonstrates EDG operation, as discussed l in the Bases for SR 3.8.1.10, during a loss of offsite power actuation test signal in conjunction with an ECCS initiation i signal. In lieu of actual demonstration of connection and ; | |||
loading of loads, testing that adequately shows the ; | |||
capability of the EDG system to perform these functions is ; | |||
acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified. | |||
The Frequency of 18 months takes into consideration plant conditions required to perform the Surveillance and is ! | |||
intended to be consistent with an expected fuel cycle length ! | |||
of 18 months. 4 This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the Note is to minimize wear and tear on the EDGs during testing. | |||
SR 3.8.1.18 This Surveillance demonstrates that the EDG starting independence has not been compromised. Also, this Surveillance demonstrates that each engine can achieve proper speed within the specified time when the EDGs are started simultaneously. | |||
j The 10 year Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). | |||
This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the i Note is to minimize wear on the EDG during testing. l | |||
( FERMI : UNIT 2 B 3.8.1 - 19 Revision 7 06/18/99 L | |||
7-- | |||
AC Sources-Operating B 3.8.1 BASES REFERENCES 1. 10 CFR 50. Appendix A. GDC 17. | |||
) | |||
: 2. UFSAR. Sections 8.2 and 8.3. | |||
: 3. Regulatory Guide 1.9. | |||
: 4. UFSAR. Chapter 6. | |||
: 5. UFSAR, Chapter 15. | |||
: 6. Regulatory Guide 1.93. ! | |||
: 7. Generic Letter 84 15. | |||
i | |||
: 8. 10 CFR 50, Appendix A. GDC 18. | |||
l | |||
: 9. Regulatory Guide 1.108. | |||
: 10. Regulatory Guide 1.137. | |||
: 11. ANSI C84.1, 1982. | |||
1 | |||
: 12. UFSAR. Section 6.3. | |||
: 13. ASME Boiler and Pressure Vessel Code. Section XI. | |||
: 14. IEEE Standard 308. | |||
4 | |||
'T 4 | |||
l l FERMI -' UNIT 2 B 3.8.1-20 Revision 7 06/18/99 4 | |||
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&fCIFlMTioh).3.8I \ | |||
.3/4.8 ELECTRICAL POWER SYSTEMS | |||
[ Al50 54 h C b #'I 3 ) | |||
3/4.8.1 A.C. SOURCES A.C. SOURCES - OPERATING d,f i | |||
llMITING CONDITION FOR OPERATION LLO 3.8.1 As a minimum, the following A.C. electrical power sources shall be ' | |||
OPERA : | |||
., p | |||
: a. Two My .cr.5 ir2;;cannt circuits between the offsite l transmission network and the onsite Class IE distribution system, ' | |||
and 0.l | |||
: b. Twolse ate and A depende onsite A.F. electrical power /sourgp, Div1ston I and Eivision ,[each consisting of two emergency dieselgeneratorsleac diesel generator wi @j 643,8,lM 1. A separate day fuel tank containing a minimum of 210 gallons of fuel, | |||
/I jS ) 2. A separate fuel storage system containing a minimum of | |||
\ P "y g.y | |||
, 3 g [ 35,280 gallons of fuel, and | |||
: 3. A n;.:r;te f;;l tr=:f:r p=;. _ (p APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. | |||
ACTION: | |||
a With one or both offsite circuits of the above required A.C. | |||
4c.w (. electrical power sources inoperable, be in at least HOT SHUTOOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; . | |||
'demonst te the OPERABI Y of the remain A . t. , sources perfo ing Surveillan Requirement 4.8 .l.1. within one ur and mat ast once per 8 ours thereafter dg A | |||
MbM kb. With one or both diesel generators in one of the above required onsite A.C. electrical power divisions inoperable; b kt A,) 1. ' Demonstrate the OPERABil.ITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1 within one 6 1 , | |||
_ hour and at least once per 8 hours thereafterf ana if he (dieyan generator (s) ecame inoperaos aue to any ca eot]er h that an inoperabl support system, independenti testablel gdmponent, or or planned preventi e maintenance testina.1 l | |||
kejbcb 4.47 --l)iy/ dieselperforming generator atSurveillance a time within 24Requirement hours, unless the 4.8.1.1.2.a.4 for one ACE 4 I absence of any potential common mode failure for the f 4.2 ! 8 remaining diesel generators is determined, and lg | |||
.s FERMI UNIT 2 3/4 8-1 Amendrient No. Pf,119 PAGE L OF 08 hv 7 | |||
FLECTRICAL POWER SYSTEMS LIMITING CON 01 TION FOR OPERATION (Continued) 32,3 3 (Continued) | |||
R Y AcA A 3 2. verify within 8 hours and at least once >er a hours 4 thereafter. that CTG 11-1 is OPERABLE. Restore the get Act AD inoperable division to OPERABLE status within 7 days or be lg V in at least HOT SHUTDOWN within the next 12 hours and in AcT7oN C- COLD SHUTDOWN within the following 24 hours. - | |||
: 3. Of t requirements f ACTION b.2. abdve for CTG 11-1 ' | |||
be . either re re the inocerabW division k' tEj to OPhmno l<sta within 72 msRnot to exceto 1 Days uw we ume Ref Ad 4 6 the' division beca'me ino>erable): or satisfy the | |||
, ''!l! requirements of ACTION .).2 above within 72 hours and restore L ReIAck AS ', f the inoperable division to OPERABLE status within 7 daysfrom th k least HOT SHUTDOWN within the next 12 hours and in COLD A'W g f)l SHUTDOWN within the following 24 h , - - . - . -. | |||
: c. With one or both diesel generators i one f the above required onsite A.C. electrical power divisions inoperable. in addition to \ i b Ar t A7. ACTION b. above verify within @ hours that all required systems | |||
/ | |||
subsystems, trains. components and devices | |||
* that depend on the g remaining onsite A.C. electrical power division as a source of emeroency power are also OPERABLE: o ~ . wise. De ut at least wi , | |||
n ap nours o inCOLDSyV0WNwithifth5 wgn n 7 ( ordeclare rekk4- k%re. ine) d With both of the above recuired onsite A.C. electrical power AtTio d 6 divisions inoperable: | |||
: 1. Demonstrate the OPERABILITY of the remaining A.C. Sources by M bl performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours thereafter: and g m Ac4 6,/ 2. | |||
Restore at least one of the above required inoperable 7 s divisions to OPERABLE status within 2 hours or be in at least HOT SHUTDOWN within the next 12 hours ar' in COLD MTloMC. SHUTDOWN within the following 24 hours; and 3 Restore the second of the above required divisions to drN A'6 OPERABLE status within tne time required by Action b above from the time of initial bss or be in at least HOT SHUTDOWN Ac.T20pj C. within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. | |||
*Except for an inoperable primary containment oxygen monitoring hN instrumentation channel, required by Specification 3.3.7.5. that depends on A,%-- the remaining OPERABLE onsite A.C. electrical power division. In this case. r take the ACTION required by Specification 3.3.7.5 for the inoperability of both required primary containment oxygen monitoring instrumentation channels. | |||
FERMI . UNIT 2 3/4 8 2 Amendment No. 119. 132 PAGE S OF 08 g,97 | |||
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l 5PectFiorniva 3 5? I ELECTRftat p0WER SYSTEMS | |||
# 64 h##IOC4b 'E'bI'3 SURVEfttANCE REOUTREMENTS gg 3,9,;, ; 4.E.i.i. c Each of the above required independent circuits between the offsite l. | |||
transmission network and the onsite Class IE distribution system shall be , | |||
J determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availat. ity. | |||
-t.".I.I.2 Each of the above required diesel generators shall be demonstrated OPERABLE: | |||
i | |||
: a. At least once per 31 days [: ; =:== 15:T "aS.i By: | |||
l 25.2.l.9 1. Verifying the fuel level in the day fuel tank. | |||
(su Spec.ficab3.r.3g2. Verifying the fuel level in the fuel storage tank. | |||
g y,g'f' g 3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank. | |||
: 4. r T_ | |||
Verifying the diesel startsifr(om_E.t Hii = . | |||
T R S g'I. 7 ,19 sabient condition and accelerates to at least(900 rpalin less than or equal to g g*g*7 I 8 | |||
?0 seconds.* Thergenerator voltage and frequency shall be I 4160 e 4ZD volts and 60 e 1.2 Hz ef t"a M ccr-e Mte-tS Itirt c i- :'. . _fTh cieses geners6 snasi oc st tea to r Ini test my usi one of the fo owing signal : | |||
a Manual. | |||
Simula d loss-of-offs e power by i El f. tgg c) Simul ed loss-of-off ite power in njunction ith an ESF tuation test gnal, d) An F actuation t t signal by i el f. | |||
sR 3.g .g.3 5. Verifying the diesel generator is synchronized, loaded to Lreater than or equal to an indicated 2500-2600 kW in | |||
', l. . g,g 1, - fac.cordance with the manufacturer's recommendations, and i | |||
operates i MDD No4c 2 fps go A:. 3 is load for at least 60 minutes. | |||
3 t-MMNm;);;8m"re-h4%9"* ";" * | |||
: 7. Verifying the pressure in all diesel generator air start | |||
" ' M C b. 3* D receivers to be greater than or equal to 215 psig. | |||
% y.RI7 SE 5.1.s.1 #8k Aok.t' ''--< uM s ''a,4Q,dowed bya wumuy f quiof riorlo I dinh lh 34 M*l l4 8'*k 1 may Am peceded by an engine prelube period.All diesel The diesel generatar start generator starts for the p 44 3.S.I . 7 (10 see) from ambient conditions shall be performed at least | |||
~ | |||
onta .oer 184this the p;:rpose.cf days in thesetesting arveiriance surveillance may be tests. | |||
precededfall by other otherengine warmuostarts for { | |||
St3.T.t h { | |||
hjok. 3 Qear g the diesel enp(ne is minimized.( ,eroceduresfeconsnenoeo py the | |||
* manufact Y | |||
4 FERMI - UNIT 2 3/4 8-3 Amendment No. JJ,107 PAGE k 0F 08 ge,7 | |||
r 1 | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.1 AC SOURCES 0PERATING ; | |||
.A.5 CTS 4.8.1.1.2.a.4 footnote *. is silent on limitations or allowances between starting and loading the EDG. ITS SR 3.8.1.2 Note'2. and SR 3.8.1.7 Note, explicitly acknowledges that the := | |||
monthly EDG start may be "followed by a warmup period prior to 2. | |||
loading." Additionally. CTS 4.8.1.1.2.a.4 footnote *. allows. | |||
for all EDG starts other than the 184 day 10 second start, that | |||
" testing may be preceded by other warmup procedures." ITS does l@ | |||
not impose a pre condition on any EDG start other than the 184 day start to be "from standby condition." Therefore, performing the monthly EDG start after " warmup procedures" is not precluded. | |||
These changes do not reflect any revision in requirement, or change in intent. The changes are editorial presentation preferences only. | |||
A.6 Not used. lh A.7 CTS 4.8.1.1.2.e.5. 6..and 7 require the performance of an EDG functional test, which includes the requirement for: a " test i signal." " simulating" a signal, or "an emergency start signal." | |||
ITS SR 3.8.1.11, 17.-and 12 (respectively) permit the system functional to be initiated by an " actual or simulated" signal. | |||
This change allows satisfactory automatic EDG starts, as well as appropriately simulated EDG starts. to be used to fulfill the system functional Surveillance requirement. Operability is > | |||
adequately demonstrated because the EDGs can not discriminate between " actual" or " test" start signals. Since this is a reasonable interpretation of the existing requirement, this is an administrative change. | |||
FERMI UNIT 2 2 REVISION 7 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.1 AC SOURCES-0PERATING TECHNICAL CHANGES LESS RESTRICTIVE | |||
" Generic" LA.1 CTS LC0 3.8.1.1 provides details defining the two offsite AC power s'ources. and design features of the EDGs (i.e. " separate and independent," " Division I and Division II. each consisting of two emergency diesel generators." and "A separate fuel transfer T pump"). The details relating to system design. function. and o Operability are not necessary in the ITS. These details are o relocated to the Bases, which maintains the consistency with - | |||
NUREG 1433. The definition of Operability the Bases outline of k Operability details (which requires change contros in accordance with ITS 5.5.10. Bases Control Program), and the surveillance requirement for the fuel oil *cansfer pump (ITS SR 3.8.1.6). - | |||
provides sufficient control of these details. These details are l not required to be in the ITS. and ITS LCO. to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. | |||
LA.2 CTS SR 4.8.1.1.2.a.4 details the options for the start signals that can be used for the monthly EDG start. These details are relocated to the Bases. The relocation of this information maintains the consistency with NUREG-1433. This is acceptable because these details do not impact the requirement to start the EDG. These details can be adequately defined and controlled in the Bases, which require change control in accordance with ITS 5.5.10. Bases Control Program. These details are not required to i be in the ITS to provide adequate protection of the public health ! | |||
and safety since the requirement for EDG Operability remains in the Technical Specifications. | |||
LA.3 CTS 3.7.1.4 includes details relating to system design. function. | |||
and Operability for the EDG Cooling Water System. ITS 3.8.1 T includes only a requirement for EDG Operability and relocates the o details of subsystem design and specific Operability requirements O to the UFSAR. This is acceptable because thera details do not impact the requirement to maintain the EDG Operable and the ITS g | |||
definition for Operability ensures that all equipment required to maintain Operability is functioning. These details can be adequately defined and controlled in the UFSAR which require change control in accordance with 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of s~ . the public health and safety acceptable because these details do not impact the requirement to maintain the EDG Operable. | |||
FERMI UNIT 2 4 REVISION 7 06/18/99l | |||
T I | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.1 - AC SOURCES 0PERATING LR.1 CTS SR 4.8.1.1.2.a.6 requires an explicit verification that the EDG is aligned to provide standby power to the associated emergency buses. This SR is not specifically detailed in the ITS. | |||
Procedural controls on EDG standby alignment, and the definition df Operability are sufficient to ensure the EDG remains aligned to provide standby power. The relocation of this information maintains the consistency with NUREG 1433. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do not impact the requirement to maintain the equipment Operable. | |||
LR.2 CTS SR 4.8.1.1.2.e.8 requires the 24 hour EDG run be associated with a 10 second start, and requires confirmation of steady state ! | |||
voltage and frequency. Since the 10 second start requirement, and l the required operating voltage and frequency are stated and ; | |||
verified in other Surveillances explicitly repeating those requirements in the 24 hour run Surveillance is not necessary. | |||
These details can be relocated from the Technical Specifications. | |||
Regulatory control of changes to these requirements (e.g.. | |||
Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since the requirement for EDG Operability, verification of 10 second start capability. and verification of 24-hour run capability, remains in the Technical Specifications. | |||
LR.3 CTS SR 4.8.1.1.2.f requires a demonstration of EDG Operability "after modifications which could affect EDG interdependence." | |||
This requirement is relocated from the Technical Specifications. | |||
Verifying proper operability, including a simultaneous.EDG start, after maintenance on the EDG that could affect the simultaneous start is consistent with normal maintenance and operating practice for post-maintenance testing. Consequently. relocation of the requirement to verify Operability of the EDGs after maintenance is considered acceptable, and also maintains consistency with NUREG 1433. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do not impact the requirement to maintain the EDG independence and Operability. | |||
T LR.4 Not used. lg FERMI UNIT 2 8 REVISION 7. 06/18/99l | |||
I 1 | |||
l DISCUSSION OF CHANGES ITS: SECTION 3.8.1 AC SOURCES 0PERATING l 1 | |||
LR.5 CTS 4.7.1.4 requires explicit verification of the proper positioning of the valves in the EDG cooling water flow path every l 31 days. ITS does not retain this explicit verification; however. | |||
ITS SR 3.8.1.2 and SR 3.8.1.3 does require EDG start and run (for a' minimum of 60 minutes). Since the EDG cooling water system provides the required cooling for all EDG operation the proper lineup is implicitly assured every 31 days by satisfactory operation of the required EDG load run. Regulatory control of changes to these requirements (e.g. Technical Specification j amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do not impact the requirement to maintain the EDG in an Operable status. | |||
l l | |||
FERMI - UNIT 2 9 REVISION 7, 06/18/99lh | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.1 - AC SOURCES 0PERATING TECHNICAL CHANGES - LESS RESTRICTIVE | |||
'Speci fic" L.1 CTS 3.8.1.1 Action a in addition to commencing an immediate plant shutdown with one or both offsite circuits inoperable, requires performance of CTS 4,8.1.1.1 (offsite circuit breaker alignment and power availability) within 1 hour and once per 8 hours thereafter. This verification of offsite circuit status is deleted. The verification is only required when one of two offsite circuits is inoperable, and even if the second circuit were to be discovered inoperable, no additional Actions or more restrictive time to complete the plant shutdown would be imposed. | |||
Since the plant is required to commence an immediate shutdown (be in MODE 3 in 12 hours) with one or both circuits _ inoperable, eliminating an increased frequency for verification of offsite circuit status will not adversely impact safety. | |||
L.2 With one EDG inoperable, CTS 3.8.1.1. Action c requires all features that depend on the remaining Operable EDG Division to be Operable. If this requirement can not be met, the CTS Action ! | |||
requires a shutdown be commenced within 2 hours. ITS 3.8.1 Required Action A.2 provides two relaxations: | |||
l@ | |||
: 1. Rather than a plant shutdown requirement, the ITS requires that the feature (s) supported by the inoperable EDG be declared inoperable if its redundant counterpart is inoperable. This provides for actions appropriate to the actual inoperabilities, which may avoid an immediate shutdown. For example, if one or both Division II EDGs are inoperable in conjunction with the Division I hydrogen recombiner, CTS Actions would require the immediate shutdown, while ITS would allow entering Actions for both hydrogen recombiners inoperable (a 7 day allowance is provided in the ITS Specification for hydrogen recombiners): thereby providing for the entire Completion Time to restore the EDG to Operable status. ' | |||
: 2. . ITS allows 4 hours (versus 2 hours) to restore inoperable features or inoperable EDG(s). This extension provides additional time, and is considered a reasonable time to effect repairs prior to requiring a forced shutdown of the unit. | |||
FERMI - UNIT 2 10 REVISION 7 06/18/99l | |||
AC Sources-Operating 3.8.1 | |||
, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME (A. ( % tinued) / A.3 R ore [ required) 42 hours fsite circuit to OPERABLE status. ANQ 6 days from discovery f failure meet LCO _ d Qr6of EOd'D One 3. ,....., - | |||
1 Perform SR 3.8.1.1 1 hour f inoperable. for OPERABLE | |||
- n _... ._n-offsite AND deMm b) in orie divial circuit (s). Ac han cl .1 Once per 8 hours thereafter 2 Declare required 4 hours from feature (s),supporte discovery of ANan C by the inoperable ,C=ditir " | |||
inoperable when the concurrent'with redundant required inoperability of feature (s) are redundant inoperable. required feature (s) | |||
* @W' (continued) | |||
).3 WilYY CUS DM fw T of CTCr //~l . gpg Q t | |||
WR/4-STS- 3.8-2 Rev 1, 04/07/05-4/7 1 l | |||
l | |||
AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME | |||
: f. (continued) M.1 OPERABLE f24} hours e inoperable due to ) | |||
common cause failure. $tiloA) b. g E < | |||
E I y | |||
.'[ @2 Perform SR 3 .l.2 J24yhours 0 5/ | |||
for OPERABLE (s). | |||
% dae.vh-gg j %t-n1o nYok ^ | |||
h J-'in 1 F :- N'95- 72 hours h e b b.3 ) | |||
- ? ? "l- | |||
{AchmbY) | |||
A. 6 Resfere bow EOGs in -( Adond.3) tk division fp DPdAftE s w .. . _ | |||
_-e w[ # | |||
23 bn=2- | |||
'. iwo tr rea] offsite L.a uud r. .wyuired 42 nuu. . . ' . - . . . | |||
circui inoperable. feature (s) inop able discovery of when the redun nt Condition required fea re(s) concurren with are inopera e. inopera lity of redund t requ ed f,f fea re(s) en C.2 Re ore one 24 hou equired) offsite y ircuit to OPERABL ) | |||
tatus. s (continued) | |||
BHR/4-STS- 3.8-3 Re" 1, 01/07/05 1 | |||
\ | |||
Rw 7 | |||
) | |||
l l | |||
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS <CD # | |||
SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days l indicated power availability for each | |||
--' __; offsite circuit. | |||
h43*l l) l SR 3.8.1.2 -------,-- --NOTES 4.,_ _ _------------ | |||
: 4. . .. . .. .m ... ......... | |||
d | |||
. Al starts may be preceded by an engine prelube period and followed by T *l L18 y 3i a wamup period prior to loading. | |||
#. A modified DG start involving idling g and gradual acceleration to i synchronous speed may be used for this , | |||
P.6 "' > sR as reco end.d by the manufacturer.* | |||
When noatri start proced es are n | |||
{ I used, the , voltage, d freque ey toleranc of SR 3.8.1.7 must be .t . | |||
Verify each starts ?. _ ;t r e; ; As ;;,;;i''-d 4-k.l '"t n .fiti n; and achieves steady state Te n S.^.'-1 voltage 2 (3740E V and s 14580 V and frequency 2 p8.8gHz and s LS .2kHz. 34 16 l.ll,d.h' (continued) 17./4 MS- 3.8-6 Rev 1, 04/07/95 t | |||
1 AC Sources-Operating | |||
..u.1 l | |||
SURVEILLANCE REQUIREMENTS (continued) | |||
[C75h w | |||
SURVEILLANCE FREQUENCY h t | |||
i SR 3.8.1.7 --- | |||
---------NOTE------- --------- | |||
All DG starts may be preceded by an engine e\ | |||
, and Q(ow b prelube period O warm q wiedp/,9 rf 4/,2. l. ).2 a N.Vs/ | |||
.tv ioa *nj ; a. ', | |||
Verify each starts from st 184 days (48.l<\.2AY condition and achieves in s seconds,+ | |||
bb .' | |||
= - - - | |||
voltage 2 (3740kV and s J'45801 V and V0It* | |||
b' frequency 2M8.gHz and's QI'.2} Hz. Op%L 13700 V Oe4151 T (b S M Ns h j t | |||
SR 3.8. 8 | |||
- - - - - - - - - - - - / -----/- | |||
Q+ | |||
This urveillan TE---- / | |||
shallnotbeperform[d' k' in DE 1 or P However redit may 6e en for u anned eve s that sa sfy / | |||
.hir SR. | |||
m /- | |||
Verif [ automatic and manua tran er month of nit power s ply))from e [no al y of ite circuit o the alte ate] j c fsite circui . / | |||
(continued) | |||
EWR/4-STS- 3.8-8 Re % -04/07/M-8ev 7 | |||
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) _ | |||
SURVEILLANCE TREQUENCY SR 3.8.1. --- | |||
g---- ----NOT EY---------------- - | |||
p h A11 DG Istarts may 'n preceded by an (DK 4.g) engine prelube period. | |||
+ | |||
Thi Survei ance sh 1 not be f | |||
p formed n MODE or 2. H ever, | |||
@ /2 edit events be tak for unp nned at sati y this S . | |||
l i | |||
i gr @.a.zo) | |||
Verify on an actual or simulated Emergency /18monthsb Core Coolin System (ECCS) initiation signal each auto-starts f = - u.._f e%. an \} %- .I | |||
: a. In 5 seconds after auto-start and during tests, achieves voltage fres"8 d/ ) 2 (374 g V a p T C ;] % [( {l | |||
: b. In ; [! C : ent -'te rfte-ste-t , h rnd fr-'r; *er+ ;Jehieves frequency hJ58.81Hzandf$1.2[ lf , | |||
( i | |||
: c. 'Operatesfor235} minute, i y | |||
: d. Pe anently con cted loads r in ergized fr the offsite wer Y # > | |||
fk "A 6 4M % | |||
system; and g e Emergency ends are en gized[or h auto-co ected throu the automa e load .quencer) fr the offdt nower y i syst (continued) | |||
WR/' STS 3.8-11 Rev-h-04/OU95-- | |||
Rev 7 | |||
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.8.1 ------------------NOT E S------------------- | |||
: 1. Homentary transients outside the load 0g (,, L , | |||
, p,i wnrt TMENF-fEPN range [do not invalidate this test. | |||
2 This urveill ce shall t be O91 per ormed in E I or . Howeve , | |||
dit may taken f unplann vents t t satisfy his SR. | |||
Verify each :;; ret h; it : ;: :7 n; 3 r hE18monthsA OP.I.. S " e! coerates for 1 24 hours: | |||
@!i but the, kal t 2 novrs) 29,0 | |||
/ | |||
Nd I.I'2*8,3\ / | |||
a .- tot ^M nours loaded 2 kW and 5 - = | |||
-kW;an[d-ft nal _t 2.)e | |||
: b. Fo --- =: hours of the test loadedi kW and s kW. | |||
24 SR 3.8.1. ----------------- NOTES ---------------- | |||
I4 | |||
: 1. This Surveillance shall be performed (g g.t.t.2.c. 9, h | |||
@within5minutesofshuttingdownthe after the has operated kW e,r./ : | |||
2L g oaded 2 ggi,gg E | |||
heakm h,x , | |||
Momentary transients outside of load stab:U.r.e d ) | |||
ran do not invalidate this test. | |||
: 2. All starts may be preceded by an engine prelube period. / g g' g~ | |||
h.N' v. e.l.2.a 4 *-) | |||
rify each starts and achieves )R8monthsK | |||
$ $Ji seconds, voltage 2 (3740F V and / \ | |||
M8t} V and frequency 2 JJ8.8) Hz and (LI I'I'I'7' d | |||
g,g/ | |||
sf61.2)Hz. q,g ,g ,g ,7,q, q) m - | |||
yo y_g 3.j. g y ,ng g (continued) hEs.sh ;a4 1(.l 9 | |||
: b. A dy s h tz, lg SWR /4-STS 3.8-13 h v 1, 04/07/95 s | |||
sev7 | |||
AC Sources-Operating B 3.8.1 BASES ACTIONS M (continued) concurrently is acceptable because it minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown. | |||
The remaining OPERABLE DGs and offsite circuits are adequate to supply electrical power to the onsite Class 1E Distribution System. Thus, on a component basis, single failure protection for the required feature's function may have been lost; however, function has not been lost. The 4 hour Completion Time takes into account the component OPERASILITY of the redundant counterpart to the inoperable , | |||
required feature. Additionally, the 4 hour Completion Time i takes into account the capacity and capability of the | |||
/NSE7ET remaining AC sources, reasonable time for repairs, and low probability of a DBA occurring during this period. | |||
B 3 8.\ - 2 4 | |||
. 1 an .2 { | |||
Required Action 1 provides an. allowance to avoid (5) '\ | |||
unnecessary testing of OPERABLE DGs. If it can be de3 mined that the cause of the inoperable DG oes not h exist on the OPERABLE perfomed. If the cavre of D6t SR 3.8.1.2 inoperability does exists h not have to be -i on other DG(s), therare declared inoperable upon discovery. and mo tion t1&of LC0 3.8.16& entered. Once the failure is k | |||
'@~Cond< | |||
C repa' red, and th onnon cTuse failure no longer exists, Required Actio 1 is satisfied. If the cause of the initial inoperable DG cannot be confimed not to exist on '% | |||
the remaining DG(s), performance of SR 3.8.1.2 suffices to provide assurance of continu LITY of those DGs. I | |||
! f,I In the event the inoperable cred PERABLE A' | |||
status prior to completing either 1 or 2,the(plant corrective action programF will con 31nue to evaluate tne common cause possibility. This continued evaluation, however, is no longer under the 24 hour constraint imposed while in Condition * | |||
.A According to Generic etter84-15(Ref.7),[24[hoursisa reasonable time to confirm that the OPERABLE DGs are not affected by the same problem as the inoperable DG. | |||
(continued) 8WR/4-STS- 8 3.8-9 ki 1, 04/07/05 | |||
#ev7 4 | |||
AC Sources Operating B 3.8.1 Insert B 3.8.1-8 Ad. _ | |||
i To minimize the impact of operation with an inoperable EDG, it is necessary to periodically ensure the availability of CTG 111. *R The verification of the status of CTG 11-1 is performed by an administrative check of breaker and line availability, and the ! | |||
CTG 111 ability to supply Division I loads. Since this Required Action only specifies " verify the status." even when CTG 111 is not available it does not result in this Required Actions being not met. However, upon discovery that CTG 11 1 is unavailable, the limitations of Required Action A.5 are imposed. | |||
FERMI UNIT 2 Page B 3.8 9 -(Insert) REVISION 7 06/18/99l | |||
AC Sources-Operating B 3.8.1 BASES - | |||
i ACTIONS (continued) p. | |||
a=h ondh i | |||
v>ith no OPETEAoSLE EDGs % me divi jan S h | |||
j _ | |||
T According to Regulatory Guide 1.g3 (Ref 6), operation may Mg#*M gEDGs) continue is Cei. | |||
73 hours.,:a tier. | |||
Cer. C for | |||
: tier. a period O, the that remaining should not OPERABLE DGsexceed and in nit d | |||
* Vi3* o fsite circuits are adequate to supply electrical power to d | |||
looFoO the onsite Class IE Distribution System.fffhe 72 hour M~ l i.aspietion Time takes into account tne capacity and capability of the remaining AC sources, reasonable time for repairs, and low probability of a DBA occurring during this f gINS3 81-@T 3a Periody | |||
/ | |||
mie second lation Time'for Requi Action 8.4 establishe a init on the maximum me allowed for any | |||
- combinati n of required AC power urces to be inoperable g@{ during y single contiguous oc rrence of failing to meet the LC . If Condition B is e ered while, for instance, a I | |||
8 s11-3b -l offs e circuit is inoPerabi and that circuit is sub quently restored OPE E, the LC0 may already hav be not met for up to 72 ours. This situation coul ead | |||
, t a total of 144 hours since initial failure of th LCO, t restore the DG. At his time, an offsite circu could again become inopera e, the DG restored OPERABL and an additional 72 hours for a total of 9 days) all d prior to complete restorat n of the LCO. The 5 day C letion Time provides a limit n the time allowed in a sp ified condition after discovery of failure to me the LC0. This limit is cons ered reasonable for situat ns in which Conditions and B are entered concurre ly. The 'AM" connector etween the 72 ho::r and 6 d Completion Times means th both Completion Times ap y simultaneously, and the nor restrictive must be met. | |||
1 As i Required Action B.2, the ompletion Time allows fo an exc tion to the normal 'ti zero" for beginning the ai owed outage time " clock This exception results tablishing the ' time zero' at the time that the LC was nitially not met, inst fid of the time that Conditi n B was entered. | |||
C.1 and C.2 . | |||
Required Act n C.I addresses actions to be aken in the event of i perability of redundant requir d features us V (continued) | |||
BWR/4-ST B 3.8-10 -Rev-17-04/07/9F , | |||
1 l | |||
~, | |||
&v7 | |||
AC Sources-Operating B 3.8.1 I | |||
i Insert B 3.8.1-3a Required Action A.5 imposes this 72_ hour' Completion time i from the discovery of the non availability CTG 11-1. | |||
However, if CTG 11-1 is available to supply Division I loads (determined by administrative' check of breaker, line 7 availability, and CTG 111 status) Required Action A.5 would be met-and Required Action A.6 would allow the restoration k l time of 7 days. | |||
l Insert B 3.8.1 3b The_7 day Completion Time to restore all EDGs to OPERABLE l status takes into account the capacity and capability of the i remaining AC Sources as well as the additional reliability l afforded by the availability of CTG 11-1. ! | |||
) | |||
i l | |||
I 1 | |||
FERMI - UNIT 2 Page B 3.810 (Insert) REVISION 7 06/18/99l | |||
AC Sources-Operating B 3.8.1 BASES SURVEILtANCE minimum and maximum frequencies of the DG are 58.8 Hz and REQUIREMENTS 61.2 Hz, respectively. These values are equal to i 2% of (continued) the 60 Hz nominal frequency and are derived from the recommendations found in Regulatory Guide 1.9 (Ref. 3). | |||
SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are connected to their preferred power source and that appropriate independence of offsite circuits is maintained. | |||
The 7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room. | |||
SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the standby electrical power supply to mitigate DBAs and transients and maintain the unit in a cafe chutdown condition. | |||
cth6nttalS h n% M) | |||
OfI Tominimizethe&wearenmovingpartssnatnonotget lubricated when the engine is not running, these SRs have - | |||
been modified by a Note (Note forSR3.8.1.2andNote@ | |||
for SR 3.8.1.7) to indicate that 11 DG starts for these tI Surveillances may be preceded by n engine prelube period | |||
.and followed by a warm to loading. A WQ hWOJ For the purposes of | |||
$ " I$EM w __ estina. t e DGs are startedefronF stanuu w.diti:.;. ]5tandby conditions for a DG mean that b 3 I'I d 'the diesel engine coolant and oil are being continuously j circulated and temperature is being maintained consistent y with manufacturer recommendations. z G2. | |||
In order to reduce stre,s; and wear Tn diesel engines, y manufacturerkreconsnend,thmodifiedstartinwhichthe No | |||
' starting speed of DGs is imited, warmup is limited to this i ,, lower speed, and the DG are gradually accelerated to synchronous speed prior o loading. These start procedures S- | |||
.q g6 W] are,tfjeintentofNote which is onlygapplicable when4veh- ,1,, | |||
pg 7........p............,m._ . , u,. ..nu a cw. . g | |||
.(g 3.d r anowel to sahsjue sR3.t.ia W no (continued) | |||
SuRJ4-STS-fcMing Sg 3g,,;3, 8 3.bl6 R=1,MlWlW Rgv 7 | |||
1 AC Sources 0perating ) | |||
B 3.8.1 l | |||
i Insert B 3.8.1-6 __ | |||
<<Not used>> lT 1 | |||
l Insert B 3.8.1-7 to hot conditions by using one of the following signals: | |||
l Manual. l Simulated loss-of offsite power by itself, ; | |||
Simulated loss of-offsite power in conjunction with an l ESF actuation test signal. or An ESF actuation test signal by itself. l l | |||
i f | |||
FERMI UNIT 2 Page B 3.8-16 (Insert) REVISION 7 06/18/99l 4 | |||
-A | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 (continued) | |||
REQUIREMENTS SR 3.8.1.7 requires that, at a 184 day Frequency, the DG gSgty FRoy starts from standhv conditions and achieves required voltage gg | |||
/ anc frequency within Qseconds.4 The GBqLecond start PA06 6 3d-4 requirement suppo ts the assumpuuns in the design basis LOCA analysis o uF , Section &6.3A (Ref. 12). The O' start requiremen is not appitcable to SR 3.8.1.2 ' :: Met- ? | |||
second Og'g 4-f 2 ;.61.2), | |||
above 2[;a modified i used. If : ::fif t:dstart tart quirement/of SR 3.8.1.7 ap ies sterts not p.;;:d:/n us , the[ 124econd descriedJ) 3 | |||
,A | |||
/ lNSERit-h Since SR 3.8.1.7 does require a cond rt, it is more restrictive than SR 3.8.1.2, and t may be performed in lieu e/ | |||
of SR 3.8.1.2. 'H : ;;::: t h th: t;te..t .T e^vi. i vi 6 | |||
{ 6 315.)-k ; !" ? l l ?. | |||
l Og,j The nomal 31 day Frequency for SR 3.8.1.2 (;;e T;ble 0.0.1-1, i cl WM:: " ..eraivr 7.e Oc;..Joi.-) is consistent with T Regulatory Guide 1.g (Ref. 3). The 184 day Frequency for O SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7). These Frequencies provide J l | |||
adequate assurance of DG OPERABILITY, while minimizing ' | |||
degradation resulting from testing. | |||
l SR 3.8.1.3 1 f,I j . g] | |||
This Surveillance e rifie:J that the DGs are capable of 3 synchronizing and accepting greater than or equal to the g7 83S.bl/6 equivalent of the maximum expected accident loads # A minimem | |||
'? | |||
i' run time of 50 minutes is required to stabutze engine temperatures, while minimizing the time that the DG is Y connected to the offsite source. | |||
Although no power factor requirements are established by this SR, the DG is normally operated at a power factor between 20.8 laggingle and the machine,while f,1.0A1.0kisanoperationallimitation4to The f.p.8],value is the design rating of g i ensure circulating,{c,urrents are minimizedf Tl.. M d i;;d i; | |||
). | |||
'r: MM t: re:id r;;th; s...i.;dui,.T Oe M. Routine overloading may nsult in more frequent teardown inspections k< | |||
in accordance with vendor recommendations in order to maintain DG OPERABILITY. | |||
(continued) | |||
BWR/4-STS- B 3.8-17 -Rev-1 704/07/95 Rev7 | |||
l i | |||
AC Sources-Operating B 3.8.1 1 | |||
Insert B 3.8.1-4a In addition to the SR requirements, the time for the EDG to O reach steady state operation, unless the modified EDG start d i method is employed, is periodically monitored and the trend 6 evaluated to identify degradation of governor and voltage j regulator performance. | |||
l I | |||
3 1 | |||
Insert B 3.8.1-4b l4 I without the risk of overloading the EDG. The EDG is tested l f at approximately 90% of its continuous load rating, which provides margin to excessivo EDG loading, while demonstrating f the EDG capability to carry loads near the maximum expected accident loads. | |||
1 | |||
~ FERMI UNIT 2 Page B 3.8 17 (Insert) REVISION 7 06/18/99l | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS SR 3.8.1.3 (continued) y The normal 31 day Frequency for this Surveillance (::: - I i c h 0.0.1-1) is consistent with Regulatory Guide 1.9 5 (Ref. 3). M Note I modifies this Surveillance to indicate that diesel engine runs for this Surveillance may include gradual loading, as recesmended by the manufacturer, so that mechanical stress and wear o esel engine are minimized. | |||
.s. | |||
Note 2 mod s Surveillance by ng that momentary transients cause of changing bus lo not invalidate Op,q o d $!ML M this test. Similarly, momentary powe ctor transients-abows. | |||
permal yy 'th: Mrit do not invalidate the test. | |||
Note 3 indicates that this Surveillance should be conducted on only one DG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations. | |||
I Note 4 s pulates a prerequ Ite requirement for performan f.3 of thi SR. A successful | |||
<credi satisfactory per ruance s start must precede t p test to SR 3.8.1.4 This SR provides verification that the level of fuel oil in the day tank-[W ea$t :::t:d 0;;M is at or above the level at which fuel oil is automaticaily added. The level is expressed as an equivalent volume in gallons, and is selected to ensure adequate fuel oil "or a minimum of I hour of DG Q9,1 operation at full load { ; ".l The 31 day Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period. | |||
SR 3.8.1.5 Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in 1 | |||
(continued) | |||
"'"f t "S | |||
. B 3.5-18 Rev 1, 04/07/95 Ret 7 | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE SR 3.B.III.(continued) ~ | |||
REQUIREMENTS | |||
: b. fomance of the R will not cause pe urbations to the electrical distribution syst hat could res t n a challenge steady state oper on or to plan safety systems and c Perfomance f the SR, or failu of the SR, wi not cause, or sult in, an A00 wi attendant ch enge to plant taf y cytt . | |||
SR 3.s.1. | |||
Regulatory Guide 3.108 (Ref 9), paragraph 2.a.(3), requires demonstrationonceperp8monthsjtthattheDGscanstartand run continuously at ful load capability for an interval of f.\ not less than 24 hours-22 hours of which is at a load equivalent to the continuous rating of the DG, and 2 hours of ~. | |||
22hwere At which is at a load equivalent to 1105 of the continuous dutyprinj-@ l rating of the DG./Prant smmhas taken an exception to thi qpedatdt hD'/o reouirement and perfoms thed2 hour run at th 2000 Sn mei% | |||
l of40 Umhnuous rating (yee sw). ine IK, starts for this Surveillance can be N i performed ither from standby or hot conditions. The Mnw ; | |||
ftthg(290 kW-bNgi provision for prelube and warmup, discussed in SR 3.8.1.2, j i gIpQ g Dnd fo dual loading, discussed in SR 3.8.1.3, are applica e to this SR. , | |||
hno er to ensure th the DG is tested nder load con hKW -2foD t are as close t esign conditions s possible, t ing on m st be performed ing a power fact s [0.9 . Th power | |||
( ' factor is chose o be representat eofthea]ctu d 7 | |||
,3 W sis inducti loadina that the could exoeri e A load 7 | |||
bana is provi'ded to avoid routine overloading of the DG. | |||
Routine overloading may result in more frequent teardown (9 | |||
/M 5EET inspections in accordance with vendor reconnendations in order i g to maintain DG OPERABILITY. | |||
The tf18 monthpFrequency is consistent with the reconnendations of Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(3); takes into consideration plant conditions required to perfom the Surveillance; and is intended to be consistent with expected fuel cycle lengths. | |||
(continued) | |||
D'"!/t ST: 8 3.8-27 Rev 4 -04/07/95 Rev 7 | |||
AC Sources-0perating B 3.8.1 Insert B 3.8.1-9 . | |||
Although no power factor requiresents are established by this SR. | |||
- the EDG is normally operated at a power factor between 0.8 lagging C i and 1.0. The 0.8 value is the design rating of the machine, while a the 1.0 is an operational limitation to ensure circulating currents are minimized. | |||
[ | |||
l FERMI UNIT 2 Page. B 3.8 27 (Insert) REVISION 7 06/18/99l | |||
AC Sources-Operating B 3.B.1 BASES SURVEILLANCE SR 3.8.1. continued) | |||
REQUIREMENTS 0-This Surveillance has been modified by $ Note'K. Note'k states that momentary transients due to chanoino bus loads do not invalidate this test. /Simpiarly, somentpy power | |||
' factor The | |||
/ason transients for No mave 2 is the thatlimit / do d ing not invalidate operatio the te with the rea or critical performance this Surveil ance could ause | |||
[,3 pe urbations t the electric distribution systems t at would cha' enge continu steady state operation nd, as result, pla ; safety syst s. Credit be taken or unplanned av ts that satis y this SR. j - | |||
SR 3.8.1. | |||
Of.'$ This Surveillance demonstrates that he diesel engine can restart from a hot condition, such as subsequent to shutdown O' from normal Surveillances, and achieve GM SfatLVol$ and frequency within 11 R secondsr TheWMeauired voltaae second time is Qo | |||
#g g derivec from the requirements of the acc'idert analysis to respond to a design basis large break LOCA. The 8 month)o Frequency is consistent with the recommendations @of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(5). | |||
This SR is modified by two Notes. Note 1 ensures that the ! | |||
test is performed with the diesel sufficiently hot. The { | |||
requirement that the diesel has operated for at least 2 hours Og new full load conditions prior to performance of this urveillance is based on manufacturer recommendations for '>- | |||
achieving hot conditions. Sne so.u v.uv ,, ,,. .. : d;d t; e . . d - I | |||
,vuuns v1 riveuing vi ... % . Routine overloads may result ~ | |||
in more frequent teardown inspections in accordance with 'k vendor reconnendations in order to maintain DG OPERABILITY. | |||
Momentary transients due to changing bus loads do not invalidate this test. Note 2 allows all DG starts to be preceded by an engine prelube period to minimize wear and tear l on the diesel during testing. | |||
SR 3.8.1. | |||
As required by Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(6), this Surveillance ensures that the manual p,9 synchronization ind u t===t w 1oad transfer from the DG to the offsite source can be made and that the DG can be returned (continued) | |||
SWR /4-STS- B 3.8-28 ":V 1, 04/07/05 Rav7 | |||
AC Sources-Oporating B 3.8.1 BASES REFERENCES (continued) 12hSAR,Sectiong6.3g | |||
: 13. ASME Boiler and Pressure Vessel Code, Section XI. | |||
: 14. IEEE Standard 308. | |||
N | |||
.r SWR /4 STS. B 3.8-34 Rev 1, 04/07/95-Rev 7 | |||
I JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ) | |||
ITS: SECTION 3.8.1 AC SOURCES 0PERATING J e | |||
I | |||
: e. Not used. lh I | |||
: f. ISTS SR Notes limiting Modes that an SR can be performed in.. | |||
-are not adopted, consistent with CTS requirements. CTS detail ' | |||
prescribing Mode limitations has been relocated via Amendment 95 consistent with Generic Letter 91 04. | |||
: g. ISTS SR details incorporating EDG power factor limitations is not adopted - consistent with CTS level of detail. Any applicable power factor limitations on EDG testing will continue to be addressed outside of Technical Specifications. | |||
: h. During the restoration from a loss of-offsite power (ITS SR 3.8.1.15) Fermi 2 (per CTS) returns the EDG to a " standby" status. This criteria imposes an additional confirmation J beyond the ISTS requirement to only return the EDG to a " ready-to load" status. | |||
: 1. The change to ITS SR 3.8.1.8 is based on the fact that Fermi 2 electrical design is such that each ESF division is not allowed bo to be transferred to the opposite division offsite source l during plant operation. An offsite power source is cross tied to the opposite _ division only in maintenance situations. JFD d l l | |||
P.1 will be modified to reflect this justification. | |||
: j. The change to ITS SR 3.8.1.12 is based on the fact that the bypass of Fermi 2 EDG automatic trips on ECCS initiation signals does not require a concurrent bus loss of voltage k | |||
i signal. | |||
P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses. | |||
P.3 Bases changes are made to reflect changes made to the Specification. | |||
Refer to the Specification, and associated JFD if applicable, for additional detail. Some are specifically addressed: | |||
a. | |||
A ITS SR 3.8.1.13 (based on CTS) does not impose an explicit power T factor limitation. Therefore the Bases are modified to discuss the " normal" power factor operation. consistent with that provided in the Bases of ITS SR 3.8.1.3. | |||
P.4 Editorial Bases change made for clarity, due to Fermi specific design and terminology, or consistency. | |||
FERMI UNIT 2 2 REVISION 7 06/18/99l | |||
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.1 AC SOURCES 0PERATING N | |||
P.5 NUREG 1433, SR 3.8.1.2 Note 3 second sentence, is not adopted. _L The second sentence of the Note is a restriction not required by d CTS.- | |||
P.6 SR 3.8.1.2 does not accurately reflect the allowance for '' warmup l | |||
' prior to loading" as its Bases do, and as SR 3.8.1.7 does, y Therefore, ITS SR 3.8.1.2 Note 2 is corrected to include this - | |||
intended clarification of EDG allowed operation. k P.7 NUREG 1433 LCO Item c, and Condition F, explicitly address requirements and Actions for automatic load sequencers: but include a Reviewer's. Note indicating the acceptability of deleting the explicit treatment if the sequencer affects only affects the associated EDG. The Fermi 2 design for the load .sequencers is such that they do not affect offsite circuit loading, and only l affect EDG loading. Therefore. the option is implemented to implicitly include the sequencer Operability with the requirement for the Operability of the EDG and delete the explicit treatment. | |||
This is also consistent with the CTS treatment. | |||
P.8 : ' Additional detail added to the Bases to-reflect information relocated | |||
'from CTS. Refer to. CTS Discussion Of Changes to the related requirement'.for a detailed justification of changes made to the current licensing basis, which are reflected in the ITS as presented. | |||
P.9 - The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification | |||
" split" criteria found in 10 CFR 50.36(c)(2)(ii). | |||
GENERIC CHANGES 3 | |||
n C.1 TSTF 163. Rev 2: NRC' approved change to NUREG 1433. | |||
FERMI'- UNIT 2 3- REVISION 7 06/18/99l | |||
SPET.-1 Ft CArtaN f,?.2 fAGf kEYHWED , | |||
/Al d'67' 7 l | |||
l l | |||
l PAGE / _0F 02 Tgv7 | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.2 AC SOURCES-SHUTDOWN M.2 CTS 3.8.1.2 Action a for inoperable AC sources, requires immediate corrective actions to restore the inoperable AC sources, but only "whea in H00E 5 with the water level less than 20 feet. 6 inches above the reactor vessel flange." ITS 3.8.2 requires the immediate corrective actions to restore the inoperable AC. sources regardless of plant conditions. This eliminates flexibility and is therefore a more restrictive change. | |||
TECHNICAL CHANGES - LESS RESTRICTIVE | |||
" Generic" LA.1 CTS LC0 3.8.1.2.b provides details defining the design features of _ | |||
the EDGs (i.e.. "each diesel generator with: " . and "A fuel l transfer pump"). The details relating to system design function. | |||
f 4 | |||
and Operability are not necessary in the ITS. These details are relocated to the Bases, which maintains consistency with NUREG- Q 1433. The definition of Operability, the Bases outline of Operability details (which requires change control in accordance with ITS 5.5.10. Bases Control Program), and the surveillance requirement for the fuel oil transfer pump (ITS SR 3.8.1.6), | |||
provides sufficient control of these details. These details are not required to be in the ITS. and ITS LCO. to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. | |||
This approach provides an effective level of regulatory control and provides for a more appropriate change control process. The level of safety of facility operation is unaffected by the change because there is no change in the requirement to maintain the equipment Operable. Furthermore. NRC and Detroit Edison resources associated with processing license amendments to these requirements will be reduced. This change is a less restrictive ! | |||
administrative change with no impact on safety. | |||
FERMI - UNIT 2 3 REVISION 7 06/18/99l | |||
r DISCUSSION OF CHANGES ITS: SECTION 3.8.2 - AC SOURCES-SHUTDOWN | |||
-LA.2 CTS 3.8.1.2 Action a for the inoperability of a required AC source. requires suspension of " crane operations over the spent fuel pool ." These " crane operation" issues are relocated from the CTS (as in the case of. CTS 3.9.7. " Crane Travel-Spent Fuel Storage Pool"), based on the administrative controls of heavy - | |||
loads (which are in accordance with Fermi 2 positions on NUREG- J. | |||
0612 and Generic Letter 80 113). Therefore, the Actions associated with crane operation following a loss of power sources have been relocated to the UFSAR. consistent with other heavy-loads issues. . Relocation to UFSAR maintains consistency with | |||
-NUREG 1433. Changes to the UFSAR will be controlled by the provisions of 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the requirement for power source Operability and restoration remains in the Technical Specifications. | |||
LA.3 CTS 3.7.1.4 includes details relating to system design, function. | |||
and Operability for the EDG Cooling Water System. ITS 3.8.1 T~ | |||
includes only a requirement for EDG Operability and relocates the 9 details of subsystem design and specific Operability requirements O to the UFSAR. This is acceptable because these details do not < | |||
impact the' requirement to maintain the EDG Operable and the ITS definition for Operability ensures that all equipment required to maintain Operability is functioning. These details can be adequately defined and controlled in the UFSAR which require change control in accordance with 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety acceptable because these details do not impact the requirement to maintain the EDG Operable. i i | |||
LA.4 CTS 4.7.1.4 details a requirement for the EDG cooling water pump to automatically start upon receipt of a start signal for the associated EDG. ITS SR 3.8.2.1 requires EDG automatic starts i (i.e., SP 3 8.1.10 and SR 3.8.1.11) for proper operation of an l Operabli ED The detail of verification of proper EDG starting. ! | |||
such thet i1 includes verification of EDG cooling water pump start. is relocated to the Bases for SR 3.8.1.10 and SR 3.8.1.11. | |||
This detail can be adequately defined and controlled in the Bases, which require change control in accordance with Chapter 5 of the ITS.. This detail is not required to be in the ITS to provide adequate protection of the public health and safety since the detail in the ITS is adequate for assuring proper performance of j the EDGs. | |||
FERMI UNIT 2 4 REVISION 7 06/18/99l | |||
r I | |||
DISCUSSION OF CHANGES l ITS: SECTION 3.8.2 AC SOURCES SHUTDOWN LR.1 CTS 4.7.1.4 requires explicit verification of the proper positioning of the valves in the EDG cooling water flow path every 31 days. ITS does not retain this explicit verification: however. | |||
l ITS SR 3.8.1.2 and SR 3.8.1.3 does require EDG start and run (for a minimum of 60 minutes). Since the EDG cooling water system provides the required cooling for all EDG operation, the proper lineup is implicitly assured every 31 days by satisfactory operation of the required EDG load run. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do l not impact the requirement to maintain the EDG in an Operable i status. | |||
l TECHNICAL CHANGES LESS RESTRICTIVE "Speci fi c" L.1 CTS SR 4.8.1.2. Surveillance Requirements for EDG and offsite sources while shutdown, includes the requirement to perform the | |||
! CTS equivalent of ITS SR 3.8.1.18 (simultaneous EDG start test). | |||
i ITS SR 3.8.2.1 does not require this test to be applicable for determining Operability when shutdown. The change is acceptable because simultaneous start of all four EDGs is not needed because only 2 EDG are required to be Operable. Therefore. this exception has minimal impact on safety. | |||
Furthermore. ITS SR 3.8.2.1, Note. provides several exceptions to required demonstrations (although still retaining the applicability of the specific functional capability to be Operable) that are not provided in CTS SR 4.8.1.2. The reason for the Note is to preclude requiring the Operable EDG from being i paralleled with the offsite power network or otherwise rendered l | |||
inoperable during the performance of SRs. and to preclude de energizing a required 4160 V ESF bus or disconnecting a required offsite circuit during performance of SRs. With limited AC sources available, a sinole event could compromise both the required circuit and the EDGs. The Fermi 2 EDG design is such that on any EDG surveillance test start the EDG is rendered - | |||
inoperable. Therefore, the exception list includes all ITS SRs involving an EDG start (i.e.. ITS SRs 3.8.1.2. 3.8.1.7. and - | |||
3.8.1.11 are included, in addition to those proposed in the l ._ NUREG). This change is consistent with NUREG-1433. k FERMI UNIT 2 5 REVISION 7 06/18/99l l | |||
L | |||
? | |||
l | |||
@l Diesel Fuel Oil and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS | |||
@l3.8.3 Diesel Fuel Oil and Starting Air 3.8.3 The stored diesel fuel oil and starting air subsystem shall | |||
- @ l LC0 be within limits for each required emergency diesel i generator (EDG). | |||
i APPLICABILITY: When associated EDG is required to be OPERABLE. ' | |||
ACTIONS- | |||
..................................... NOTE---- - -- - - -- - - -- -- - - | |||
Separate Condition entry is allowed for each EDG. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore fuel oil 48 hours EDGs with fuel oil level to within level < 35.280 gal and limits. i | |||
> 30.240 gal.in l storage tank. i- | |||
@i B. One or more required B.1 Restore fuel oil 7 days EDGs with stored fuel -total particulates to oil total particulates within limit. | |||
not within limit. | |||
4 | |||
#l C. One or more required C.1 Restore stored fuel 30 days EDGs with new fuel oil oil properties to properties not within within limits. | |||
limits. | |||
(continued) u-l FERMI - UNIT 2 3.8 13 Revision 7 06/18/99 | |||
ngl Diesel Fuel Oil and Starting Air W 3.8.3 | |||
-ACTIONS (continued) | |||
C0lOITION REQUIRED ACTION COMPLETION TIME l | |||
l gj~D. Required Action and D.1 Declare associated Immediately 1 associated Completion -EDG inoperable. 1 Time not met. | |||
l .QB y | |||
L One or more required EDGs with diesel fuel Mj -011. or starting air | |||
. v.;/ subsystem not within | |||
! limits for reasons other than I .hj Condition A, B, or C. | |||
SU'RVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY I | |||
i SR' 3.8.3.1 Verify each required EDG fuel oil storage 31 days tank contains = 35,280 gal of fuel. | |||
l SR 3.8.3.2 Ver4fy each required EDG fuel oil In accordance properties of new and stored fuel oil are with the tested in accordance with, and maintained ' Emergency within the limits of, the Emergency Diesel Diesel Generator Fuel Oil Testing Program. Generator Fuel ! | |||
011 Testing i l | |||
Program 1 | |||
l (continued) 1~ | |||
1 J | |||
,l FERMI UNIT 2- 3.8 14 Revision 7 06/18/99 l | |||
L | |||
. 1 | |||
.hl' Diesel Fuel Oil and Starting Air 3.8.3 ' | |||
SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY kj SR 3.8.3.3 - Verify each required EDG air start receiver 31 days pressure is a 215 psig. | |||
hj SR 3.8.3.4 Check for and remove accumulated water from each required EDG fuel oil storage tank. | |||
31 days l | |||
l l | |||
l I | |||
i l | |||
i l | |||
i I | |||
l FERMI UNIT 2 3.8 15 Revision 7 06/18/99 i | |||
l Diesel Fuel Oil and Starting Air B 3.8.3 4 | |||
8 3.8 ELECTRICAL POWER SYSTEMS l B 3.8.3 Diesel Fuel 011 and Starting Air BASES | |||
' BACKGROUND Each emergency diesel generator (EDG) is provided with a storage tank having a fuel oil capacity sufficient to operate that EDG for a period of 7 days while the EDG is supplying maximum continuous load discussed in UFSAR, Section 9.5.4 (Ref. 1). This onsite fuel oil ca)acity is l sufficient to operate the EDGs for longer than t1e time to replenish the onsite supply from outside sources. | |||
1 Fuel oil is transferred from storage tank to day tank by either of two transfer pumps associated with each storage tank. Redundancy of pumps and piping precludes the failure I of one pump, or the rupture of any pipe valve, or tank to result in the loss of more than one EDG. | |||
For proper operation of the standby EDGs, it is necessary to ensure the proper quality of the fuel oil. Regulatory Guide 1.137 (Ref. 2) addresses the recommended fuel oil i practices as supplemented by ANSI N195 (Ref. 3). The fuel oil properties governed by these SRs are the water and sediment content, the kinematic viscosity, specific gravity (or API gravity), and impurity level. | |||
Each EDG has an air start system with adequate capacity for five successive start attempts on the EDG without recharging the air start receiver (s). | |||
APPLICABLE The initial conditions of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses in UFSAR. Chapter 6 (Ref. 4), and Chapter 15 (Ref. 5), assume Engineered Safety Feature (ESF) systems are OPERABLE. The EDGs are designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ESF systems so that fuel Reactor Coolant System, and containment design limits are not exceeded. These limits are discussed in more detail in the Bases for Section 3.2, Power Distribution Limits: Section 3.4, Reactor Coolant System (RCS): and Section 3.6 Containment Systems. | |||
jFERMI-UNIT 2 B 3.8.3 - 1 Revision 7 06/18/99 | |||
/p Diesel Fuel Oil and Starting Air B 3.8.3 BASES | |||
' APPLICABLE SAFETY ANALYSES (continued) hl . | |||
Since diesel fuel oil and starting air subsystem support the operation of the standby AC power sources, they satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). | |||
LC0 Stored diesel fuel oil is required to have sufficient supply for 7 days of full load operation. It is also required to gl meet specific standards for quality. This requirement, in con,iunction with an ability to obtain replacement supplies within 7 days, supports the availability of EDGs required to shut down the reactor and to maintain it in a safe condition for an anticipated operational occurrence (A00) or a postulated DBA with loss of offsite power. EDG day tank fuel oil requirements, as well as transfer capability from the storage tank to the day tank, are addressed in LC0 3.8.1. "AC Sources-0perating." and LC0 3.8.2. "AC Sources -Shutdown. " | |||
The starting air system is required to have a minimum capacity for five successive EDG start attempts without recharging the air start receivers. | |||
APPLICABILITY The AC sources (LC0 3.8.1 and LC0 3.8.2) are required to ensure the availability of the required power to shut down the reactor and maintain it in a safe shutdown condition I after an A00 or a postulated DBA. Because stored diesel ' | |||
fuel oil and starting air subsystem support LC0 3.8.1 and LC0 3.8.2. stored diesel fuel oil and starting air are required to be within limits when the associated EDG is required to be OPERABLE. | |||
ACTIONS The ACTIONS Table is modified by a Note indicating that separate Condition entry is allowed for each EDG. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable EDG subsystem. Complying with the Required Actions for one inoperable EDG subsystem may allow for continued operation, and subsequent inoperable EDG subsystem (s) governed by j separate Condition entry and application of associated < | |||
Required Actions. | |||
1 l FERMI - UNIT 2 B 3.8.3 - 2 Revision 7, 06/18/99 I i | |||
jl Diesel Fuel Oil and Starting Air B 3.8.3 BASES ACTIONS (continued) | |||
L1 In this Condition. the 7 day fuel oil supply for a required EDG is not available. However, the Condition is restricted to fuel oil level reductions that maintain at least a 6 day supply. These. circumstances may be caused by events such as: | |||
: a. Full load operation required for an inadverte.nt start while at minimum required level: or | |||
: b. Feed and bleed operations that may be necessitated by increasing particulate levels or any number of other oil quality degradations. | |||
This restriction allows sufficient time for obtaining the requisite replacement volume and performing the analyses required prior to addition of the fuel oil to the tank. A period of 48 hours.is considered sufficient to complete restoration of the required level prior to declaring the EDG inoperable. This period is acceptable based on the remaining capacity (> 6 days), the fact that procedures will be initiated to obtain replenishment, and the low probability of an event during this brief period. | |||
@ u This Condition is entered as a result of a failure to meet the acceptance criterion for particulates in one or more required EDG storage tanks. Normally, trending of particulate levels allows sufficient time to correct high particulate levels prior to reaching the limit of acceptability. Poor sample procedures (bottom sampling), | |||
contaminated sampling equipment, and errors in laboratory analysis can produce failures that do not follow a trend. | |||
Since the presence of particulates does not mean failure of the fuel oil to burn properly in the diesel engine, since particulate concentration is unlikely to change significantly between Surveillance Frequency intervals, and since proper engine performance has been recently demonstrated (within 31 days).-it is prudent to allow a brief period prior to declaring the associated EDG inoperable. The 7' day Completion Time allows for further evaluation. resampling, and re analysis of the EDG fuel oil. | |||
l ; FERMI f UNIT 2? B 3.8.3 3 Revision 7 06/18/99 | |||
J | |||
@ Diesel Fuel Oil and Starting Air B 3.8.3 BASES ACTIONS (continued) | |||
@l u | |||
With the new fuel oil pro)erties defined in the Bases for | |||
@l SR 3.8.3.2 for new fuel t1at has already been added to a required EDG storage tank not within the required limits, a period of 30 days from the time of obtaining new fuel oil sample results is allowed for restoring the stored fuel oil properties. This period provides sufficient time to test the stored fuel oil to determine that the new fuel oil, when mixed with previously stored fuel oil, remains acceptable, or to restore the stored fuel oil properties. This restoration may involve feed and bleed procedures, filtering, or combination of these procedures. Even if a EDG start and load was required during this time interval and the fuel oil 3roperties were outside limits, there is high likelihood tlat the EDG would still be capable of performing its intended function. | |||
I u With a Required Action and associated Completion Time not (Aj met, or the stored diesel fuel oil or starting air subsystem not within limits for reasons other than addressed by "l Conditions A through C, the associated EDG may be incapable of performing its intended function and must be immediately declared inoperable. | |||
SURVEILLANCE SR 3.8.3.1 REQUIREMEtHS This SR provides verification that there is an adequate inventory of fuel oil in the storage tanks of each required EDG to support each EDG's operation for 7 days at full load. | |||
The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. | |||
The 31 day Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and unit operators would be aware of any large uses of fuel oil during this period. | |||
u l FERMI UNIT 2 B 3.8.3 -4 Revision 7 06/18/99 | |||
I i | |||
Ogj Diesel Fuel Oil and Starting Air B 3.8.3 l | |||
EASES SURVEILLANCE REQUIREMENTS (continued) gl SR 3.8.3.2 The tests of fuel oil prior to addition to the storage tank nc? a means of determining whether new fuel oil is of the appropriate grade and has not been contaminated with substances that would have an immediate detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the fuel oil may be added to the storage tanks without concern for contaminating the l entire volume of fuel oil in the storage tanks. These tests are to be conducted prior to adding the new fuel to the storage tank (s), but in no case is the time between sampling (and associated results) of new fuel and addition of new fuel oil to the storage tank to exceed 31 days. The tests, limits, and applicable ASTM Standards for the new fuel oil tests listed in the Emergency Diesel Generator Fuel Oil Testing Program of Specification 5.5 are as follows: | |||
: a. Sample the new fuel oil in accordance with ASTM D4057-88 (Ref. 6): | |||
h b. Verify that the sample has an API Gravity of within 0.3 degrees at 60*F or a specific gravity of within 0.0016 at 60/60'F. when compared to the suppliers certificate, , | |||
or an absolute specific gravity at 60/60*F of a 0.83 and s 0.89 or an API gravity at 60*F of a 27" and s 39 . Also, verify in accordance with the tests t | |||
specified in ASTM D975 91 (Ref. 6) a kinematic viscosity at 40*C of a 1.9 centistokes and s 4.1 centistokes, and a flash point of a 125*F: and | |||
: c. Verify that the new fuel oil has a clear and bright appearance with proper color when tested in accordance with ASTM D4176 86 (Ref. 6). | |||
Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the LC0 since the fuel oil is not added to the storage tanks. ' | |||
Following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in Table 1 of ASTM 0975 91 (Ref. 6) are met for new fuel oil when tested in accordance with ASTM D975 91 (Ref. 6), except that the analysis for sulfur may be performed in accordance < | |||
with ASTM D1552-90 (Ref. 6) or ASTM D2622 87 (Ref. 6), | |||
s. | |||
l FERMI-UNIT 2 83.8.3-5 Revision 7. 06/18/99 i | |||
hl Diesel Fuel Oil and Starting Air B 3.8.3 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
These additional analyses are required by Specification 5.5.9. " Emergency Diesel Generator Fuel Oil Testing Program." to be 3erformed within 31 days following sampling and addition. T11s 31 days is intended to assure: 1) that the sample taken is not more than 31 days old at the time of adding the fuel oil to the storage tank, and 2) that the results of a new fuel oil sample (sample obtained arior to addition but not more than 31 days prior to) are o)tained within 31 days after addition. The 31 day period is acce) table because the fuel oil properties of interest. even if t1ey were not within stated limits, would not have an immediate effect on EDG operation. This Surveillance ensures the availability of high quality fuel oil for the required EDGs. | |||
Fuel oil degradation during long term storage shows up as an increase in particulate, mostly due to oxidation. The presence of particulate does not mean that the fuel oil will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment, however, which can cause engine failure. | |||
Particulate concentrations should be determined in accordance with ASTN D2276 88 (Ref. 6). Method A. This method involves a gravimetric determination of total particulate concentration in the fuel oil and has a limit of 10 mg/1. It is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing. | |||
The Frequency of this test takes into consideration fuel oil j degradation trends that indicate that particulate concentration is unlikely to change significantly between Frequency intervals. | |||
l SR 3.8.3.3 This Surveillance ensures that, without the aid of the refill compressor, sufficient air start capacity for each EDG is available. The system design requirements provide for a minimum of five engine start cycles without recharging. The pressure specified in this SR is intended to reflect the lowest value at which the five starts can be accomplished. | |||
The 31 day F.ecuency takes into account the capacity, capability, recundancy, and diversity of the AC sources and l FERMI . UNIT 2 B 3.8.3 - 6 Revision 7 06/18/99 | |||
1 | |||
'hi Diesel Fuel Oil and Starting Air B 3.8.3 BASES SURVEILLANCE REQUIREMENTS (continued) other indications available in the control room, including alarms, to alert the operator to below normal air start pressure, SR 3.8.3.4 hl Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive. Removal of water from the required EDG fuel storage tanks once every 31 days eliminates the necessary environment for bacterial survival. | |||
This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during EDG operation. Water may come from any of several sources, including condensation, ground water. rain water, contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily represent failure of this SR. provided the accumulated water is removed during performance of the Surveillance. | |||
i REFERENCES 1. UFSAR, Section 9.5.4. ; | |||
: 2. Regulatory Guide 1.137. | |||
: 3. ANSI N195. 1976. | |||
: 4. UFSAR Chapter 6. | |||
: 5. UFSAR Chapter 15. | |||
: 6. ASTM Standards: D4057 88: D975 91: D4176 86: D1552 90: | |||
D2622 87: and D2276 88. | |||
l l | |||
w j l FERMI UNIT 2 B 3.8.3 - 7 Revision 7. 06/18/99 | |||
l 3/4.8 ELECTRICAL POWER SYSTEMS S PE4FicknorJ S.9 3 l 3/4.8.1 A.C. SOURCES [b505c4SgdhtnNoy) 8.8. / ) l l | |||
A.C. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: | |||
a Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, y and M3' * ! bg Two separate and independent onsite A.C. electrical power sources, Division I and Division II, each consisting of two emergency ' | |||
diesel generators, each diesel generator with: | |||
: 1. A separate day fuel tank containing a minimum of 210 gallons L of fuel, gR 3.g ~3,1 2. A separate fuel stora e system containing a minimum of 35,280 gallons of fue , and {*l AM. LCO 3,3,3 | |||
: 3. A separate tuei transter pump Ag); cab l lip | |||
,ffitCABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. St M S CTION: | |||
With one or both offsite circuits of the above required A.C. | |||
electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTOOWN within the next 24 hours; demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1. within one hour and at least once per 8 hours thereafter and, g J. With one or both diesel generators in one of the above required g.g onsite A.C. electrical power divisions iaoperable; J.8.1 1. Demonstrate the OPERABILITY of the remaining A.C. sources by ' | |||
performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours thereafter, and if the diesel generator (s) became inoperable due to any cause other l than an inoperable support system, an independently testable l component, or preplanned preventive maintenance or testing, by performing Surveillance Requirement 4.8.1.1.2.a.4 for one diesel generator at a time within 24 hours, unless the absence of any potential common mode failure for the remaining diesel generators is deterrined, and , | |||
i FERMI UNIT 2 3/4 8-1 Amendment No. SJ,119 PAGE / OF 05 gev 7 | |||
l l | |||
f SPECAPICM70h.l 3 S'.3 ELECTRicAt POVCR SYSTEMS SURVEILLANCE REOUTREMENTS F4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability. | |||
4.8.1.1.2 Each of the above required diesel generators shall be demonstrated OPERABLE: l Sti . a. | |||
At least once per 31 days hnMTAGGERJB' TEST SAffE]5y: | |||
Squi$icahn l 3.2 1 1. | |||
Verifying trie fuel Tever in the day fuei tank.. . . * * . , | |||
ySt : | |||
: 2. Verifying the fuel level in the fuel storage tank.ll'* | |||
"3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank. ' | |||
: 4. Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in less than or equal to 10 seconds.* The generator voltage and frequency shall be 4160 a 420 volts and 60 a 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started for this test by using one of the following signals: | |||
gel | |||
) a) Hanua1. | |||
Qejf; cob. r. 5' b) Simulated less-of-offsite power by itself. | |||
c) Simulated loss-of-offsite power in conjunction with an 8 T-l ESF actuation test signal. | |||
d) An ESF actuation test signal by itself. | |||
: 5. Verifying the diesel generator is synchronized, loaded to greater than or equal to an indicated 2500 2600 kW in accordance with the manufacturer's recommendations, and operates with this load for at least 60 minutes. | |||
6. | |||
Verifying the diesel generator is aligned to provide standby power to the associated emergency busses. | |||
: 7. Verifying the pressure in all diesel generator air start 6 4 3. 7, 3,.3 receivers to be greater than or equal to 215 psig. l Fall diesel generator starts for the purpose of this Surveillance Requirement g" ( may As arreceded by an engine prelube period. The diesel generatar start (10 sec) from ambient ' conditions shall be performed at least KStahn- once .per 184 days in these surveillance tests. All other engine star.ts for 3'g* g the purpose of this surveillance testing may be preceded by other warmup procedures reconrnended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized. | |||
h FERMI - UNIT 2 3/4 8-3 | |||
~ | |||
Amendment No. JJ,107 s | |||
PAGE c2 0F 05 g,g 7 i | |||
9 ecd Pt c h'rtbrd 3. 7 3 j(so .% Spec &coHm 3.fr. I.) | |||
ELEETRICAL p0WER SYSTEMS | |||
((bO b6 6 /6cibC4 b feb SURVEf tl ANCE pE0VIREMENTS (Continued) i | |||
: b. By removing accumulated water: | |||
seL From the day tank at least once per 31 days and after each pecificab J,3.l\/ 1. occasion when the diesel is operated for greater than I hour, and I | |||
6/?. 3 2,,3,[ 2. From the storage tank at least once per 31 days. | |||
I D E 3 g,,, c. By sampling new fuel oil in accordance with ASTM 04057 88 prior to addition to the storage tanks and: | |||
l g*g , 1. By verifying in accordance with the tests specified in ASTM 0975-91 prior to addition to the storage tanks that the | |||
: sample has: | |||
4 sk 5Fificalia a) An API Gravity of within 0.3 degrees at 60'F or a specific gravity of within 0.0016 at 60/60'F, when f.F compared to the supplier's certificate or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity at 60'F of greater than or equal to 27 degrees but less than or equal to 39 degrees. | |||
b) A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by | |||
, comparison with the supplier's certification. | |||
c) , A flash point equal to or greater than 125'F, and d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176 86. | |||
: 2. By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975 91 are met when tested in accordance with ASTM D975-91. | |||
: d. At least once every 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276 88, and verifying that total particulate contamination is less than 10 mg/ liter when Wckgd in accordance with ASTM D2276 88, Method A. | |||
(e. At least once per 18 months by: | |||
l N 1. Subjecting the diesel to an inspection in accordance with Qec.i(icahd . | |||
procedures prepared in conjunction with its manufacturer's reconrnendations for this class of standby service. | |||
FEP.MI - UNIT 2 3/484 Amenoment No. # , 95 i | |||
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PAGE_ 3 0F 05 Re 7 7 | |||
e e | |||
' t.; | |||
SPEGlF iCJtTlotJ 3.2.3 fAko Su Spalficalin 3.g.\) | |||
ELECTRicAt POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) e M f. At least once per 10 years or after any modifications whien could - | |||
affect diesel generator interdependence by starting all four I S pu.* scc,f im diesel generators simul'taneously, during shutdown, and verifying 3* g* g that all four diesel generators accelerate to at least 900 rpm in 1ess than or equal to 10 seconds. ; | |||
Ai 17.; .;.;. ;;r " - ;.r; ty: l 4./ | |||
Draining a fuel oil stora tank, removing e accumula sediment and c aning the tankf :. ; - adh _ | |||
S O(. 2. Performing a pressure test of those portions of the diesel Speciscafisw fuel oil system designed to Section 111. subsection ND of 3, g, g the ASME Code in accordance with ASME Code Section 11 Article IWD.5000. | |||
j (4.8.2.3.3 Reeerts - Not Used I | |||
l l | |||
j l | |||
1 FERMI - UNIT 2 3/4 a.7 | |||
,, Amendmnent No.107 L-PAGE OF 05 #ev 7 , | |||
1 | |||
1 DISCUSSION OF CHANGES ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR lh ADMINISTRATIVE A.1 In the conversion of the Fermi 2 current Technical Specifications (CTS) to the proposed plant specific Improved Technical ! | |||
Specifications (ITS), certain wording preferences or conventions l are adopted which do not result in technical changes (either l actual or interpretational). Editorial changes, reformatting, and l revised numbering are adopted to make the ITS consistent with the I Boiling Water Reactor (BWR) Standard Technical Specifications ! | |||
NUREG 1433, Rev. 1. | |||
A.2 CTS 4.8.1.1.2.c details diesel fuel oil test requirements. These details are addressed in the ITS Administrative Controls Programs. | |||
Section 5.5, and required by ITS SR 3.8.3.2. This is an administrative presentation issue only. The details of the CTS lh j conversion to these ITS Program requirements are addressed in Section 5.0. j TECHNICAL CHANGES MORE RESTRICTIVE None TECHNICAL CHANGES LESS RESTRICTIVE | |||
" Generic" l LA.1 CTS 4.8.1.1.2.g.1 requires a 10 year cleaning of the EDG fuel oil storage tank, which reflects a preventative maintenance type of SR. Failure to perform this SR, does not necessarily result in an inoperable EDG. Preventative maintenance SRs generally have been l relocated from the TS and allowed to be under licensee control, as they are not necessary for ensuring Operability. Relocating this surveillance maintains consistency with NUREG 1433. The required cleaning of the storage tanks is relocated to the Technical Requirements Manual-(TRM). This cleaning can be adequately defined and controlled in the TRM where revisions are controlled I by the provisions of 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the requirement for EDG Operability remains in the Technical Specifications. | |||
FERHI - UNIT 2 1 REVISION 7 06/18/99l l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l[ | |||
TECHNICAL CHANGES LESS RESTRICTIVE "Speci fic" L.1 CTS LCOs 3.8.1.1 and 3.8.1.2 include requirements associated with diesel fuel oil storage. These requirements are moved to a new Specification ITS 3.8.3, Diesel Fuel Oil and Starting Air. The Applicability of this new LC0 is "when associated EDG is required l@ | |||
to be OPERABLE" which envelops the Applicabilities for the requirements moved into the new Specification. lh ITS LC0 3.8.3, Diesel Fuel Oil and Starting Air, includes the following new less restrictive allowances: Condition A (less than l@ | |||
7 days but more than 6 days of EDG fuel available): Condition B l (fuel oil particulates not within limits): Condition C (new fuel oil properties not within limits): Condition D (Actions or g l Completion Time for other Required Actions not met). These new Conditions are less restrictive because they provide time to restore a Condition that, under the CTS equivalent requirements, would result in the EDG being immediately declared inoperable. | |||
This change is acceptable because each of these parameters, while supporting EDG Operability, contains substantial margin before reaching a condition that would prevent the EDG from performing its safety function. Therefore, the limited levels of degradation permitted by these new conditions justify some allowance for restoration. During the newly allowed restoration periods for these parameters, the EDG is still capable of performing its intended function. | |||
Specifically. Action A allows 48 hours to restore fuel oil level in the storage tanks prior to declaring the EDG inoperable provided fuel oil level is sufficient for 6 days of operation at the continuous rated load. Action B allows 7 days to restore fuel lg oil total particulates to within limits prior to declaring the EDG inoperable, because the most likely cause of high particulates is poor sampling and particulates for limited durations will not prevent EDG operation. Action C allows 30 days to restore other j new fuel oil properties to within limits because these tests are ( | |||
t intended to measure long term oil stability and are not indicative of conditions that would prevent EDG operation in the short run. | |||
Action D is provided to declare the EDG inoperable if previous Actions are not met. Therefore, these changes have no adverse N | |||
impact on safety. | |||
; FERMI UNIT 2 2 REVISION 7 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.3 DIESEL FUEL 0IL AND STARTING AIR lh L.2 CTS SR 4.8.1.1.2 a requires the monthly verification of EDG fuel ; | |||
storage tank level be performed "on a STAGGERED TEST BASIS." The ) | |||
intent of this requirement for staggered testing was to maintain 4 jtonthesametestscheduleasthemonthlyEDGrun. Note that in I the DOCS for ITS 3.8.1. the staggered test basis for the EDG start y and load was deleted. Therefore, consistent with that change in i frequency, the EDG fuel oil level verification staggered testing Q requirements have been deleted. The system design continues to T provide fuel oil level alarms to alert the operator to any abnormal losses of fuel oil between EDG surveillance runs. | |||
RELOCATED SPECIFICATIONS None TECHNICAL SPECIFICATION BASES Bases for this Specification have been added that reflect the format and i applicable content of ITS 3.8.3 consistent with the BWR STS, NUREG 1433. I Rev. 1. | |||
l FERMI UNIT 2 3 REVISION 7 06/18/99l l | |||
) | |||
r Diesel Fuel Oil (_Ec: 0;QandStartingAir-3.8.3 lh 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel 011@stgrT[1) and Starting Air | |||
[ cts) | |||
LCO 3.8.3 The stored diesel fuel oil .ubr1rTT) ar.d starting air subsystem shall be within limits for each required diesel generator . | |||
f - | |||
[ | |||
APPLICABILITY: When associated'bG is required to be OPERABLE. l ACTIONS | |||
- - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - ------- | |||
Separate Condition entry is allowed for each%G. | |||
i CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.I Restore fuel oil 48 hours fuel oil level level to within N)28 J : "^ limits. | |||
> M, r galgaland in orage tank, eguidd E f | |||
. One o moreDGswth( 8. Restore lube oil 4 ours lube o inventory inventor to within i i < 40Er al and limits. | |||
>M 1. g | |||
~ | |||
( One or mo're$6s with .I Restore fuel oil 7 days I l l stored fuel oil total 6 total particulates to particulates not within limit, within limit. V (continued) i BWR/4-STS. 3.8-21 R;v I, 04/07/95 | |||
./ | |||
Rev7 | |||
) | |||
i DieselFuelOilf andStartingAir{h 3.8.3 ACTIONS (continued) | |||
<as) | |||
CONDITION REQUIRED ACTION COMPLETION TIME | |||
. One or more 1 Restore stored fuel 30 days new fuel oil ( oli properties to properties not within within limits. L limits. | |||
E. One or more,0Gs th E.1 Res re starting air 48 ours starting air eiver iver pressure to pressure < [ ] psig [225) psig. # | |||
and 2 [125) sig. | |||
Required Action and associated Completion D 1 Declare associated inoperable. | |||
Immediately g Time not met. V E | |||
One or more ,DGs with Uvguired E, diesel fuel oil, bda- . /h f.4 U | |||
=rdi, or starting air subsystem not within limits for reasons other than n tion A, Cy)lfy 4 SWR /4-STS- 3.8-22 Rev 1, 04/07/95-Rev 7 | |||
Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REDUIREMENTS SURVEILLANCE FREQUENCY TlakVLJG$D Verifyeace_[fueloilstoragetankcontains SR 3.8.3.1 31 days (J. 7.l.l. b.2 ) | |||
2 't ^^^' gal of fuel. | |||
.t.p.2.a.1) 9e@ e.r. i.2.t.t> | |||
SR .8.3.2 Ve ify lube oil inve ory is 2 f50GJ g . 31 days g | |||
SR 3.8.3 Verify | |||
@ r*[ 6G3 4 3.l.i.1.c.34) 1 oil properties of new and In accordanc l stored fuel oil are tested in accordance with the Diesel | |||
+ Fuel Oil h { | |||
with,andmaintainedwithinthelimitso[f, the leseltluel Oil Testing Pro ram. Testing Program E mw w c yl -- ** ' | |||
3.8.3. | |||
etaired C ) | |||
SR rify eac ir starr receiver pressure 31 days (Q,g.l.l.2,4.7) dib . "9 SR 3.8.3 Check for and remove accumulated water from 431Adays each4 fuel o_11 storage _ tank. | |||
f(quina E$G) f.g,f./,2,b,2.) | |||
SR 3.8.3.6 For ch fuel oil storage t k: years | |||
: s. D in the fuel oil; | |||
\cl b. Remo the sediment; and | |||
: c. Clean t tank. | |||
^ | |||
BWR/4-SYS- 3.8-23 Rev 1, 04/07/95 | |||
./ | |||
Rd 7 | |||
) | |||
Diesel Fuel 011 { Q and Starting Air B 3.8.3 p& | |||
B 3.8 ELECTRICAL POWER SYSTEMS g A/0T #4/kED *. | |||
B 3.8.3 Diesel Fuel 011Q,vbe-UTTiand Starting Air "OG ~* 06 g BASES (eemp _ | |||
BACKGROUND Each Mtesel erator (DG) is provided with a storage tank. | |||
having a fue oil capacity sufficient to operate that DG f -- | |||
I a_ period of 7 days while the DG is supplying maximum can6nuous ! | |||
OPa @u;; FSAR,e ::::rt ---id::t Section 19 (l.%",}-load-d-- | |||
1 . u" -- - .d (Ref.u-) ' discussed | |||
'- ' "- -in' '- | |||
;;;e:tg .f ; n. ... ;;;;; ;; =; ;7;- | |||
miletier This onsite fuel oil capacity is sufficient to operate the DGs for longer than the time to replenish the onsite supply from outside sources. . | |||
l Fuel oil is transferred from storage tank to day tank by either of two transfer pumps associated with each storage tank. Redundancy of pumps and piping precludes the failure of one pump, or the rupture of any pipe, valve, or tank to result in the loss of more than one DG. -All at:id: t=E:, | |||
h ;-+ ad pipir; r: M st=d e=de;-e: d. | |||
For proper operation of the standby DGs, it is necessary to ensure the proper quality of the fuel oil. Regulatory Guide 1.137 (Ref. 2) addresses the recomended fuel oil practices as supplemented by ANSI N195 (Ref. 3). The fuel oil properties governed by these SRs are the water and sediment content, the kinematic viscosity, specific gravity (orAPIgravity),andimpuritylevel. | |||
I The DG lubr ation system is designed to provide surf lubricati to permit proper opefation of its associate G 3 | |||
under al loading conditions, he system is required circul e the lube oil to th diesel engine working rfaces and t remove excess heat . ersted by friction dur g oper tion. Each engine-ci sump contains-an inve cry ca ble of supporting a nimum of !F} days of o ration. | |||
e onsite storage in dition to the engine o sump is ufficient to ensure 7 ays' continuous opera on.y This supply is sufficient o allow the operator t replenish lube i (11 from outside so es. j - | |||
Each DG has an air start system with adequate capacity for five successive start attempts on the DG without recharging the air start receiver (s). | |||
(continued) | |||
BWR/4-US B 3.8-41 -Rev 1, M/0W Rev 7 | |||
Diesel Fuel 011Cl.ube-t!TT~) and Starting Air jg> | |||
B 3.8.3 0' BASES (continued) | |||
' -APPLICABLE The initial conditio of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses i , Chapter [6k (Ref. 4), and Chapter [15A(Ref.5 ssume Engine)ered Safety Feature (ESF) systems are OPERABLE. The DGs are designed to provide sufficient capacity, capability, redundancy and reliability to ensure the availability of necessary powe,r to ESF . systems so that fuel, Reactor Coolant System, and containment design limits are not exceeded. These limits are discussed in more detail in the Bases for Section 3.2, Power Distribution Limits; Section 3.4, Reactor Coolant System (RCS); and Section 3.6, Containment Systems.. | |||
Since diesel fuel oilf.3ebe m.1 and starting air subsystem support the operation of the standby AC power sources, they l@ | |||
p'7 satisfy Criterion 3 of '" ""I .";;;cy OutM S Q q CFR50. % % @ % D.J LC0 Stored diesel fuel oil is required to have sufficient supply for 7 days of full load operation. It is also required to meet specific standards for quality. .^f it M i!!;. , | |||
-suff4cient-1;h eil-supply-must-h :=9 tM- +a | |||
-->-- tS ~ | |||
capab Fity +a aaan+= =* fem-load-foe 4-days. This requirement, in con. junction with an ability to obtain replacement supplies within 7 days, supports the availability of DGs required to shut down the reactor and to maintain it in a safe condition for an anticipated operational occurrence (A00) or a postulated DBA with loss of offsite power. DG day tank fuel oil requ'eements, as well as transfer capability from the storage tank to the day tank, are addressed in LCO 3.8.1, "AC Sources-Operating," | |||
and LCO 3.8.2, 'AC Sources-Shutdown." | |||
The starting air system is required to have a minimum capacity for five successive DG start attempts without recharging the air start receivers. | |||
APPLICABILITY The AC sources (LCD 3.8.1 and LCO 3.8.2) are required to ensure the availability of the required power to shut down the reactor and maintain it .in a safe shutdown condition after an A00 or a fuel cit .___ ... postulated DBA. air a and starting Because stored subsystem diesel support 8 \ | |||
LCO 3.8.T and LCD 3.8.2, stored diesel fuel oil,;4ebe-wit / I (continued) | |||
-BWR/4-STS- 8 3.8-42 Rev-Ir-04/07/g5-Reu7 t | |||
1 - | |||
?. | |||
Diesel Fuel 011 6 and Starting Air Vgp B 3.8.3 BASES APPLICABILITY and starting air are required to be within limits when the (continued) associated DG is required to be OPERABLE. | |||
ACTIONS The ACTIONS Table is modified by a Note indicating that separate Condition entry is allowed for each DG. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable DG subsystem. Complying with the Required Actions for one inoperable DG subsystem may allow for continued operation, and subsequent inoperable DG subsystem (s) governed by separate Condition entry and application of associated Required Actions. | |||
L1 (~tyi! | |||
In this Condition, the 7 day fuel oil supply for a tG is not available. However, the Condition is restricted to fuel oil level reductions that maintain at least a 6 day supply. | |||
These circumstances may be caused by events such as: | |||
: a. Full load operation required for an inadvertent start while at minimum required level; or | |||
: b. Feed and bleed operations that may be necessitated by increasing particulate levels or any number of other oil quality degradations. | |||
This restriction allows sufficient time for obtaining the requisite replacement volume and performing the analyses required prior to addition of the fuel oil to the tank. A period of 48 hours is considered sufficient to complete i restoration of the required level prior to declaring the DG l inoperable. This period is acceptable based on the remaining capacity (> 6 days), the fact that procedures will be initiated to obtain replenishment, and the low ' | |||
probability of an event during this brief period, t | |||
'g Yi lobe oil inventor < Soe gal, sufficient lu oil to l supp 7 days of contin s DG operation at full ad condit s may not be avail e. However, the Condi n is j F | |||
(continued) | |||
BWR/4-ST& B 3.8-43 Ris I, 04/07/95 av 7 | |||
) | |||
. . . , . . . . .s .. .:.... . .: | |||
. Diesel Fu21011IM_and Starting Air l B 3.8.3 BASES ACTIONS P | |||
' L 1 (continued) ^ 1 restricted to lu (11volumereductionsth intain at least a 6 day ly. This restriction ws sufficient time for obt ing the requisite repipement volume. A Period of hours is considered s ff'icient to complete - | |||
restorat n of the required vol prior to declaring the 03 inoper le. This period is a eptable based on the | |||
, rama ing capacity fa that procedures (>will6 day , the low rate of usag e r plenishment, and the 1 initiated to obtain probabili_ty of an event durin. | |||
J is brief perio fd _ _ _ | |||
in ru. of vMvt (pd M | |||
.5 k aqt M ES This Cor.dition is entered as a result of allure to meet the acceptance criterion for particulate Normally, trending of particulate levels allows sufficient time to correct hig particulate levels prior to reaching the limit of acceptab 11ty. Poor sample procedures contaminated sampling equipment, and errors (bottom sampling), | |||
in laboratory analysis can produce failures that do not follow a trend. | |||
Since the presence of particulates does not mean failure 't 1 l | |||
the fuel oil to burn properly in the diesel engine, sirs ! | |||
particulate concentration is unlikely to change significantly between Surveillance Frequency intervals, and i i | |||
since proper engine perfonsknce has been recently ' | |||
demonstrated (within 31 days), it is prudent to allow a brief period prior to declaring the associated DG inoperable. The 7 day Completion Time allows for further evaluation resampling, and re-analysis of the DG fuel __ oil. | |||
.fg g[sa) }& ltaS ahlady k.a+1 addCd h" | |||
~ ' ~ | |||
Q fegwired EDG [u!A o*1 SWCofe &$ | |||
MMM With the new uel oil properties defined in the Bases for SR 3.8.3 ot within the required limits, a period of doW ni 9 M W fwd ~30 days 11 lowed for restoring the stored fuel oil p;l Sufk,(LWIb Properties. This period provides sufficient time'to test | |||
. the stored fuel oil to detrmine that the new fuel oil, when mixed with previously storea fuel oil, remains acceptable, or to restore the stored fuel oil properties. This ' | |||
restoration may involve feed and bleed procedures, filtering, or combination of these procedures. Even if a DG start and load was required during this time interval and (continued) | |||
SWR /4.5TS. B 3.8-44 Rev-Ir04/07f95-2d7 | |||
DieselFuelOilf:Eube.4n)andStartingAir j B 3.8.3 1 | |||
BASES ACTIONS ,23 (continued) l the fuel oil properties were outside limits, there is high likelihood that the DG would still be capable of performing its intended function. | |||
[Withstartinga capacity for elver pressure < [225] psi ficient l e successive DG start att oes not exist. H er, as long as the receiv ressure is | |||
> [1 sig, there is adequate ty for at least one s attempt, and the DG c considered OPERABLE while air receiver press s restored to the required 11 . | |||
A period of 48 h f.3 restoration s considered sufficient to c e required pressure prior to e | |||
ring the DG ino e. This period is acceptable ed on the rye ing air start capacity, the fac at most DG starts l 1re accomplished on the first att , and the low probability of an event durin is brief period ; | |||
l l | |||
With a Required Action and associated Completion Time not met, or the stored diesel fuel oilf"W = mor starting air subsystem not within limits for reasons other than [@ | |||
addressed by Conditions A through , the associated DG may be incapable of performing its inten e function and must be imediately declared inoperable. | |||
G l$ | |||
SURVEILLANCE SR 3.B.3.1 REQUIREMENT 4 This SR provides verification that there is an adequate inventory of fuel oil in the storage tan to support each DG's operation for 7 days at full load. The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. | |||
The 31 day Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are (continued) | |||
SWR /4-STS- B 3.8-45 Rev 1, 04/07/95-s | |||
&v7 | |||
_- o | |||
Diesel Fuel 011(~EtrbeJ and Starting Air T B 3.8.3 BASES | |||
' SURVEILLANCE SR 3.8.3.1 (continued) | |||
REQUIREMENTS provided and unit operators would be aware of any large uses of fuel oil during this period. | |||
SR 3.8.3.21 | |||
\ | |||
This Surveilla . ensures that sufficient lu icating oi | |||
. inventory i vailable to support at least days of full load oper on for each DG. The requirement is based o the DG manufacturer's s con on[500)- | |||
values for the i | |||
run t of the DG. Implicit in th SR is the requiremerit to rify the capability to trans r the lube oil from its p, s rage location to the DG, whe the DG lube oil sump does t hold adequate inventory f 7 days of full load (Q operation without the level aching the manufacturer's U | |||
recommended minimum level A 31 day Frequency is dequate to ensure that a ficient \ | |||
lobe oli supply is phsite, since DG starts and ntimearjr i | |||
< closely monitored tiy the plant staff- - | |||
6 I SR 3.B.3 o$ [w) Dil ffief-{0 addili-g & ,5/gy a ge. M/t l@ | |||
s | |||
* The tests ii;t:d 5:h e are a means of determining whether new fuel oil is of the appropriate grade and has not been contaminated with substances that would have an immediate/ | |||
detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the fuel oil Mh d may be added to the storage tanks without concern for ! | |||
os,socW N contaminating the entire voltane of fuel oil in the storage i tanks. These tests are to be conducted prior to adding the l new fuel dgm jM , | |||
betweengothestoragetank(s),butinnocaseisthetime | |||
..ceipbof new fuel ancb::-de: ting t% tests- to exceed 31 days. The tests, limits, and applicable ASTM hpfb6$ M Standardsfareasfollows: | |||
.fo .ga nco fue,\dOtsbskd a. Sample the new fuel oil in accordance with ASTP - | |||
Rd b'ij D4057-pa)(Ref.6); | |||
4 /A)SER7 Tdsb)hWom p( b. Verif * | |||
@yjirigr} | |||
accordance with (Ref. 6)fthat the the~testkecifica sample hasdan absonn inemarg | |||
$pec}Mcdon 6.6 spectu e gravity at 60/60'F of 2 0.83 and s 0.89 or an API gravity at 60*F of 2 27' and 5 39'3fa kinematic | |||
[. | |||
C Also, | |||
- vcM[& ,J(continued) g-D ~ | |||
4WR/4-STS- B 3.8-46 -Rev-1,-04/07/95- | |||
@7 j; j e , | |||
: '.V ,. | |||
'i ,, G : | |||
Diesel Fuel Oil and Starting Air l h B 3.8.3 INSERT B 3.8.3-1 an API Gravity of within 0.3 degrees at 60 F or a specific | |||
. gravity of within 0.0016 at 60/60"F, when compared to the suppliers certificate, or... | |||
..3 FERMI UNIT 2 Page B 3.8 46' (Insert) REVISION 7 06/18/99l | |||
DieselFuel011[ nd Start n l( | |||
BASES SURVEILLANCE SR 3.8.3 ' | |||
(continued) | |||
REQUIREMENTS I viscosity at 40'C of h 1.9 centistokes and 5 4.1 centistokes, and a flash point of 2 125'F; and | |||
: c. Verify that the new fuel oil has a clear and bright appearance with proper color when tested in accordance with ASTM D4176- g (Ref. 6). | |||
Failure to meet any of the above limits is cause for i rejecting the new fuel oil, but does not represent a failure ' | |||
g to meet the LC0 4sstu b since the fuel oil is not added to the storage tanks. | |||
P.4 a - | |||
_;,.;g,;,, | |||
the fue I:o:3 | |||
'1 ; ,,[11owing is analyzed to establish the thatinitial new fuel oli sample, the other l | |||
properties specified in Table 1 of ASTM D975 4W4 (Ref. 6) are met for new fuel oil when tested in accordance with ASTM j | |||
. D975 4mic (Ref. 6), except that the analysis for sulfur may ' | |||
be performed in accordance with ASTM D15524901. (Ref. 6) or | |||
'%EflT $ 3,q,3 7, ASTM D2622-197} (Ref. 6)./ The day period is acceptable because tne rues ou propertie o nterest, even if they | |||
" ~ | |||
were not within stated limits, would not have an immediate effect on DG operation. This Surveillance ensures the availability of high quality fuel oil for the Fuel oil degradation during long term storage shows up as an increase in particulate, mostly due to oxidation. The presence of particulate does not mean that the fuel oil will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment, however, which can cause engine failure. | |||
Particulate concentrations should be determined in accordancewithASTMD2276-4n)(Ref.6),MethodA. This method involves a gravimetric detemination of total particulate concentration in the fuel oil and has a limit of 10 mg/1. It is acceptable to obtain a field sample for subsequent laboratory test,ing in lieu of, field, testing. | |||
M n'",".O+ | |||
_2: .- ". I"_ 3"L.2 "+' | |||
u m""2": '"'. '"I '' ' I"C | |||
: ' ' i' '' ' 7 ' ~ | |||
The Frequency of this test takes into consideration fuel oil degradation trends that indicate that particulate (continued) | |||
BWR/4 !TS B 3.8-47 6 1, 01/07/95 (fev1 J | |||
I l | |||
l Diesel Fuel Oil and Starting Air @ | |||
B 3.8.3 INSERT 8 3.8.3 2 These adNional analyses are required by Specification 5.5.9. " Emergency Diesel Generator Fuel Oil Testing Program." . | |||
to be performed within 31 days following sampling and I addition. This 31 days is intended to assure: 1) that the sample taken is not more than 31 days old at the time of adding the fuel' oil to the storage tank. and 2) that the 1 results of a new fuel oil sample (sample obtained prior to ) | |||
addition but not more than 31 days prior to) are obtained within 31 days after addition, i | |||
l FERMI- UNIT 2 Page B 3.8 47 (Insert) REVISION 7 06/18/99l | |||
l Diesel Fuel Oilfp} and Starting Air l@/ | |||
B 3.8.3 \._ | |||
i BASES | |||
( . | |||
l 2' l | |||
l SURVEILLANCE REQUIREMENTS SR 3.8.3 7 (continued) lh l concer.tration is unlikely to change significantly between Frequency intervals. | |||
SR 3.8.3. | |||
l @ | |||
This Surveillance ensures that, without the aid of the refill compressor, sufficient air start capacity for each DG is available. The system design requirements provide for a , | |||
m}n g- of p el end ne spart,cyg es w g oup,gecpar g g L.-- , | |||
j w[.. wh a muse w t suas h.h w u rw h h[ . w[ ,[,h a ved L.,Ai v .,,.... l---The pressure specified in this SR is intended to ref" eet the lowest value at which the (fivel starts can be accomplished. | |||
The,(31kdayFrequencytakesintoaccountthecapacity, capability, redundancy, and diversity of the AC sources and i other indications available in the control room, including alarus, to alert the operator to below normal air start pressure. | |||
SR 3.8.3 Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water Ifg g environment in order to survive. Removal of water from the fuel storage tanks once every ,L31kdays eliminates the necessary environment for bact'eYtal survival. This is the most effective means of controlling microbiological fouling. | |||
In addition, it eliminates the potential for water entrainment in the fuel oil during DG operation. Water may come from any of several sources, including condensation, ground water, rain water, contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity 'of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily represent failure of this SR, provided the accumulated water is removed during performance of the Survelliance. | |||
(continued) | |||
BWR/4-STS B 3.8-48 Jtey 1, 04/07/95 Ren | |||
Diesel Fuel Oil and Start n BASES SURVEILLANCE SR 3.BI6 ' | |||
REQUIREMENTS ' | |||
(continued) Drai ng of the fuel oil store n.thusupplytanhs, removal of cumulated sediment, and nk cleaning are required at 1 year intervals by Regulat Guide 1.137 (Ref. 2), | |||
aragraph 2.f. This SR is ypically performed in conjunction with ASME Boi r-end Pressure Vessel Code, Section XI (Ref. 7), ex inations of the tanks. To prec1 e g,( the introduction of s actants in the fuel oil system, e cleaning should be a amplished using sodium hypochio e solutions or their uivalent, rather than soap or detergents. This R is for preventive maintenane The presence of sedi nt does not necessarily repre nt a failure of this R provided that accumulated ediment is W wed durino erformance of the Surveillan g REFERENCES 1. SAR,Section(9.5 | |||
: 2. Regulatory Guide 1.137. | |||
: 3. ANSI N195, 1976. | |||
4.hSAR, Chapter 46{. | |||
5 $ 5AR, Chapter {15h | |||
: 6. ASTM Standards: D4057-Tssi;D975-Yqs};D4176-Ju}; | |||
D1552-pop D2622-J37); and 02276-yt J. | |||
a = w . . . . .. . . - . . | |||
!""./' US B 3.8-49 Rev-1,-04/07/95-Rev7 1 | |||
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.3 DIESEL FUEL OIL AND STARTING AIR lh i | |||
NON BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and consnitments. Additional rewording, reformatting, and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. | |||
P.2 Bases changes are made to reflect plant specific design details. ) | |||
equipment terminology, and analyses. ' | |||
P.3 Not used. ! | |||
P.4 The Bases discussion regarding implementation of the Emergency Diesel Generator Fuel Oil Testing Program is revised. These revisions include, editorial enhancement for clarity, supplying the basis and intent of some of the required time limits of the Program: | |||
and include plant specific corrections for consistency with approved testing methods and procedures. | |||
Given the varying options for " receipt" of fuel oil, there may be potential delays between " receipt", sampling, analysis. and addition to the EDG storage tank. Therefore, additional detailed l | |||
clarification is appropriate. The Bases presented in the NUREG ' | |||
assumes that any and all fuel oil received is promptly added to , | |||
the storage tanks (after initial sampling). The clarification is ' | |||
needed specifically in the event fuel oil is " received" and stored on site for a period prior to addition to the tanks. The h inference in the ITS Bases would be that a fully tested sample is .d. | |||
required within 31 days after this " receipt": even if it is many $' | |||
months before the fuel oil is to be added to the storage tenk. | |||
The correct intent is supplied with this change (which is the same as the STS in the event the fuel oil is promptly added). The sample that will have a detailed follow-up analysis must be a recent sample of fuel oil: taken no more than 31 days before addition. This will leave a window for receipt of the sample analysis results from 31 days prior to addition to up to 31 days after addition. | |||
FERMI UNIT 2 1 REVISION 7 06/18/99 l | |||
m. | |||
4 l | |||
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l@ | |||
- P.5 ISTS 3.8.3 Action E for EDG air receivers below minimum air pressure, is not adopted. This Action reflected new, added flexibility to the CTS requirements which consider the EDG inoperable as soon as low air pressure is. discovered. Similarly. | |||
~ | |||
'ISTS 3.8.3 Action 8 and SR 3.8.3.2 for EDG lube oil minimum volume, is 'not adopted. This would have provided new, added flexibility to considering the EDG inoperable while providing time | |||
-to~ restore lube oil quantities. The additional flexibility would require additional design testing, analyses, and or procedures and programs beyond the scope of the Fermi 2 conversion effort. | |||
Therefore. this flexibility is not adopted at this time. | |||
P.6 ~ Editorial changes to reflect Writer's Guide conventions. When the LCO requirement might be requiring Operability of only some of the EDG subsystems (because in shutdown operations not all EDGs are required Operable), the convention is to use " required" in the Actions and Surveiliances when referring to the EDG. | |||
P.7 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification. | |||
" split" criteria found in 10 CFR 50.36(c)(2)(ii). | |||
GENERIC CHANGES ! | |||
C.1 TSTF 2: NRC approved change to NUREG-1433. O 4 | |||
FERMI - UNIT 2 .2 REVISION 7 06/18/99l u | |||
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 DIESEL FUEL OIL AND STARTING AIR l@ | |||
TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.3 "L.1" Labeled Comments / Discussions) | |||
Detroit Edison has evaluated the proposed Technical Specification change identified as "Less Restrictive" in accordance with the criteria specified by 10 CFR 50.92 and has determined that the proposed change does not involve a significant hazards consideration. | |||
The bases for the determination that the proposed change does not involve a signifirant hazards consideration is an evaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below. | |||
: 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated? | |||
This change provides an allowable out of service time for diesel fuel oil and lube oil when these parameters are less than the required value. ] | |||
but which do not prevent the EDG from performing its safety function. | |||
This change will not result in a significant increase in the probability of an accident previously evaluated because the status of diesel fuel oil and lube oil does not affect the initiators of any analyzed event. | |||
This change does not affect the ability of the EDGs to support the performance of any credited equipment. As a result. no analyses assumptions are violated. Each of these EDO parameters contains substantial margin before reaching a condition that would prevent the EDG from performing its safety function and during the period allow for restoration, the EDG is still capable of performing its intended function. Based on this evaluation. there is no significant increase in the consequences of a previously analyzed event. | |||
: 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated? | |||
This proposed change will not involve any physical changes to plant systems, structures. or components (SSC), or changes in normal plant operation. Therefore, this change will r.ot create the possibility of a new or different kind of accident from any accident previously evaluated. | |||
FERMI - UNIT 2 1 REVISION 7 06/18/99l | |||
i l | |||
N0 SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l@ | |||
TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.3 "L.1" Labeled Comments / Discussions) | |||
: 3. Does this change involve a significant reduction in a margin of safety? | |||
The proposed change provides an allowable out of service time for diesel fuel oil and lube oil when these parameters are less than the required value. Each of these parameters contains substantial margin before reaching a condition that would prevent the EDG from performing its safety function. During the time allowed for restoring an out of limits parameter, the EDG is still capable of performing its intended function. | |||
There is no detrimental impact on any equipment design parameter, and the plant will still be required to operate within prescribed limits. | |||
While certain margins are decreased, based on the limited extent of the degradation (at least 6 days of fuel oil remains: EDG start capability remains: and fuel oil is still expected to support EDG operation), and the limited duration of these degradations, the change does not involve a significant reduction in the margin of safety. | |||
FERMI - UNIT 2 2 REVISION 7 06/18/99l | |||
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l@ | |||
TECHNICAL CHANGES - LESS RESTRICTIVE (Soecification 3.8.3 "L.2" Labeled Comments / Discussions) | |||
Detroit Editon has evaluated the proposed Technical Specification change identified as "Less Restrictive" in accordance with the criteria specified by 10 CFR 50.92 and has determined that the proposed change does not involve a significant hazards consideration, i | |||
The bases for the determination that the proposed change does not involve a significant hazards consideration is an evaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below. | |||
: 1. Does the change involve a significant increase in the probability or i consequences of an accident previously evaluated? | |||
The EDG fuel oil level verification staggered testing requirements have been deleted. This change will not result in a significant increase in 4 | |||
5 1 the probability of an accident previously evaluated because the test T schedule or verification of EDG fuel oil level has no effect on the initiators of any analyzed events. This change will not result in a significant increase in the consequences of an accident previously evaluated because the normal Technical Specification surveillance testing schedule provides adequate assurance that the Operable EDGs will be capable of performing their intended safety functions without additional verification of fuel oil level. Staggered testing provides no additional assurance of reliability because the EDGs are independent and the potential of a common cause failure is evaluated promptly whenever any EDG becomes inoperable. | |||
: 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated? | |||
This proposed change will not involve any physical changes to plant systems, structures, or components (SSC), or changes in normal plant operation. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. | |||
FERMI UNIT 2 3 REVISION 7 06/18/99l | |||
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 DIESEL FUEL OIL AND STARTING AIR lh TECHNICAL CHANGES - LESS RESTRICTIVE (Soecification 3.8.3 "L.2" Labeled Comments / Discussions) ) | |||
: 3. Does this change involve a significant reduction in a margin of safety? | |||
The proposed change, which allows only more scheduling flexibility in i performing EDG Surveillances while continuing the same frequency of g testing, is acceptable because the Operability of the EDGs is unaffected 2 by testing schedules, there is no detrimental impact on any equipment design parameter, and the plant will still be required to operate within g | |||
assumed conditions. The normal Technical Specification Surveillance testing schedule provides adequate assurance that the Operable EDGs will be capable of performing their intended safety functions. Staggered testing provides no additional assurance of reliability because the EDGs are independent and the potential of a common cause failure is evaluated promptly whenever any EDG becomes inoperable. Therefore the change does not involve a significant redetion in the margin of safety. | |||
i FERMI UNIT 2 4 REVISION 7 06/18/99l l | |||
DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS | |||
' SURVEILLANCE FREQUENCY m SR' 3.8.4.1 Verify battery terminal voltage is a 130 V 7 days for Division I and a 125.7 V for lb Division II on float charge. | |||
6 SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors. | |||
2 Verify each battery cell to-cell and terminal connection resistance is s 1.5E 4 ohm. | |||
t4 SR 3.8.4.3 Verify battery cells, cell plates, and 18 months J. racks show no visual indication of physical i 4 damage or abnormal deterioration that could i | |||
%, degrade battery performance. | |||
SR 3.8.4.4 Remove visible corrosion and verify battery 18 months cell to cell and terminal connections are coated with anti corrosion material. j SR 3.8.4.5 Verify each battery cell to cell and 18 months terminal connection resistance s 1.5E-4 ohm. | |||
SR 3.8.4.6 Verify each required battery charger 18 months O supplies for Division I: a 100 amps at g a 129 V for a 4 hours; and Division II: | |||
= 100 amps at = 124.7 V for a 4 hours. | |||
L% | |||
(continued) | |||
.s l FERMI UNIT 2 3.8-17 Revision 7 06/18/99 | |||
J l | |||
DC Sources-Operating B 3.8.4 | |||
' BASES' BACKGROUND (continued) a- Each DC battery subsystem is separately housed in a | |||
. ventilated room a) art from its charger and distribution j centers. Each su) system is located in an area separated | |||
' physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class IE subsystems such as batteries, battery chargers, or distribution panels. ' | |||
The batteries for DC electrical power subsystems are sized to produce required capacity at 80% of nameplate rating, m corresponding to warranted capacity at end of life cycles A and the 100% design demand. The minimum design voltage 4 limit is 105/210 V. | |||
Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation. while at the same time maintaining its battery bank fully charged. | |||
Each battery charger has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 24 hours while supplying normal steady state loads (Ref. 11). | |||
4 APPLICABLE ~ The initial conditions of Design Basis Accident (DBA) and | |||
: SAFETY ANALYSES ' transient analyses in the UFSAR. Chapter 6 (Ref. 4) and ' | |||
Chapter 15 (Ref. 5). assume that Engineered Safety Feature- , | |||
(ESF) systems are OPERABLE. The DC electrical power system provides. normal and emergency DC electrical power for the EDGs. emergency auxiliaries, and control.and switching during all MODES of. operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis ' | |||
' of the unit. This includes maintaining sufficient DC i sources OPERABLE during accident conditions in the event of: : | |||
E a. . An assumed loss of all offsite AC power or all onsite AC power; and | |||
: b. A worst case single failure. | |||
The DC sources satisfy Criterion 3 of 10 CFR ; | |||
50.36(c)(2)(ii). | |||
[ FERMI UNIT 2' B 3.8.4-2 Revision 7 06/18/99 I | |||
1 l | |||
DC Sources-Operating B 3.8.4 BASES i | |||
LC0 The DC electrical power subsystems-with each DC subsystem | |||
, consisting of two 130 VDC batteries in series, two battery chargers, and the corresponding control equi > ment and interconnecting cabling supplying power to t1e associated bus, are required to be OPERABLE to ensure the availability of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (A00) or a postulated DBA. Loss of any DC electrical power subsystem does not prevent the minimum safety function from being performed (Ref. 3). | |||
APPLICABILITY The DC electrical power sources are required to be OPERABLE in MODES 1, 2. and 3 to ensure safe unit operation and to ensure that: | |||
: a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of A00s or abnormal transients: and i | |||
: b. Adequate core cooling is provided, and containment l integrity and other vital functions are maintained in ! | |||
the event of a postulated DBA. ; | |||
i' The DC electrical power requirements for MODES 4 and 5 are addressed in the Bases for LCO 3.8.5 "DC Sources-Shutdown." | |||
ACTIONS A.1 and B.1 Conditions A and B represent one division with a loss of i ability to completely respond to an event, and a potential loss of ability to remain energized during normal operation. | |||
If one of the re inoperable (e.g., quired DC electrical inoperable power subsystems battery, inoperable battery is charger (s), or inoperable battery charger and asscciated inoperable battery), the remaining DC electrical power subsystems have the capacity to support a safe shutdown and to mitigate an accident condition. A subsequent worst case single failure could, however. result in the loss of minimum necessary DC electrical subsystems to mitigate a worst case accident. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the hlFERMIUNIT2 B 3.8.4 - 3 Revision 7 06/18/99 i | |||
L l | |||
l DC Sources-Operating B 3.8.4 l | |||
! BASES. | |||
ACTIONS (continued) potential for com)lete loss of DC power to the affected | |||
.- division. The 4 lour Completion Time (Required Action A.1) for restoration of an inoperable battery charger allows time to replace the inoperable charger with an OPERABLE spare | |||
, battery charger, if available. The four hour. limit is reasonable based on the remaining capability of the battery i to carry the loads for this period. The 2 hour limit for l Required Action B.1 is consistent with the allowed time for an inoperable DC Distribution System division. The 2 hour , | |||
l Completion Time is based on Regulatory Guide 1.93 (Ref. 6) | |||
I and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and. if the DC electrical power subsystem is not restored to l OPERABLE status, to prepare to effect an orderly and safe l | |||
unit shutdown. | |||
C.1 and C.2 . | |||
If the station service DC electrical power subsystem cannot l | |||
< be restored to OPERABLE status within the required Completion Time, 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 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the recuireti plant conditions from full power conditions in an orcerly manner and without challenging plant systems. -The Completion Time to bring the unit to MODE 4 is consistent I with the time required in Regulatory Guide 1.93 (Ref. 6). | |||
SURVEILLANCE SR 3.8.4.1 REQUIREMENTS Verifying battery terminal voltage while on float charge for , | |||
the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with manufacturer recommendations and IEEE 450 (Ref. 7) j B 3.8.4 -4 Revision 7 06/18/99 hlFERMI-UNIT 2 | |||
(L DC Sources-Operating l B 3.8.4 l | |||
BASES | |||
. SURVEILLANCE REQUIREMENTS (continued) | |||
SR 3.8.4.2 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each inter cell and terminal connection, provides an indication of. physical damage or abnormal deterioration that could potentially degrade battery performance. | |||
The connection resistance limits procedurally established for this SR are no more than 20% above the resistance as measured during installation and not above the ceiling value established by the manufacturer. This provides conservative measures to assure the Technical Specification limit is not exceeded. | |||
The Frequency for.these inspections, which can detect conditions that can.cause power losses due to resistance heating is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends. | |||
SR 3.8.4.3 | |||
. Visual-inspection of the battery cells cell plates, and | |||
' battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. The presence of physical damage or | |||
'd deterioration does not necessarily represent a failure of J - this SR. provided an evaluation determines that the physical g . damage or deterioration does not affect'the OPERABILITY of | |||
<the battery (its ability to perform its design function). | |||
The 18 month ~ Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable from a standpoint of maintaining reliability. | |||
s_ . . | |||
l FERMI UNIT ~2 'B 3.8.4 - 5 Revision'7. 06/18/99 | |||
:/ | |||
} . | |||
l l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.4 - DC SOURCES-0PERATING ADMINISTRATIVE l | |||
A.1 In the conversion of the Fermi 2 current Technical Specifications ! | |||
(CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not result in technical changes (either actual or interpretational). Editorial changes, reformatting, and re' vised numbering are adopted to make the ITS consistent with the Boiling Water Reactor (BWR) Standard Technical Specifications l NUREG 1433 Rev. 1. | |||
A.2 CTS SR 4.8.2.1.e limitation on the 60 month battery performance discharge test, to perform it "during shutdown." is more specifically presented in ITS SR 3.8.4.7 Note. The ITS SR is l presented with a more specific Note limiting the performance in Modes 1, 2, and 3. This specific limitation is consistent with the intent of "during shutdown" for this surveillance (as discussed with the NRC during ITS negotiations). Since this is , | |||
only a change in presentation of the CTS intent and current l practice, this change is considered administrative. l TECHNICAL CHANGES MORE RESTRICTIVE l None TECHNICAL CHANGES - LESS RESTRICTIVE | |||
" Generic" l | |||
LA.1 CTS LC0 3.8.2.1 provides details defining the two divisions of DC T power sources. The details relating to system design. function. 9 ar.d Operability are not necessary in the ITS. This information is 4 relocated to the Bases, which maintains the consistency with NUREG 1433. The definition of Operability, the Bases outline of Operability details (which requires change control in accordance with ITS 5.5.10. Bases Control Program) provides sufficient l control of these details. These details are not required to be in the ITS, to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. | |||
FERMI UNIT 2 1 REVISION 7 06/18/99l l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.4 DC SU'JRCES 0PERATING LA.2 CTS 3.8.2.1. Action a. details one procedure for restoring an inoperable battery charger to Operable status " replace with the spare battery charger." This detail is relocated to the Bases for the ITS 3.8.4 Action to restore the battery charger to Operable status. The relocation of this information maintains the consistency with NUREG-1433. This is acceptable because these details do not impact the requirement to restore an Operable charger to service. These ' details can be adequately defined and controlled in the Bases which require change control in accordance with ITS 5.5.10. Bases Control Program. These details are not required to be in the ITS to provide adequate protection of the public health and safety, because these details do not impact the requirement to restore the required equipment to Operable. | |||
LA.3 The CTS details incl'ude the design duty cycle (4 hours), and, with l the option to simulate the emergency loads (using a " dummy load") | |||
by specifying the design load profile. CTS SR 4.8.2.1.d.2 details , | |||
the requirement for performance of a simulated battery service 4 test. ITS SR 3.8.4.7 relocates these design details to the UFSAR 6 and Technical Requirements Manual (TRM) but does retain the y requirement for the battery service test, and allowance for an t | |||
" actual or simulated" test. Relocating these surveillance details maintains consistency with NUREG 1433. These relocated design details can be adequately defined and controlled in the UFSAR and TRM. Changes to the UFSAR and To.M will be controlled by the provisions of 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the requirement for the battery service test remains in the Technical Specifications. , | |||
LA.4 CTS 4.8.2.1.f provides details defining battery performance degradation. The relocation of this information to the ITS Bases maintains the consistency with NUREG 1433. Any change to these details requires change control in accordance with ITS 5.5.10. | |||
Bases Control Program, which provides adequate control of these details. These details are not required to be in the ITS to provide adequate protection of the public health and safety. | |||
because these details do not impact the requirement to maintain the equipment Operable, or the requirement to perform the battery performance discharge test. | |||
FERMI UNIT 2 2 REVISION 7 06/18/99l | |||
r-l l | |||
l DC Sources-Operating i 3.8.4 l | |||
l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 7 days kfl ' | |||
2 - T"1%on float charee. - * | |||
*7 | |||
* g ' g-fa @ Diyisie7 Awd h.125q sW bm H. | |||
SR 3.6.4.2 Verify no visible corrosion at battery 92 days teminals and connectors. | |||
g eac k-fo _cdl and 44kinh Verify attery connection resistancee[is . | |||
s 41.5E-4 ohn)ef - i=+- -re" e-----t4e-r, l P. I s ::.;; c.;: <a- <=+- rut car.r.;nic;.;, - | |||
f L EE ' ^M f:r int:r ti;, ......d ;m.e, | |||
:M f (LLL_6] f ,7 ;;.;inel- | |||
::::ntit,r.;]. | |||
C'I SR 3.8.4.3 Verify battery cells, cell plates, and months ; | |||
racks show no visual indication o ical 4 l damage or abnormal deterioration -tha .%.7 . l ,0- l- k (c oyta cityade, leaW1 p u %_ nw. | |||
SR 3.8.4.4 Remove visible corrosion and verify battery months cell to cell and terminal connections are f,l --[:l::: : d it;ht, M] coated with 4*8'2*I'01 anti-corrosion material. | |||
@ d^d D lD M k_fHbattery7connectionresistance /8 SR 3.8. Ver' montns tac -" | |||
5 0 5E 4 oh t fr- 4-t M .',:-; cler, ~----t aae-M :r :rn i ::n---ti:::, | |||
p'g . | |||
s ;;."., -4 i,; , f;r intoe-44cr :: nn tirn:. V, E,2 ) . 0. 3 | |||
::d ; !!.5El &] fsr t:--i- ' | |||
ee;.ndies) . | |||
(continued) | |||
St W 4- N 4 3.8-25 "= 1, Ot/07/05 AEV ] | |||
j | |||
DC Sources-Operating B 3.8.4 BASES BACKGROUND In case of loss of normal power to the battery charger, the (continu DC loads are automatically powered from the-e;.ti n - | |||
(' 2. batteries. | |||
The DC power distribu ion system is described in more detail | |||
. in Bases for LCO 3.8. , " Distribution System-Operating," | |||
and LC0 3.2, " Distribution System-Shutdown." | |||
Each battery has adequate storage capacity to carry the required load continuously for approximately hours (Ref. 4 4 n, | |||
i fach battery subsystem is separately housed in a ventilated room apart from its charger and distribution centers. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class IE subsystems such as batteries, battery chargers, or distribution panels. | |||
The batteries for DC electrical power subsystems are sized to produce required capacity at 80% of nameplate rating, (9 corresponding to warranted capacity at end of life cycles 1 and the 100% design demand. The minimum design voltage R limit is 105/210 V. W Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation , | |||
of connected loads required during normal operation, while at the same time maintaining its battery bank fully charged. | |||
P.3 Each M"4 - | |||
:nin battery charger has sufficient capacity , | |||
1 to restore the battery from the design minimum charge to its l fully charged state within 24 hours while supplying n9rmal I steady state loads (Ref. . | |||
APPLICABLE The initial conditions o sign Basis Accident (DBA) and SAFETY ANALYSES transient analyses in th SAR, Chapter 4k (Ref. 4) and Chapter 115k (Ref. 5), assume that Engin{eered Safety Feature (ESF)sfs1ensareOPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the ! | |||
DGs, emergency auxillaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial issumptions of the (continued) 4"!/1 ST: B 3.8-51 6 1, 0?/07/;: - | |||
/ | |||
Rev7 | |||
/ | |||
1 DC Sources-0perating B 3.8.4 | |||
/ | |||
INSERT B 3.8.4-2 | |||
<< R OVED in Revi ion 7 >> i l | |||
l 1 | |||
l l | |||
l | |||
/$- 0 FERMI UNIT 2 Page B 3.8 51 (Insert) REVISION 7' 06/18/99l } | |||
DC Sources-Operating B 3.8.4 BASES I | |||
SURVEILLANCE SR 3.8.4.2 (continued) | |||
REQUIREMENTS acceptable based on operating experience related to detecting corrosion trends. | |||
SR 3.8.4.3 I | |||
/NMT Visual inspection of the battery cells, cell plates, and f 3,3,Q qq battery racks provides an indication of physical damage or 1 | |||
abnormal deterioration that.could potentially degrade e1 battery performance. 3 I g,,Qpgtifib....pg'ertii.!"1: 9.,.pi:t:gtejth } | |||
* t _E*'' | |||
r. | |||
3 ;''* | |||
* v' 6 * ' NU ''*u*'' | |||
n".".L*..' t. !.6'v"e'.w"i 6 : en anu rau i6fn v. 6 .vi. | |||
ym. . .y q | |||
h3,7 4k - | |||
J p,1 SR 3.8.4.4 and SR 3.8.4.5 Visual inspection and resistance measurements of inter-cell,. | |||
int:r r::h, int:r ti:r s and terminal connections provides W indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti-corrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. | |||
The visual inspection for corrosion is not intended to require removal of and inspection under each teneinal connection. | |||
The removal of visible corrosion is a preventive maintenance SR. The presence of visible corrosion does not necessarily represent a failure of this SR, provided visible corrosinn is removed during performance of this Surveillance. | |||
1 er's Note: The requiremen to verify that term on etions are lean and tight applies only to nickel a ium batter s as per IEEE tandard P1106, EEE Op.3 Re on. ended e etice for Ins iation, nainte ance, Testi a d Replace t of Vented Ni kel - Cadmium B tteries for tationary plications.'' his requirement y be remo d or lead a d batteries. , , | |||
(continued) | |||
BWR/4 STS B 3.8-55 Rey-1704f07j95 eav7 i | |||
) | |||
DC Sources Operating B 3.8.4 | |||
, INSERT B 3.8.4 4a The presence of physical damage or deterioration does not necessarily represent a failure of this SR provided an | |||
[ | |||
evaluation determines that the physical damage or g deterioration does not affect the OPERABILITY of the battery P (its ability to perform its design function). 8 k | |||
t INSERT B 3.8.4 4b l/ | |||
The 18 month Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable -from a standpoint of maintaining reliability. | |||
FERMI UNIT 2 Page B 3.8 55 (Ir 't) REVISION 7. 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.5 DC SOURCES. SHUTDOWN M.2 CTS 3.8.2.2 Actions for inoperable DC sources, does not require corrective action to restore the inoperable source. ITS 3.8.5 requires the immediate corrective actions (Required Action A.2.4) to restore the inoperable DC sources. This eliminates flexibility, and is therefore a more restrictive change assures efforts to return the plant to acceptable safe operation from the standpoint of necessary electrical support. As such, this more restrictive change has no negative impact on safety. | |||
TECHNICAL CHANGES - LESS RESTRICTIVE | |||
'' Generic" LA.1 CTS LC0 3.8.2.2 provides details defining the two divisions of DC power sources. The details relating to system design, function. Y and Operability are not necessary in the ITS. This information is 9O relocated to the Bases, which maintains the consistency with NUREG 1433. The definition of Operability, the Bases outline of Operability details (which requires change control in accordance with ITS 5.5.10. Bases Control Program) provides sufficient control of these details. These details are not required to be in the ITS to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. | |||
) | |||
1 1 | |||
FERHI UNIT 2 2 REVISION 7 06/18/99l ! | |||
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.5 DC SOURCES SHUTDOWN NON BRACKETED FLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current Technical Specification requirements. Specifically. LC0 3.0.3 is not Fequired to'be applied to the Actions of this Specification. | |||
P.2 Bases changes are made to reflect plant specific design details. | |||
equipment terminology. and analyses. | |||
P.3 Bases changes are made to reflect changes made to the Specification. | |||
Refer to the Specification and associated JFD if applicable for i additional detail. | |||
P.4 NUREG-1433 imposes excessively restrictive DC power source requirements when features on both divisions are required to be Operable. This change continues to require Operable DC power ! | |||
sources on both divisions. but relaxes the ISTS requirements for one division. This will allow for appropriate surveillance and testing activities during shutdown conditions. CTS requirements I were made more restrictive to reflect this proposed ITS. Refer to associated DOC M.1 provided below for reference: | |||
M1 CTS 3.8.2.2 requires one division of battery and battery charger to be Operable during shutdown conditions, but is not specific as to which division it must be powering. ITS imposes additional requirements consistent with the Operability requirements of all other features that may be required to be Operable by the ITS. | |||
Specifically ITS 3.8.5. DC Sources - Shutdown requires: 1) one div.ision to be Operable with both 125 V batteries and both associated battery chargers, and 2) when the other DC distribution subsystem division is required to be energized, providing power from at least one battery or one battery charger. | |||
Since the DC sources Operability requirements are extended to require the capability of supplying power to all necessary loads. | |||
if one or more required DC sources are not Operable, sufficient DC sources may still be available to support sufficient required components to allow continuation of refueling activities for a limited time. Therefore. it may not be necessary to suspend all Core Alterations, irradiated fuel handling, and OPDRVs. | |||
Conservative Actions can be assured if all required equipment associated with the inoperable DC source are declared inoperable and their associated Actions taken. Therefore, along with the conservative additional requirements placed on Operable DC sources. Required Action A.1 is also proposed. | |||
FERMI - UNIT 2 1 REVISION 7 06/18/99l | |||
. J | |||
Battery Cell Parameters 3.8.6 3.8- ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 - Battery cell parameters for the Division I and Divis. ion II batteries shall be within limits. | |||
APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE. | |||
. ACTIONS | |||
..................................... NOTE----- - --- - -- ------ - -- ---- | |||
Separate Condition entry is allowed for each battery. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cells 1 hour with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6 1 ! | |||
@l | |||
# Table 3.8.6 1 Category Category C limits. ' | |||
A or B limits. ; | |||
! AND k | |||
~ | |||
A.2 Verify battery cell 24 hours , | |||
parameters meet Table 3.8.61 AND Category C limits. , | |||
Once per 7 days ' | |||
thereafter AND A.3 Restore battery cell 31 days parameters to , | |||
Table 3.8.6 1 hl l Category A and B limits. | |||
(continued) l FERMI UNIT 2- 3.8 22 Revision 7 06/18/99 i | |||
Battery Cell Parameters 3.8.6 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable. | |||
Time of Condition A not met. | |||
08 One or more batteries with average electrolyte temperature of the representative cells not within limits. | |||
08 One or more batteries with one or more battery cell parameters not within Table 3.8.6 1-Category C values. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE- FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.6 1 Category A limits. | |||
(continued) | |||
: l. FERMI UNIT 2 3.8-23 Revision 7 06/18/99 | |||
Battery Cell Parameters B 3.8.6 BASES ~ | |||
SURVEILLANCE REQUIREMENTS (continued) | |||
Category C' defines the limits for each connected cell. | |||
These values. although reduced, provide assurance that | |||
. sufficient capacity exists to perform the intended function | |||
' and maintain a margin.of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and | |||
' the battery must be declared inoperable. | |||
The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates. suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value for voltage is based on IEEE 450 (Ref. 3), which states that a cell voltage of 2.07 V or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement. | |||
The Category C limit'on average specific gravity a 1.190. is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit. it is required that | |||
+he specific gravity for each connected cell must be no less | |||
'than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery. ' | |||
2I -Footnote (b) to Table 3.8.6 1 is applicable to Category A. ! | |||
Q B. and C specific gravity. Footnote (b) of Table 3.8.6 1 requires the above mentioned correction for electrolyte 3 level and temperature. : | |||
Because of specific gravity gradients that are produced l | |||
.during the recharging process. delays of several days may occur while waiting for the specific gravity to stabilize. | |||
A stabilized charger current is an acceptable alternative to sacific gravity measurement for determining the state of m c1arge of the designated pilot cell. This phenomenon is 1 ' discussed in IEEE 450 (Ref. 3). Footnote (c) to Ql ' Table 3.8.6 1 is applicable to Category A and C. and allows the float charge current to be used as an alternate to | |||
- speci fic . gravity. | |||
l FERMIL UNIT 2 B 3.8.6 -6 Revision 7 06/18/99 j | |||
b i i | |||
ELECTRICAL-POWER SYSTEMS 3/4.8.2 fpfc / F/ e4 77DM .3 7 le D.C. SOURCES D.C. SOURCES - OPERATING g g.gg g,g, j (Also .sa .spuiRca He 3 7.2-) | |||
LIMITING CONDITION FOR OPERATION (3.8.2.I As a minimum, the following 0.C. electrical power sources shall.be OPERABLE: ; | |||
a .. . Division 1. consisting of: | |||
El. 130 VDC Battery 2A-1. | |||
: 2. 130 VDC Battery 2A-2. i | |||
: 3. Two 130 VDC full capacity chargers. - | |||
: b. Division II. i:onsisting of: | |||
: 1. 130 VDC Battery 2B-1. | |||
,2 . 130 VDC Battery 28-2. | |||
: 3. Two 130 VDC full capacity chargers. , | |||
APPLICABILfTY: OPERATIONAL CONDITIONS 1, 2, and 3. | |||
d A'Y ACTION: | |||
sf d | |||
\ N / | |||
t. | |||
With a battery charger in either Division I or Division II of the above D.C. electrical power sources inoperable, restore the inoperable battery l I | |||
charger to OPERABLE status or replace with the spare battery charger f within in COLD4SHUTDOWN hours or be inthe within at following least HOT SHUTDOWN within the next 12 hours 24 hours. | |||
: b. ; | |||
With either Division I or Division II of the above required D.C. | |||
electrical power sources otherwise inoperable, restore the inoperable . | |||
division to OPERABLE status within 2 hours or be in at least HOT SH within"the'next 12 hours and in COLD SHUTDOWN within the following 24 hours. | |||
SURVEILLANCE REOUTREMEt'TS l 4.8.2.1 | |||
< demonstrated OPERABLE:Each f of the above required 130-volt batteries and chargers s | |||
: a. i At least once per 7 days by verifying that: | |||
S A 3.3.4 1 1. | |||
The and parameters in Table 4.8.2.1-1 meet the Category A limits, su- . | |||
spa ge gm 7.r. ~ Total battery terminal voltage is greater than or equal to 130 for nlvision 11 on float charge. volts for Division I and 'greater th | |||
: b. ,l ! | |||
At least onceJer 92 dals/and withinW.a eryL/ | |||
N hovd | |||
[i battery r overcharge with battery terminal e voltagdiscTarge eater than 150 | |||
' li gl i_ 1 and greater than 145 volts f_ D1 vision 11 y | |||
.I | |||
, l SA 34,(,,'2 J 1. 1_( 4.< sA 3. s 4. 3 ') l. . -+- | |||
The parameters in Table 4.8.2.1-1 meet the Category B limits, 1d t | |||
'This | |||
'3.7.1.2 are ACTION taken. may be delayed for up to 16 hours for batte f SR. S)Lati$ cal 3n 3.& | |||
FERMI - UNIT'2 3/4 8-10 Amendment No. BB.121 PAGE 3- # 03 Ra 7 t | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.6 BATTERY CELL PARAMETERS Additionally. CTS 4.8.2.1.b requires- a verification that battery parameters, meet Category B limits within 7 days after a battery discharge or overcharge. This 7 day " allowance" is consistent with the CTS 7 day action time discussed above. ITS SR 3.8.6.2 provides a more restrictive requirement to surveil battery parameters within 24 hours after a battery discharge or overcharge. While this surveillance is a more restrictive frequency, it is accompanied by the extended (31 day) Completion Time discussed above: and is therefore, of minimal impact on operation. | |||
L.2 CTS Table 4.8.2.1 1 requires that the electrolyte level be maintained in a specified range. ITS Table 3.8.6-1 footnote (a) allows for a temporary electrolyte level increase during and following an equalize charge and is based on guidance from Appendix A to IEEE-450. The level excursion due to gas generation during an equalizing charge would be expected to return to normal following completion of the equalize charge. Therefore, this less restrictive change will have a negligible impact on safety. | |||
L.3 CTS 4.8.2.1.b.3 requires that once every 92 days and within 7 days after a battery discharge or overcharge, the average electrolyte temperature is verified to be above 60 F. ITS SR 3.8.6.3 requires this same verification to be performed only once every 92 days, eliminating the increased frequency after a battery discharge or > | |||
overcharge. This is acceptable because a large discharge or d overcharge of the battery will tend to heat the battery electrolyte not reduce the temperature. The need to increase the k | |||
frequency of monitoring electrolyte temperature is not necessary. | |||
Therefore, this less restrictive change will have no impact on safety. | |||
RELOCATED SPECIFICATIONS None 4 | |||
TECHNICAL SPECIFICATION BAE S Bases for this Specification have been added that reflect the format and applicable content of ITS 3.8.6 consistent with the BWR STS. NUREG-1433. | |||
_.. Rev. 1. l FERMI - UNIT 2 3 REVISION 7 06/18/99l l | |||
Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS | |||
[ CTS) 3.8.6 ' Battery Cell Parameters _ | |||
LCO 3.8.6 OivifikI cwd Civisih Battery cell parameters for the-pt:ti;r, ;...w . .riu uuj gg 4, batteries shall be within@ limits-;f ide,0.9.5 L APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE. | |||
ACTIONS | |||
-NOTE - - - - - - - - - - - - - - - - - - - - - - - - | |||
Separate Condition entry is allowed for each battery. | |||
3 CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verifypilotcell,[sl I hour 78t 4.12 8-1; with one or more electrolyte level and nok 0h(D battery cell float voltage meet parameters not within Table 3.8.6-1 1 Category A or B Category C limits. | |||
limits. Q3 4 l | |||
TabitS8 A.2 Verify battery can 24 hours g OC.I .. parameters meet Table 3.8.6-1 M Category C limits. | |||
Once per 7 days thereafter M | |||
A.3 Restore battery cell 31 days parameters to Category A and B | |||
_ limits D( sf Table 3.5.6-J. | |||
(continued) | |||
--0WRf4-GM-- 3.8-30 ^ev 1, 04/07/06- | |||
@v7 | |||
l l | |||
l Battery Cell Parameters 3.8.6 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME-l B. Required Action and B.1 Declare associated Imediately | |||
. associated Completion battery inoperable. | |||
Time of Condition A T6L 941.1-l) not met. | |||
g , g y) | |||
E ; | |||
One or more batteries i with average I electrolyte temperature of the 3.1.1. b.3 ) | |||
representative cells not within limits. | |||
E One or more batteries with one or more battery cell parameters not within 1 yCategort C values. | |||
NT abl&3.8E-D 1 | |||
1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days A Table 3.8.6-1 Category A limits. 4 0 2.l A .j p i | |||
(continued) ; | |||
l L;/4 :T: 3.8-31 L.1, C4/C7/>6-- | |||
Ren/ 7 | |||
i Battery Ce*1 Parameters i B 3.8.6 l | |||
BASES | |||
) | |||
SURVEILLANCE Table 3.B.6-1 (continued) | |||
REQUIREMENTS Category C defines the limits for each connected cell. | |||
These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function ) | |||
and maintain a margin of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and the battery must be declared inoperable. | |||
( | |||
The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the i plates suffer no physical damage and maintain adequate I electron transfer capability. The Category C Allowable Value for voltage is based on IEEE-450 (Ref. 3), which states that a cell voltage of 2.07 Y or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement. | |||
The Category C limit on average specific gravity 3 ..!?!), | |||
is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit, it is required that the specific gravity for each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not k overall degradation of the battery. | |||
otnote @ET Table 3.8.6-1 tu t y t: ;;;d 'h | |||
; s;Zy = ) applicable to Category A, 8, and C specific 7 | |||
gravity. Footnote (b) of Table 3.8.6-1 requires the above ln mentioned correction for electrolyte level and temperatute f Ni sne xception Inat levpl correction is not requi ma when ba ery charging curr nt, while on f1 at charge, is | |||
<1 for station serv e batteries an < 0.5 amp for,DG bat ries. This curre provides, in eral, an ind Watio V f overall battery c dition. f j | |||
Because of specific gravity gradients that are produced during the recharging process, delays of several days may occur while waiting for the specific gravity to stabilize. | |||
A stabilized charger current is an acceptable alternative to specific gravity measurement for determining the state of charge of the designated pilot cell. This phenomenon is discussed in IEEE-450 (Ref. 3). Footnote (c) to Table 3.8.6-1 | |||
'mL (Is ApplicaMe. k Castgwy Aa*d C d*tQ ~ | |||
1k (continued) | |||
Z/4 ST: - B 3.8-69 | |||
* 1, 04/07/05 b7 | |||
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.6 BATTERY CELL PARAMETERS NON-BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG-1433 to reflect Fermi 2 current l licensing basis: including design features, existing license requirements and commitments. Refer to CTS Discussion Of Changes to i the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. Additional rewording. reformatting. and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. | |||
P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses. | |||
P.3 Bases changes are made to reflect changes made to the Specification. | |||
Refer to the Specification, and associated JFD if applicable, for additional detail. | |||
P.4 Not used. | |||
lh P.5 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification | |||
" split" criteria found in 10 CFR 50.36(c)(2)(ii). | |||
GENERIC CHANGES C.1 TSTF 278. Rev 0: NRC approved change to NUREG-1433. | |||
J FERMI UNIT 2 1 REVISION 7 06/18/99l i | |||
i | |||
i NO SIGNIFICANT HAZARDS EVALUATION ! | |||
ITS: SECTION 3.8.6 BATTERY CELL PARAMETERS i TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.6 "L.3" Labeled Comments / Discussions) | |||
Detroit Edison has evaluated the proposed Technical Specification change identified as "Less Restrictive" in accordance with the criteria specified by l 10 CFR 50.92 and has determined that the proposed change does not involve a I significant hazards consideration. | |||
The bases for the determination that the proposed change does not involve a significant hazards consideration is an evaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below. | |||
: 1. Does the change involve a significant increase in the probability or ! | |||
consequences of an accident previously evaluated? | |||
The proposed change eliminates the increased frequency of monitoring battery electrolyte temperature after a battery discharge or overcharge. | |||
The DC electrical power sources and this requirement are not an ; | |||
initiator of any previously analyzed accident. Therefore, the change y will have no impact on the probability of an accident previously 1 analyzed. | |||
The ITS LC0 and SRs continue to provide adequate assurance of Operable batteries because a large discharge or overcharge of the battery will tend to heat the battery electrolyte not reduce the temperature. | |||
Therefore, the proposed change does not involve an increase in the consequences of any accident previously evaluated. | |||
: 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated? | |||
This proposed change will not involve any physical changes to plant systems, structures, or components (SSC), or changes in normal plant operation. Therefore this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. | |||
FERMI UNIT 2 5 REVISION 7 06/18/99l | |||
l l | |||
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.6 - BATTERY CELL PARAMETERS TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.6 "L.3" Labeled Comments / Discussions) | |||
: 3. Does this change involve a significant reduction in a margin of safety? | |||
This change does not involve a significant reduction in a margin of ty-safety because a large discharge or overcharge of the battery will tend ) | |||
to heat the battery electrolyte not reduce the temperature. Therefore. 22 the need to increase the frequency of monitoring electrolyte temperature QC is not necessary to assure the battery's capability to perform its safety function. | |||
l l | |||
l l | |||
FERMI UNIT 2 6 REVISION 7 06/18/99l j | |||
, . . .y . . | |||
Distribution Systems-Operating 3.8.7 3.8 ELEC1RICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating l LC0 3.8.7 The following Division I and Division II AC and DC electrical power distribution subsystems shall be OPERABLE: | |||
: a. AC electrical power distribution subsystems: | |||
Division I Division II | |||
: 1. 4160 V Buses 11EA. 12EB 13EC. 14ED 64B. 64C 65E. 65F | |||
: 2. 480 V Buses 72EA. 72EB 72EC. 72ED 72B. 72C 72E. 72F | |||
: 3. 120 V MPU 1 MPU 2 | |||
: b. DC electrical power distribution subsystems: | |||
Division I Division II | |||
: 1. 130 V Distribution 2PA 2 2PB 2 Cabinet | |||
: 2. 260 V MCC 2PA 1 2PB 1 APPLICABILITY: MODES 1. 2. and 3. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required. A.1 Restore AC electrical 8 hours | |||
'AC electrical power power distribution distribution subsystem (s) to 6N_Q subsystems inoperable. OPERABLE status. | |||
16 hours from discovery of failure to meet LC0 (continued) | |||
, } FERMI UNIT 2 3.8 26 Revision 7 06/18/99 i | |||
( . ,- .o ,g[ ;f g ' | |||
Spec t rienTieu 3. 6,7 A.I ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS | |||
(/ AISo (Mg w # A c k s.s'.t ) | |||
m hui[icAS.5,7.7) | |||
Of 5TRIBUT10N OPERATING LIMITING CONDITION FOR OPERATION L.0 0 4.aa.'m The following power distribution system divisions and busses shall be | |||
.'3 | |||
* I O energ>ced41Wtte breaktpf oDen bt(ween reduAhant buspts within EMe unif)L , g | |||
: a. A.C. power distribution: j | |||
: 1. Division 1. sistincLof* | |||
a) 4160V R mple usses llEA and 12EB. | |||
b) 4160V R tor Bu. ina Busses 64B and 64C. | |||
c) 480V Complex usses 72EA and 72EB. | |||
d) 480V eactor B'ut Busses 72B and 72C. | |||
e) 120V Division [] Powp Suppfy unrU MPU 1. | |||
: 2. Division 11. sisting h I a) 4160V mpiex susses 13EC and 14ED. | |||
b) 4160 Re ter Bu Busses 6SE and 65F. | |||
c) 480V R Comple usses 72EC and 72ED. | |||
d) 480V actor i M Busses 72E and_72F. | |||
e) 120Y ptvision 1111W rower suppiy # nit) MPU 2. | |||
" y, YC * | |||
: b. D.C. power distribution: | |||
: 1. Division 1. consisting of: | |||
a) 130 volt D.C. Distribution Cabinet 2PA 2. | |||
b) 260 volt D.C. MCC 2PA 1. | |||
: 2. Division !! consisting of: | |||
a 130 volt D.C. Distribution Cabinet 2PB 2. l b 260 volt D.C. MCC 2PB 1. 1 APPtfCABitfTY: OPERATIONAL CONDITIONS 1, 2 and 3. \ | |||
00: AcT104 D / ,' | |||
ACTION: 0MW ' | |||
a.. With one of the above required A.C. distribution system division - | |||
not energized, reenergize the division within}8'fiours' or be in at \ | |||
riAC3cM g ACTIDM C least HOT SHUTDOWN within the next 12 hours and T CDL SHUTDOWN within the f 24 hours.' [,l bt 4 J^ *% k | |||
: b. With one f the above required D.C. distribution system divisions Q N ON not energized, reenergize the division withindfiobrs~ lor be in at j l ACTiotJ C., least HOT SHUTDOWN within the next 12 hours and inl 6LD SHUTDOWN l | |||
[ within the following 24 hours. | |||
: c. titth the swing bus not energized or the swing bus automatic W- throwcver scheme inoperable, declare both low pressure coolant Spec'eficafiirr 55.l injection (LPCI) system subsystems inoperable and take the ACTION | |||
, required by Specification 3.5.1. l | |||
/ Su ihis ACTION may be delayed for up to 16 hours for A.C. distribution system ' | |||
j' components made inoperable due to loss of EECW cooling providad theI ACTIONS of | |||
'ft&iSicdh. w- Specification 3.7.1.2 are taken. ! | |||
y 17.'L l | |||
FERMI - UNIT 2 3/4814 Amendment No. 29, 80 PAGE L _0F 02 g,g 7 L ) | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.7 - DISTRIBUTION SYSTEMS OPERATING ADMINISTRATIVE A.1 In the conversion of the Fermi 2 current Technical Specifications (CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not result in technical changes (either actual or interpretational). Editorial changes, reformatting, and revised numbering are adopted to make the ITS consistent with the Boiling Water Reactor (BWR) Standard Technical Specifications NUREG 1433. Rev. 1. | |||
IECHNICAL CHANGES MORE RESTRICTIVE M.1 CTS 3.8.3.1. Action a. and CTS 3.8.3.1. Action b. require restoration of the AC electrical power distribution subsystem within 8 hours and restoration of the DC electrical power distribution subsystem within 2 hours: however, there is no limit on overlapping inoperabilities of AC and DC subsystems. ITS 3.8.7 Action A. and ITS 3.8.7 Action B. have the same 8 hour and 2 hour Completion Times, but also establish a maximum time of 16 hours g that any combination of AC and DC electrical power distribution i subsystems fails to meet LC0 3.8.7. Therefore, to place an appropriate restriction on any unusual situation, the additional d | |||
T Completion Time of "16 hours from discovery of failure to meet the LC0" is added. This Completion Time restriction although more restrictive, ensures consistent application of the ITS and therefore, will have no negative impact on safety. | |||
TECHNICAL CHANGES - LESS RESTRICTIVE | |||
" Generic" LA.1 CTS 3.8.3.1 requires power distribution divisions and buses to be | |||
" energized with tie breakers open ", and also includes descriptive information on distribution nomenclature. ITS LC0 3.8.7 relocates specific details of Operability and descriptive information to the j Bases. This is acceptable because these details do not impact the requirement to maintain Operability and the ITS definition for { | |||
i Operability ensures that the buses are energized and not cross I tied. These details can be adequately defined and controlled in l the Bases which require change control in accordance with ITS j 5.5.10. Bases Control Program. These details are not required to i be in the ITS to provide adequate protection of the public health and safety, because these aetails do not impact the requirement to l maintain the equipment Operable. | |||
1 FERMI UNIT 2 1 REVISION 7. 06/18/99l | |||
DISCUSSION OF CHANGES ITS: SECTION 3.8.7 DISTRIBUTION SYSTEMS 0PERATING IfCHNICAL CHANGES LESS RESTRICTIVE "Speci fic" L.1 CTS LC0 3.8.3.1 allows restoration times for one division of AC distribution (8 hours Action a), and one division of DC distribution (2 hours Action b), de energized. ITS 3.8.7 Action A and B, allows one "or more" AC and DC electrical power distribution subsystems to be inoperable for the same times. | |||
respectively. Concurrently, however, ITS Action D is also added to require that if two or more electrical power distribution subsystems are inoperable, resulting in a loss of function, enter LC0 3.0.3 immediately. The combinatior of the "or more" addition to ITS 3.8.7 Actions A and B and the addition of Action D, along with ITS LCO 3.0.6, Safety Function Determination Program, ensure that with the loss of any electrical power distribution system no loss of function will occur without the appropriate action. This presentation will allow the Action A or Action B Completion Time for a portion of one division to be inoperable in conjunction with . | |||
a portion of the second division to be inoperable, provided these M portions do not affect redundant systems required for safe 1 operation. In the event a loss of function exists, ITS Action D ] | |||
will provided actions consistent with the CTS Actions for g inoperabilities in both divisions. Therefore, this less restrictive change will have a negligible impact on safety. | |||
BJLOCATED SPECIFICATIONS None I TECHNICAL SPECIFICATI0t[ BASES The CTS Bases for this Specification have been replaced by Bases that reflect the format and applicable content of ITS 3.8.7 consistent with the BWR STS, NUREG 1433. Rev. 1. | |||
FERMI UNIT 2 2 REVISION 7 06/18/99l | |||
Distribution Systems-Operating 3.8. | |||
3.8 ELECTRICAL POWER SYSTEMS 3.8. V Distribution S st -Operati ud , j [ CTS Y na S.IloA r . | |||
<, _, ,, g LCO 3 vision andbivision AC DC, -{e,M AC';it;l :, ;J t f electrical power distribution su systems shall be OPERA 8LEAh f/t/ SERT 3.8.1-1, y APPLICABILITY: MODES 1, 2, and 3. | |||
1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME O'fk" | |||
.. One or more nc - | |||
fje.) | |||
A.1 Restore AC electrical 8 hours a electrical power power d tion - | |||
distribution subsyst o E subsystems inoperable. OPERABL tus. | |||
16 hours from g discovery of /g,g T , | |||
failure to meet ; | |||
LCO E One or more A vital B.1 MestoreACvital us 2 houri uses inoperabl distribution subiystems to E OPERAh E status, k.I khoursfrom dit very of , | |||
fail to meet ' | |||
LCO i | |||
6 . One no snon- 1 Restore D lectrical 2 hours 5:nvies} DC electrical power d ution g; h power distribution subsyst subsystems inoperable. | |||
E OPERABL tus. | |||
16 hours from u discovery of (Doc M.I) 1 failure to meet << | |||
LCO T (continued) | |||
W.rTS- 3.8-38 n;; 1, 01/07/05 | |||
#cv 7 oc . | |||
s y t | |||
t' | |||
: y. . r - . . . | |||
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ! | |||
ITS: SECTION 3.8.7 DISTRIBUTION SYSTEMS OPERATING NON BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and comitments. Refer to CTS Discussion Of Changes to the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. Additional rewording, reformatting, and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. | |||
P.2 Bases changes ara made to reflect plant specific design details, equiprent terminology. and analyses. | |||
P.3 Not used. | |||
P.4 Fermi CTS details some. but not all. distribution buses in the requirements of CTS LC0 3.8.3.1. The remaining distribution subsystems are inferred to be associated with Operability of individually powered features (as such, they are not allowed the l | |||
" blanket" 8 hours (for AC)/2 hours (for DC) to restore power). ! | |||
ITS reflects the Fermi 2 current licensing basis (CLB). Only l | |||
" primary" AC buses. MPUs. DC distribution cabinets, and DC MCCs l are addressed in ITS LC0 3.8.7: the remainder of the distribution system is directly addressed by Operability of the associated powered features. | |||
P.5 Editorial changes made for clarity. The Bases statement. "..the remaining are capable of supporting the minimum functions " is based on the implicit assumption that Action D is not also entered d (which is required if there is a loss of safety function). 4. | |||
Therefore, these changes simply include this assumption for added clarity. | |||
Q P.6 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification | |||
" split" criteria found in 10 CFR 50.36(c)(2)(ii). l FEPsMI UNIT 2 1 REVISION 7 06/18/99l | |||
1 I | |||
) | |||
l l I JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.8.8 DISTRIBUTION SYSTEMS SHUTDOWN I | |||
l NON BRACKETED PLANT SPECIFIC CHANGES - | |||
P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license j l | |||
requirements and commitments. Refer to CTS Discussion Of Changes to ! | |||
the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. Additional rewording, reformatting, and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. Specifically, some of these changes are discussed as follows: j | |||
: a. An editorial clarification is inserted in the LC0 Bases -- | |||
acknowledging that during shutdown conditions what would 1 otherwise be redundant safety related divisions, may be cross tied. This acknowledgement is provided in the NUREG 1433 k l Bases for Specification 3.8.2, and is similarly added here. | |||
P.2 Not used. | |||
P.3 Not used. | |||
P.4 Editorial correction to Bases to include information consistent with the associated ITS Required Action. | |||
P.5 The reference to the NRC Policy Statenent has been replaced with a more appropriate reference to the Improved Technical Specification 1 | |||
" split" criteria found in 10 CFR 50.36(c)(2)(ii). l l | |||
4 FERMI UNIT 2 1 REVISION 7 06/18/99l j | |||
INSERT THIS PAGE IN FRONT OF VOLUME 11 Volume 11: CTS MARKUP COMPILATION Remove Replace 3/4 3-23 (3.5.1 CTS M/U) pg i of 10 3/4 3-23 (3.5.1 CTS M/U) pg 1 of 10 Rev 7 3/4 4-2 (3.5.1 CTS M/U) pg 2 of 10 3/4 4-2 (3.5.1 CTS M/U) pg 2 of 10 Rev 7 3/4 5-3 (3.5.1 CTS M/U) pg 5 of 10 3/45-3(3.5.1 CTS M/U) pg 5 of 10 Rev 7 3/4 5-3 (3.5.2 CTS M/U) pg 1 of 8 3/4 5-3 (3.5.2 CTS M/U) pg i of 8 Rev 7 3/4 5-4 (3.5.2 CTS M/U) pg 2 of 8 3/4 5-4 (3.5.2 CTS M/U) pg 2 of 8 Rev 7 3/4 5-6 (3.5.2 GS M/U) pg 3 of 8 3/4 5-6 (3.5.2 CTS M/U) pg 3 of 8 Rev 7 3/4 5-8 (3.5.2 CTS M/U) pg 5 of 8 3/4 5-8 (3.5.2 CTS M/U) pg 5 of 8 Rev 7 3/473(3.5.1 CTS M/U) pg 8 of 10 3/4 7-3 (3.5.1 CTS M/U) pg 8 of 10 Rev 7 3/47-5(3.8.1 CTS M/U) pg 1 of 8 3/47-5(3.8.1 CTS M/U) pg i of 8 Rev. 7 3/4 7-5 (3.8.2 CTS M/U) pg 1 of 2 3/4 7-5 (3.8.2 CTS M/U) pg 1 of 2 Rev. 7 3/4 S-1 (3.8.1 CTS M/U) pg 2 of 8 Rev 2 3/4 8-1 (3.8.1 CTS M/U) pg 2 of 8 Rev 7 3/4 8-) (3.8.3 CTS M/U) pg 1 of 5 Rev 2 3/4 8-1 (3.8.3 CTS M/U) pg i of 5 Rev 7 3/48-2(3.8.1 CTS M/U) pg 3 of 8 Rev 2 3/4 8-2 (3.8.1 CTS M/U) pg 3 of 8 Rev 7 3/48-3(3.8.1 CTS M/U) pg 4 of 8 3/48-3(3.8.1 CTS M/U) pg 4 of 8 Rev 7 3/4 8-3 (3.8.3 CTS M/U) pg 2 of 5 3/4 8-3 (3.8.3 CTS M/U) pg 2 of 5 Rev 7 3/4 8-4 (3.8.3 CTS M/U) pg 3 of 5 3/4 8-4 (3.8.3 CTS M/U) pg 3 of 5 Rev 7 3/4 8-7 (3.8.3 CTS M/U) pg 4 of 5 3/4 8-7 (3.8.3 CTS M/U) pg 4 of 5 Rev 7 3/4 8-10 (3.8.6 CTS M/U) pg 1 of 3 Rev 2 3/4 8-10 (3.8.6 CTS M/U) pg 1 of 3 Rev 7 3/4 8-14 (3.8.7 CTS M/U) pg 1 of 2 3/4 8-14 (3.8.7 CTS M/U) pg i of 2 Rev 7 3/4 8-15a (3.5.2 CTS M/U) pg 8 of 8 3/4 815a (3.5.2 CTS M/U) pg 8 of 8 Rev 7 Rev 7 06/18/99 l j | |||
l | |||
e l | |||
SpecaricAmo 2. r.1 \ | |||
b50 54 SpedMCANM 3,3 f.l) | |||
INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMEN ON LIMITING CONDITION FOR OPERATION 6 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2. | |||
APPLICABILITY: As shown in Table 3.3.3-1. | |||
AC.IlQH: | |||
: a. With an ECCS actuation instrumentation channel trip setpoint less 1 i | |||
conservative than the value shown in the Allowable Values column I of Table 3.3.3-2, declare the channel inoperable until the channel i is restored to OPERABLE status with its trip setpoint adjusted g consistent with the Trip Setpoint value, | |||
: b. With one or more ECCS actuation instrumentation channels 3 inoperable, take the ACTION required by Table 3.3.3-1. | |||
Vc eb y | |||
3 ' | |||
: c. With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within: | |||
: 1. 7 days, provided that the HPCI and RCIC systems are OPERABLE, otherwise, | |||
: 2. 72 hours. | |||
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours i and reduce reactor steam dome pressure to less than or equal to l 150 psig within the following 24 hours. l SURVEILLANCE REOUTREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK', CHANNEL FUNCTIONAL TEST and , | |||
CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the i frequencies shown in Table 4.3.3.1-1. l 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of 11 channels shall be performed at least once per 18 months.* | |||
fR35.l.N 4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function ** shall be demonstrated to be within the limit at least once per 18 months. | |||
s fu for the diesel generator output breakers: Completion of logic system | |||
. gym j functional testing, for the loss of power function, to positively verify that the breaker reciosure permissive relay ~(52xx) is re-energized by the SI*"M' 3 associated bus load shedding logic contact closing, rather than the 52XX being re-energized by a parallel path, may be deferred and must be completed no later than during the first plant outage after September 29, 1995. | |||
SR 3.5.t.l y **ECCS actuation instrumentation resonnte time need not be measured and may be 1y poTE (assumeg n De the/ design instrpfhentation respodse time) !i | |||
,k , | |||
v FERMI - UNIT 2 3/4 3 23 Amendment No. Jpp, 195.111 PAGE I 0F 10 8'" 7 | |||
j i | |||
59eD Rc,Fnand 5 6 / l | |||
[dfso sedpecharne 3.% / ) | |||
i REACTOR COOLANT SYSTEM ' | |||
sunVEfttANCE RFOUTREMENTS 4.4.1.1.3 Each pump discharge valve shall be demonstrated OP8RAELE by I g 3.Lt.7 cycling once pereach valve through at least one complete cycle of full travel at least} | |||
18 months. | |||
ll h.l.1.2 DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in Su operation, at least once per 12 hours verify that: ' | |||
See.cdkah%j SSI a. THERMAL POWER is less than or equal to 67.2% of RATED THERMAL POWER, and | |||
: b. The individual recirculation pump flow centroller for the operating recirculation pump is in the Manual mode, and | |||
: c. The speed of the operating recirculation pump is less than y or equal to 754,of rated pump speed. | |||
j 4.4.1.1.4 With one reactor coolant system loop not in operatjon with THERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase: | |||
/ | |||
M \q | |||
: a. Less than or equal to 145"F between reactor vessel steam k"4"gA b. | |||
space coolant and bottom head drain line coolant, and 3.'f. I Less than or equal to 50*F between the reactor coolant | |||
/ | |||
within the loop not in operation and the coolant in the reactor pressure vessel **, and | |||
: c. Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the operating loop.** | |||
Al .- ; | |||
S ta. | |||
Cpec;6ca hm | |||
**Reouirement does not apply when the recirculation loop not ih operation is isolated from the reactor pressure vessel. | |||
3M.c FERMI - UNIT 2 3/440 Amendment No. 53, 69. 87. US.133 M | |||
PAGE $ OF 10 | |||
r 5P&c.IFicAT104 M. l | |||
{hl40 $st Spes\Cce,4,'er. S.c.2) | |||
EMERGENCY CORI? C00llNC SYSTEMS LIMITING COND 'T10N FOR OPERAT10N fContinued) | |||
ACTION: (Continued) | |||
.3. S'. I _ d. For the ADS: (ADO Ac.nouP/ | |||
.2 1. | |||
Mc7 san '3" (HPCI systeaQ Oe~ CSS =dWith N l ec t one of the_ a_bove reanired ADShalve avs*= are OPERABLE, restore the A cyg q inoperaDle ADS valve to OPERABLE status within 16 days or be in at Ac7tod .I . least HOT SHUT 00WN within the next 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours. | |||
/C'TroM I 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTD0WN within 12 hours and reduce reactor steam done pressure.to s 150 psig within the next 24 hours, | |||
: e. / With a CSS h ader AP instrumentation channel inoperable perable, restore bbk annel to OPERABLE status with 72 hours or deters e th CSS head AP lo; ally at least once per hours; otherwise. clare/ | |||
l tthe as ciated CSS subsystem inoperab1 f _ | |||
Ii . ith an LPCI or 5 system discharge line " keep / filled" alm instrumentatio operable. nerform Surveillante RequiremenL/ | |||
[R,) | |||
.5.1.a.l.a. | |||
3 | |||
~ | |||
(g. | |||
the event an tcc5 system is ctuated and injects water into the ~ | |||
I actor Coolant System, a Sp tal Report shall be prep d and submitted to the Commissio pursuant to Specification .9.2 within 90 days describing the circ stances of the actuation the total accumulated actuation c les to date. The current alue of the usage factor for each affec d safety injection nozzle all be provided in i . | |||
Special Report enever its value exceeds .70 E SURVEILtANCE REQUIREMENTS 4.5.1 The emergency core cooling systems shall be demonstrated OPERABLE by: | |||
: a. At least once per 31 days: | |||
: 1. For the CSS, the LPCI system, and the HPCI system: _ _ _ | |||
s g 3 5 1.-3 a) Verifying [by)entino Et the hiah sj.inuent that the system piping from the. pump discharge valve to t e system isciation vai ,e is filled with water. | |||
l | |||
'5R3714- b) Verifying that each valve, manual, power operated or automatic, in the flow path that is not lockedi sealed, or otherwise secured in position, is in its correct | |||
* position. | |||
g g g 3,q ,) 6 2. , | |||
For the LPCI system, verifying that the ross-tie valve is open. | |||
(6/15ESI [iExcept t)tt an autpinatic valve rgpable of automafic return tofts ECCS position g,g,g,4when ar/ECCS standl is presentAay be in positi4n for anothe(mode of operation FERMI . UNIT 2 3/4 5 3 PAGE 5 0F 10 Sgy 7 | |||
1 1 | |||
1 i | |||
( l | |||
-boca bc4 dien. 5.5 2. { | |||
[if/so see specifiedian B.s'.Q l | |||
1 1 | |||
/ I EMERCENCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION Montinuedi ACTIdN: (Continued) | |||
: d. For the ADS: | |||
j | |||
' 1, With one of the above required ADS valves inoperable, provided the HPCI system, the CSS and the LPCI system are OPERABLE, restore the inoperable ADS valve to OPERABLE status within 14 days or be in at l | |||
least HOT SalTDOWN within the next 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours. | |||
: 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam dome pressure to s 150 psig within the next 24 hours. | |||
l | |||
' e. With a CSS header AP instrumentation channel inoperable, restore the l g - | |||
inoperable channel to OPERABLE status within 72 hours or deterinine the CSS header AP locally at least once per 12 hours; otherwise, declare | |||
*g the associated CSS sut' system inoperable. | |||
gi # | |||
3,6,I f. With an LPCI or CSS system discharge line " keep filled | |||
* alarm instrumentation inoperable, perform Surveillance Requirement 4.5.1.a.1.a. | |||
: g. In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Connission pursuant to Specification 6.g.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in l | |||
l this Special Report whenever its value exceeds 0.70. | |||
SVRVElllANCE REOUIREMENTS r | |||
4.5.1 The emergency core cooling systems shall be demonstrated OPERABLE by: | |||
(CC. , | |||
~ | |||
"" a. At least once per 31 days: | |||
$yeC[ | |||
: 1. For the CSS, the LPCI system, and the HPCI, system M. | |||
a) Verifying [by v/ntina at the Idah noint unt0that the system M 3*b'g'q pipin from the pump discharge valve to'the system isolation valve l | |||
is fi led with water. A b) verifying that each valve, manual, power operated or automatic, in 5R 3.5 7,6 the flow path that is ' lot locked, sealed, or otherwise secured in position, is in its correct | |||
* position. | |||
i g ', For the LPCI system, verifying that the cross. tie valve is open. [$,4 2. | |||
S Pf,,. 5.1 | |||
*Exceptfhatanautomati valve capable of automatfor c return to its [CCS po[ tion another mode of oppration. | |||
when ajt ECCS signal is present may be in positi FERMI - UNIT 2 3/4 5 3 PAGE l OF 08 gev 7 | |||
n a . . . .. . . . e | |||
: 4. J'. ..r. . .$ . | |||
. . -. . . . . . u . U... D .L..- | |||
Sp.e cificad io n. 3. 5. 2 l (Als sec speewca-(sn. e. s.O | |||
: 4.1 Eerectury ener con 1HC MYSTEMS SJRVEILLANCE RE 1U1 tEMEN"5 (centinued) l r | |||
4*c.d..g*. g 3. -for the HPCI system, verifying that the HPCI pump flow controller is j g $#c { in the correct position. | |||
3' ' b. Verifying that, when pursuant to Specification 4.0.5: | |||
g 2;'g,g* g 11. The two CSS pumps in,_each subsystem together deve_lsp a, flow of at 1 $_t 6350 come]Qhst~a te:M~We p'ressuce.o" arandr ma oradat | |||
- k Mt.N i i FNfgisiiill'n~g to a reacWr~vesse i pressure of a 100 ' | |||
psig. ___ | |||
i | |||
: 2. Each J.PCI pump in each subsystem develops [ow of at least 10,000 gpe(acaWCTJ61[Ena iWisatref a zJuAsi | |||
~ | |||
asponding to a reactor vessel to ori-m i 6am.a t 6 vii i. . ... , | |||
ressure of a 20 ' | |||
psig. ./O | |||
$CO 3. The HPCI pump develops a flow of at least 5000 gpm in the test flow i path with a system head corresponding to reactor vessel operating | |||
$f *gghof). | |||
3 ,g pressure including injection line losses when steam is being supplied Qotheturbineat 1025 +20. -80 psig.* | |||
: c. At least once per 18 months g.(ud( W" ' | |||
: l. For the CSS, the LPCI system. M d the HPCI systeeD performing a GR 3.C.2 7 system functional test which includes,stmulated automatic actuation g l gg of the systas throughout its emergency operating sequence and l . | |||
verifying that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel may be excluded from this test. | |||
: 2. or the HPCI system, verifying that: | |||
a) The system develops a flow of at least 5000 gpm in the test flow l path with a system head corresponding to reactor vessel operating pressure including injection line losses when steam is being supplied to the , turbine at 165 + 50. ,0 psig.* | |||
u b) The suction for the HPCI system is automatically transferred from gyCC%{'pf/o the condensate storage tank to the suppression chamber on a | |||
$ *g ,) condensate storage tank water level - low si nal and on a suppression chamDer - water level high signa . j | |||
: 3. Performing a CHANNEL CALIBRATION of the CSS and the LPCI system discharge line ' keep filled" alarm instrumentation. | |||
4 Performing a CHANNEL CAllBRATION of the CSS header AP instrumentation and verifying the setpoint to be s the allowable value of 1.0 psid. | |||
$Cd | |||
. rQ,o./ *The provisions of Specification 4.0.4 are not applicable provided the gfrCil surveillance is performed within 12 hours after reactor steam pressure is | |||
~>; ,6 . I - adequate to perform the test. | |||
FEllMI - UNIT 2 3/454 Amendment No. 87 b | |||
c2 PAGE 0F 08 del 7 s | |||
P :. (! # , 6 %.: | |||
l l | |||
L 68ECi Ac+ Weal 5. f.2. | |||
FMFRCENCY CORF cont TE SYETTMS 3/4 5.7 Fres . SHUTDrud A,l l tIMITING CONDITION FOR OPERATION | |||
' / | |||
3.5.2 At least two f the f lowing (subsystemsshallbeOPERABLE: | |||
re spray syst (CSS) subsyst with a subsystem rised of: | |||
f a. ' | |||
: 1. At leas two OPERABLE CS pumps. and | |||
: 2. An OP E flow path apable of taking s tion from at 1 st one f the following ter sources and t nsferring the t Y | |||
~ | |||
h I | |||
- - , . u i .. . = = - ' T L.3 ' T When the suppression chamber water level is less than h l 6ft 3,6,2.'E limit required in Specification 3.5.3 or is drained, com the condensate storage tant with an indicated level of at least.19 ft. | |||
I Low essure coolant in,j ion (LPLO system uusy= 6cr. 6.. . | |||
L(l su ystem comprised of: | |||
At least two OP LE LPCI (RHR) s. and | |||
. An OPERABLE path capable of sking suction from t suppression si2er and transfer ing the water to the/~eactor eta 1** | |||
APPIIrARfITTY: OPERATIONAL CONDITION 4 and $*, | |||
ACIlQli: | |||
Actroa A _,- Witn one of the tbove required subsystem (s) inoperable, restore at least two subsystem (s) to OPERABLE status within 4 hours or suspend ' l AG## g all operations with a potential for draining the reactor vessel. | |||
l | |||
' AcTtod C X ,With Ju='=U:ndboth ofallthe above required operations with a subsystem potential for(s) inoperable, draining the suspen 40Rt | |||
* reactor vessel. Restore at le3st one s nsyntem to OP MABLE 4tatus l | |||
' kG0d g within 4 hours or stabli (SLcDNDARY CNTA NMrMT IWTMRITD%thte | |||
----2 : m- . in;*a . i ., | |||
'--- ach +o ERABLE provided that the ;rt:- = ' | |||
ppl%*ggJ 'l -heart-tr The meinerECCStheiscavity is flooded, the not required to spent fuel pool cates are T | |||
,. removed. and water level is maintained within the limits of(S m F. = m 1 | |||
.2'O | |||
.rl | |||
'd ".: =: :.:.3 | |||
** Ln,1 subsystem (s) may be considered OPERABLE during alionment and operation SR 35.2,6 for decay heat removal if capable of being manually realigned and not l NN otherwise inoperable. | |||
l l | |||
FERMI - UNIT 2 3/4 5 6 Amendment No. 226.131 1 | |||
3 0F 08 PAGE /fev7 | |||
6PECGickno*J 3..& 2-. i (Also 3te Speen(ica% 3.G.2.2b LIMfTING c0NDITION FDR OPERATION 3.5.3 The suppression chamber shall be OPERA 8LE: | |||
f | |||
* 4. a. !n OPERATIONAL CONDITIONS 1, 2, and 3 with a contained water volume of LGo 3,6,2.2. <{atleast 121,000 ft', equivalent to a level of 14'4' (-2 inches 44.3 Qadication). | |||
$A 5.s/2.g b. la OpraA"f m m enuntTtnm A and te trHh a A =#I "duduneofftleadO car umaj ,e ^hlent to afevel (9'0" may 55 <nches <n61 cation), | |||
$4 3,5, t.l.a. 'except that the suppression :- -.i be less than the limit or may be drained provided that: W ACTIDAl 6 -h Nooperationsareperformedthathaveapotentialfordraining) h y | |||
r.Fs 3.5.2.2 b Notf the rtacter vessel actor switch is ked in the 5 downorpdu}e f/( 3,5,2.'7. . b A The condensate storage tank water level is at least 19 ft., and | |||
-4. The core spray system is OPERABLE per Specification 3.5.2 with g g'g*1 an OPERABLE flow path capable of taking suction from the 4 g 3,g ,2 ,') , 6 condensate storace tank ana u .ii. 1, inu uw 6 i snur auray Epaitsi Ao the re86 tor ves . / | |||
/1. | |||
APPLICABILITY: OPERATIONAL CONDITIONS @ 2, 3h4, and 5*} | |||
Eng: k O E*G'2*L l L(D B5,*1. . \ | |||
: a. n OPERATIONAL CONDITION 1. 2, or 3 with the suppression chamber water level less than the above limit, restore the water level to within the 4to 3 4 '2. 2. N I@rslimit and within in CDLDI SHUTDOWN hour or bewinthin 4bowsG at the.4 following 24 leastICSS rs. HOT ancst)SHUTDOWN d. | |||
: b. In OPERATIONAL CONDITION or 5' with the suppression chamber water | |||
/} con) C., O level less than the above limit or rained and iw above reovired ) | |||
conditions not satisfied, suspend wn AutRATIDG andlall operations - | |||
that have a potential for draining the reactor vesse' : ' ': _ ' "" lF r n;t:- - ' :-it:5 i: # ; St:tt r ..... %.; EstaF ish SECONDARY CONTAtaserNT INTKGRIlY= :-- : nrgg li Criifiak che En hV | |||
. 'The suncretnian e"*-r is not required to be OPERASLE provided that the ' | |||
dyactor vessel head is removRDthe cavity is flooded, or being flooded N Igd' ; from the suppression pool, the spent fuel pool gates are .. - .. wnen Ine cavity is flooded. and the water level is maintained within the limits of (Specifications J.p.5 and 3W ' | |||
l FERMI - UNIT 2 3/4 5-8 Amendment No.131 | |||
,,/' | |||
PAGE 5' 0F 08 Rev 7 . | |||
, . . . ~ . . ..,. . . | |||
. . . . . .a SPEctPrcA-nord 54 ( | |||
PLANT SYSTEMS A80 Sg6/Icc I hCdbh-3,7 ) | |||
.. ENERGENCY EDUfPMENT COOLING WATER SYSTEM Al506/-(I0&dhdob*vh8' f | |||
LIMITING CONDITION FOR OPERATION 3.7.1.27wo independent emergency equipment cooling water (EECW) system subsystems shall be OFERABLE with each subsystem comprised of: | |||
: p. 6cag, 'a. One OPERABLE EECW pump, and ge''(;9 b. An OPERABLE flow path capable of removing heat from the assot.iated 3 safety related equipment. | |||
APPLICABILITY: OPERATIONAL CONDIT!DNS 1. 2. 3, 4, and 5. | |||
ACTION: | |||
L | |||
: a. In OPERATIONAL CONDITION 1, 2 or 3, with one EECW system subsystem | |||
, A operable: | |||
5a I | |||
: 1. Within 2 hours: | |||
g.g.g 68 L l a) Verify that all required systems, subsystems, trains, l | |||
((s, components and devices that depend upon the remaining OPERABL? EECW system subsystem are also OPERABLE, and ACTtos tt - | |||
(I b) Verify that M s OPERABLE. /_. Z Otherwise", be in at least H0T SHUTDOWti within the next 12 hours | |||
! 5g and in COLD SHUT 00WN within the following 24 hours. l i | |||
( 5 ptcikc d h . | |||
\ J,7 2. Declare the associated safety-related equipment inoperable and take the ACTIONS required by the applicable Specifications. | |||
Acr7eg C. 3. Restore h =; r:bh EEC" :Ut M ubsystem to OPERABLE status witnin iz nours or be in at least HOT SHUT 00WN within A CT70M O the next 12 hours and in COLD SHUTDOWN within the following 24 hours. | |||
r | |||
: b. I In OPERATIONAL CONDITION 4 or 5, determine the OPERABILITY of the I safety-related equipment associated with an inoperable EECW system | |||
$feci b han subsystem and take any ACTIONS required by the applicable 37 Specifications. | |||
A. | |||
'YI(;gW[;h/ ADS | |||
/ thanis or notequal requiredto 150 to be OPERABLE when reactor steam dome pressure is less PSIG. | |||
"Except for an inoperable Drywell Cooling Unit, required by Specification 4th y 3.7.11 or.an inoperable primary containment oxygen monitoring instrumentation | |||
.Q(A channel, required by Specification 3.3.7 S. that depends ^,n the remaining giu OPERABLE EECW system subsystem. In these cases, take the ACTION required by , | |||
pJ h Specification 3.7.11 for the inoperability of both required Drywell Cooling Units or Specification 3.3.7.5 for the inoperability of both required primary ' | |||
containment oxygen monitoring instrumentation channels. ! | |||
FERMI - UNIT 2 3/4 7 3 Amendment No. # , M ,132 PAGE f 0F 10 gev 7 | |||
, s . .4 . | |||
(; , | |||
I' l 1 G PectF r eertvu 52.l , | |||
9f G6 REmov5D l Y. SEV l l | |||
l l | |||
l | |||
. 1 l | |||
i l | |||
l \ | |||
i l | |||
l | |||
~ | |||
.5 l4- 7-3 | |||
/ | |||
l PAGE OF 08 %7 L | |||
SPET 1 FiCkrtaN 3,Tr. 2 k | |||
e no ess 7 4 | |||
I i | |||
3/47-5 PAGE / OF 02 ggv 7 i | |||
1 l | |||
SPECI'=lCkTroM 3 E l \ | |||
! .3 /4 . 8 ELECTRICAL POWER SYSTEMS | |||
[AlsoSu he b b 5-I3) 3/4.8.1 A.C. SOURCES A.C. SOURCES - OPERATING f,f ) | |||
LIMITING CONDITION FOR OPERATION LLO 3.8 As a minimum, the following A.C. electrical power sources shall be OPE : | |||
: a. Two p..;mmi ind: pend:nt circuits between the offsite l | |||
transmission network and the onsite Class IE distribution system, and LA.l | |||
: b. Two se ate and A depende onsite A.f4 electrical power / sour y , | |||
Div sion I and E_ivision ,[each consisting of two emergency dieselgeneratorsteac diesel generator wu,rg 64 3,$.l Y 1. A separate day fuel tank containing a minimum of 210 gallons | |||
_ of fuel, f g ) 2. A separate fuel storage system containing a minimum of | |||
\ f y, g. 3 | |||
[ 35,280 gallons of fuel, and | |||
. A .ip:re.tc N:1 tr:r, m r ; r;. (p - | |||
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. | |||
ACTION: | |||
: a. With one or both offsite circuits of the above required A.C. | |||
kc.g C electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; . | |||
demonst te the OPERABI Y of the remain a . t. . sources Dy 3 perfo ing Surveillan jit Requirement ast once per 8 ours thereafter dy 4.8 .l.1.withinonegourandJ MD A | |||
kb. With one or both diesel generators in one of the above required onsite A.C. electrical power divisions inoperable; Demonstrate the OPERABILITY of the remaining A.C. sources by b | |||
'l kt h) 1. ' - | |||
performing Surveillance Requirement 4.8.1.1.1 within one l, hour and at least once per 8 hours thereafte pr na if he idie generator (s ~ ecame inoperao aue to any ca eot]er h g | |||
i th an inoperabl support system, independenti testable ' | |||
mponent, or o lanned preventi maintenance testina.1 4 | |||
i Iperforming Surveillance Requirement 4.8.1.1.2.a.4 for one Ref cb Ad.2. ll diesel generator at a time within 24 hours, unless the O c 4 g 'I absence of any potential common mode failure for the / 4.2 \ 1 remaining diesel generators is determined, and lg FERMI UNIT 2 3/4 8-1 Amendment No. pp,119 PAGE L OF 08 BV 7 | |||
.3/4.8 ELECTRICAL POWER SYSTEMS S PE(-IFt cA17orJ E9 3 i 3/4.8.1 A.C. SOURCES [ 4 /50 4 Q tM h 82 N O M 8.8.l ) | |||
A.C. SOURCES - OPERATING | |||
{ | |||
A.I ' | |||
LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power-sourcer shall be OPERABLE: | |||
Two physically indeoendent circuits between the offsite transmission network and the onsite Class IE distribution system, ! | |||
Su and | |||
* bg I | |||
Two separate and independent onsite A.C. electrical power sources, Division I and Division II, each consisting of two emergency diesel generators, each diesel generator with: | |||
: 1. A separate day fuel tank containing a minimum of 210 gallons t of fuel, gR 3.g,3,1 2. A separate fuel storage system containing a minimum of {,l 35,280 gallons of fuel, and habLCO3.3,3 | |||
: 3. A separate tuei transfer pump | |||
/)fgicabilip PPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. M@S CTION: | |||
With one or both offsite circuits of the above required A.C. | |||
electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1. within one hour and at least once per 8 hours thereafter and, g . | |||
With one or both diesel generators in one of the above required g.g onsite A.C. electrical power divisions inoperable; f,$ .l 1. Demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours thereafter, and if the diesel generator (s) became inoperable due to any cause other , | |||
than an inoperable support system, an independently testable ' | |||
component, or preplanned preventive maintenance or testing, by performing Surveillance Requirement 4.8.1.1.2.a.4 for one i diesel generator at a time within 24 hours, unless the aosence of any potential common mode failure for the remaining diesel generators is determined, and FERMI UNIT 2 3/4 8-1 Amendment No, pp,119 PAGE / OF 05 ev7 , | |||
~_ | |||
SPece conou 3.g.: | |||
ElFCTRICAL POWER SYST MS t1MITING CONDITION FOR OPERATION (Continued) | |||
ACTION (Continued) verify within a nours and at least once ar B hours A R | |||
T AaA32. thereafter, that CTG 11 1 15 OPERABLE. testore the fee Ae t 44 inoperable division to OPERABLE status within 7 days or be 19 F in at least HOT SHUTDOWN within the next 12 hours and in Ac770N C COLD SHUTDOWN within the following 24 hours. - | |||
: 3. requirements f ACTION b.2. a! | |||
rIf t be , either re re the inoperab'e)dve for CTG 11-1Aannot) divisiontoOP/RABLEj g,sta within 72 esRnot to exceuo I osys nw uw use Rap Ad 4 6 lthe~ division becdme inoperable): or, satisfy the | |||
, ',!Irequirements of ACTION ).2 above within 72 hours and restore L. | |||
RegAd AS ', lthe inoperable division to OPERABLE status within 7 daysfrom th least HOT SHUTDOWN within the next 12 hours and in COLD k | |||
ANg f)lSHUTDOWN within the following 24 h - | |||
y- __ ___ | |||
: c. With one or both diesel generators i one f the above required onsite A.C. electrical power divi 1 inoperable. in addition toi \ | |||
Ac,t A,2 ' ACTION b above, verify within hours that all required systems Ru/ subrystems, trains. components and devices | |||
* that depend on the L,'2 remaining onsite A.C. electrical power division as a source of emeroency power are also OPERABLE: . wise. oe in at least wi , | |||
g wgn n m ljtnours g inCOLDSlyTDOWNwithi th3 | |||
/ (McLedwe reduk4- h4vn ijsep) | |||
~ | |||
d With both of the above required onsite A.C. electrical power ALTiod b . divisions inoperable: | |||
: 1. Demonstrate the OPERABILITY of the remaining A.C. sources by ! | |||
def M 4'I performing Surveillance Requirement 4.8.1.1.1 within one l F- hour and at least once per 8 hours thereafter: and , | |||
h Acj 6,/ 2. Restore at least one of the above required inoperable 7 - divisions to OPERABLE status within 2 hours or be in at least HOT SHUTDOWN within the next 12 hours'and in COLD Mod C SHUTDOWN within the following 24 hours; and a3 Restore the second of the above required divisions to OPERABLE status within the time required by Action b above | |||
% M n'b . frc;: the time of initial loss or be in at least HOT SHUTDOWN MfDPJC. within the r.ert 12 hours and in COLD SHUTDOWN within the , | |||
following 24 hours. j | |||
* l | |||
*Except for an ino rable primary containment oxygen monitoring l M instrumentation c nnel, required by Specification 3.3.7.5. that 'entis on | |||
.%- the remaining OPERABLE onsite A.C. electrical power division. In is case. | |||
take the ACTION required by Specification 3.3.7.5 for the inoperability of | |||
[v l both required primary containment oxygen monitoring instrumentation channels. | |||
FERMI - UNIT 2 3/4 8 2 Amendment No. 119. 132 i | |||
PAGE S OF 08 g7 l l | |||
l SPEllFicWrland 3 ? l ELECTRICAL POWER SYSTEMS 0 S R h iY '(4 b 8. | |||
SURVElllANCE RE00fREMENTS g y*j, f .6.i.i.c Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be , | |||
determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability. | |||
Each of the above required diesel generators shall be demonstrat | |||
: a. At least once per 31 days p : .:rs:x= = ??I" by: l SR 5.3.1. 9 1. Verifying the fuel level in the day fuel tank. | |||
(5.4.5P ecifitagg,g3g2. ferifyingthefuellevelinthefuelstoragetank. | |||
g g 'j' g 3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the_ day fuel tank. | |||
TR 3 r | |||
* I* 7 319 4. verifying the diesel starts t condition and accelerates to at leastL900 romlin less than or equal to SR 3*1*1'1 10 seconds.* Theegenerator voltage and frequenc 4 4160 s 4ZD volts and 60 a 1.2 Hz Mth'- "' - - y shall be ! | |||
/ t :f':- " _lL | |||
. -* irt : t :'. . _f ih aisses 3.o res snas pu st so to Il r sni test oy usi one of the fo owing signal : | |||
1 a Manual, Simula d loss-of-offs e power by i elf. g,g g i c) Simul ed loss-of-off te power in njunction ith an l ESF tuation test gnal. | |||
d)__ An F actuation t t signal by i elf. - | |||
I s,R 3,g ),3 5. Verifying the diesel generator is synchronized. loaded to | |||
; Lreater than or equal to an indicated 2500 2600 kW in I . . g ,q t --- s a accordance with the manufacturer's recommendations, and i operates wi | |||
%DD Nok 2 is load for at least 60 minutes. | |||
foe NON. 3 f. 3 t ?SNN;);;iltirr""-4 @rC* ='=^' * | |||
(Su $pe(A4cdon 3 3.'5)F7. Verifying the pressure in all diesel generator air start sat..2.na.q'-<.a.u m.-,,,em,q;,mt.a;4 u receivers to be greater th Sit F.R I."1 ##k SR F.31.l4 dok 2-)YAll diesel generator starts for the purpose of this Surveillance Requirement I@ | |||
may As preceded by an engine prelube period. The diesel generatar start 14 3.5 l.7 (10 see) from ambient conditions shall be perforised at least onca JDer __of the purpose 184 inis days sw in these surveillance w.iisance testine may betests. Tallbyother preceded other engine warmue sta:T.s for q { | |||
SE3*I*b%- ' Q# ear gthe dieselnrecedures}ecosamenceafy the manufacturg so tpet the mecyhnical GI V stress aptO fMok 3 enprne is minimized.( - | |||
* Y 4 | |||
FERMI - UNIT 2 3/4 8 3 Amendment No. JJ,107 d 0F PAGE 08 g,, 7 | |||
L 1 l | |||
l 4 | |||
SP w Fickn k 3 2.3 ELECTRICAL POWCR SYSTEMS ' | |||
SURVElllANCE RE0UIREMENTS | |||
.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be determined OPERA 8LE at least once per 7 days by verifying correct breaker alignments and indicated power availability. | |||
4.8.1.1.2 Each of the above required diesel generators shall be demonstrated l QPERABLE-Se4 . a. At least once per 31 days hnMAGGERJJffEST BASI 5j6y: ' >,1 Spati M* + l St 3,g,g ( 1. Verifying the fuel Tever in the day fusi tank.". . **., T gl 2. Verifying the fuel level in the fuel storage tank.ll' | |||
[3. Verifying the fuel transfer pump starts and transfers fuel i from the storage system to the day fuel tank. | |||
I | |||
: 4. Verifying the diesel starts from ambient condition and l accelerates to at least 900 rps in less than or equal to i 10 seconds.* The generator voltage and frequency shall be 4160 a 420 volts and 60 a 1.2 Hz within 10 seconds after the i start signal. The diesel generator shall be started for ; | |||
this test by using one of the following signals: | |||
SeL a) Hanua1. | |||
l Qadf;aM. b) Simulated loss-of-offsite power by itself. | |||
c) Simulated Icss-of-offsite power in conjunction with an | |||
>T. I ESF actuation test signal, d) An ESF actuation test signal by itself. | |||
: 5. Verifying the diesel generator is synchronized, loaded to i greater than or equal to an indicated 2500 2600 kW in ' | |||
accordance with the manufacturer's recommendations, and operates with this lead for at least 60 minutes. | |||
6. | |||
Verifying the diese1' generator is aligned to provide standby power to the associated emergency busses. | |||
: 7. Verifying the pressure in all diesel generator air start 6 A 3. 7. 3,.3 m receivers to be greater than or equal to 215 psig. | |||
FA11 diesel generator starts for the purpose of this Surveillance Requirement g" \ may h preceded by an engine prelube period. The diesel generatar start (10 sec) from ambient ' conditions shall be performed at least gec$tak- onca per 184 days in these surveillance tests. All other engine starts for 39*g the purpose of this surveillance testing may be preced'i by other warmup procedures recommended by the manufacturer so that the Achanical stress and wear on the diesel engine is minimized. | |||
C FERMI - UNIT 2 3/4 8 3 ' Amendment No. JJ.107 | |||
.J PAGE e2 0F 05 jp,g 7 t | |||
b | |||
9 EClP7chT2 bro 2.7 3 | |||
/](so .% SfecdScnfim 5.T.1.) | |||
, ELECTRICAL POWER SYSTEMS g[bo ICL 6 /6CI "C8 l'IM f' ) | |||
SURV[IllaNCE pE00fpFMENTS (Continued) | |||
: b. By removing accumulated water: | |||
fsL 3.3.l\ 1. | |||
QttiHegfM From the day tank at least once per 31 days and after each | |||
/ occasion when the diesel is operated for greater than I hour, and SM 3 2,3,[ 2. From the storage tank at least once per 31 days. | |||
F By sampling new fuel oil in accordance with ASTM D4057-88 prior to MId* ' ' ., c . addition to the storage tanks and: | |||
{k i | |||
l g 'g - 1. By verifying in accordance with the tests specified in ASTM D975 91 prior to addition to the storage tanks that the i | |||
l | |||
: -sample has. | |||
( | |||
se<.5'Cscab- a) An API Gravity of within 0 3 degrees at 60*F or a P specific gravity of within 0.0016 at 60/60'F, when f.E compared to the supplier's certificate or an absolute specific gravity at 60/60'F of greater than or equal i to 0.83 but less than or equal to 0.89 or an API 1 gravity at 60'F of greater than or equal to 27 degrees but less than or equal to 39 degrees, b) A kinematic viscosity at 40'C of greater than or equal l to 1.9 centistokes, but less than or equal to ; | |||
4.1 centistokes, if gravity was not determined by ; | |||
comparison with the supplier's certification. ' | |||
c) A flash point equal to or greater than 325'F, and l d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176 66. | |||
: 2. By verifying within 31 days of obtaining the sample that the other properties specified in Tabla 1 of ASTM D975 91 are met when tested in accordance with ASTM D975 91. | |||
: d. At least once every 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276 88, and verifying that total particulate contamination is less than 10 mg/ liter when Mharted in accordance with ASTM D2276 88, Method A. | |||
(e. At least once per 18 months by: l M 1. Subjecting the diesel to an inspection in accordance with Qecj(icahd y procedures prepared in conjunction with its manufacturer's reconsnendations for this class of standby service. | |||
- FEPJil - UNIT 2 3/4 B-4 Amenoment No. # , 95 PAGE 3 0F 05 Re 7 | |||
- 3: | |||
bPEG lF ICAT1otJ 3. 2.3 Ako Su. spwRca+;qe 3.g.\) | |||
ELECTRICAL POWER SYSTEMS | |||
, SURVFillANCF REOUTREMENTS (Continued) | |||
M | |||
: f. At least once per 10 years or infter any modifications whien could affect diesel generator interdependence by starting all four Spe.cS6Ng diesel enerators simultaneously, during shutdown, and verifying 3* g' g that al four diesel generators accelerate to at least 900 rps in 1 | |||
less than or equal to 10 seconas. | |||
Al i< a .,;.;; ;;r ^ ;;,r; 5;;: / 4*/ | |||
1 Draining a fuel oil stora tank, removing a accumula sed =a h u.. . . a . .. ..,iment and c aning the tank f :.r; | |||
,,_....a... ....u...-... | |||
$ 4. 2. Performing a pressure test of those portions of the diesel Spcib b fuel oil system designed to section !!I. subsection no of 3, g, l the ASME Code in accordance with ASME Code Section 11 i Article IWD 5000. | |||
1 (4,. 8.1.1. 3 Reeerts - Not Used l | |||
l l | |||
l l | |||
l 1 | |||
i i | |||
l FERMI - UNIT 2 3/4 B-7 | |||
- Amendmnent No.107 PAGE OF 05, | |||
&v7 L ! | |||
r | |||
] | |||
i ELECTR1 CAL POWER SYSTEHS 3/4.8.2 D.C. SOURCES Qgc I ft (A TID'J 33'Io D.C. SOURCES - OPERATING g g.f. g g g,g q | |||
{Afso Set .SpeciflOa fidrs 3. ? 2b LIMITING CONDITION FOR OPERATION i | |||
(3.8.2.1 As a minimum, the following D.C. electrical power sources shall be ! | |||
OPERABLE: | |||
a . .. Division 1. consisting of: { | |||
: 1. 130 VDC Battery 2A-1. i | |||
: 2. 130 VDC Battery 2A-2. | |||
: 3. Two 130 VDC full. capacity chargers. | |||
: b. Division 11, consisting of: | |||
,1. 130 VDC Battery 28-1. | |||
: 2. 130 VDC Battery 28-2. | |||
! 3. Two 130 VDC full capacity chargers. | |||
ApptfCABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. | |||
. gd' ACTION: | |||
1 .QP 8Aw. a | |||
\h I | |||
With a battery charger in either Division I or Division II of the above D.C. electrical power sources inoperable, restore the inoperable battery charger to OPERABLE status or replace with the spare battery charger within in COLD4SHUTDOWN hours or be in the within at following least HOT SHUTDOWN within the next 12 hours 24 hours. | |||
b. | |||
With either Division I or Division II of the above required D.C. | |||
electrical power sources otherwise inoperable restore the inoperable division to OPERABLE status within 2 hours or,be in at least HOT SHUTDOWN hours.#within the' next 12 hours and in COLD SHUTDOWN within the following 24 SURVEftlANCF REOUTREMENTS 4.8.2.1 tdemonstrated OPERABLE: /Each of the above required 130-volt batteries and char a. | |||
At least once per 7 days by verifying that: | |||
5 A 3.3.t.. l 1. | |||
The and parameters in Table 4.B.2.1-1 meet the Category A limits, S te. - | |||
s pG kea km y.s. | |||
volts for Division I and greater than or equal to '125.7 vo for nivision 11 on float charge. | |||
: b. 2Ll how.S3; l At least once per 92 dals/and within 7 s La er | |||
[,\ | |||
[di~scTarge ' wit _h 5atTe_ry terminal volta tery N b 8 i attery overcharge with battery terminal voltageathan105 volts,orh gg r ijo 1 and greater than 145 volt eater than 150r Division II, y I | |||
l 6A 3.f.0,1 1. %_fw sa3.s+.O L. l The parameters in Table 4.8.2.1-1 meet the Category B limits, | |||
, 1 i | |||
* 1 lhis ACTION may be delayed for up to 16 hours for battery 3.7.1.2 are taken. | |||
FER(MI-UNIT 2M IpebNm 37.2) | |||
~ | |||
3/4 B.10 Amendment No. 80,121 PAGE 1 ._ QF 03 R" 7 | |||
1 I | |||
SPEO nen erJ 3. E 7 ELECTRICAL POWEp SYSTEMS p,l AISo sex Spuificak, s. g. j ) l 3/4 8 3 ONSITE POWER DISTRIBUTION SYSTEMS g g g ; f,.cg,g, 3,7, t} | |||
D15"R BUTION - OPERATING L"M T NG CONDITION FOR OPERATION l.00 -3.2.3.1 1he following power distribution system divisions and busses shall be 3 50 enero>ceop,itivise creakeos open b,(ween reoumeant busses witnin we unip pj | |||
: a. A.C. power distribution: | |||
: 1. Division I, s i s t i na__ o f- - | |||
-} | |||
a) 4160V HR mple sses 11EA and 12EB. | |||
b) 4160V R ter Bu Busses 648 and 64C. | |||
c) 480V Ccmply usses 72EA and 72EB. | |||
d) 480V eactor Fu Busses 72B and 72C. i e) 120V Division U Powpt Supp/y unrU MPU l. I | |||
: 2. Division !!, nsisting of:/ | |||
a) 4160V mpiex susses 13EC and 14ED. | |||
b) 4160 Re ter Bu Busses 65E and 65F. | |||
c) 480V R Comple usses 72EC and 72ED. | |||
d) 480V actor i Busses 72E and_72F. 4 e) 120V Division 1111_& rower suppiy # nit) MPU 2. I | |||
'h y, V | |||
: b. D.C. power distribution: | |||
: 1. Division 1, consisting of: I a) 130 volt D.C. Distribution Cabinet 2PA 2. | |||
b) 260 volt D.C. MCC 2PA 1. | |||
: 2. Division 11, consisting of: i a) 130 volt D.C. Distribution Cabinet 2PB-2. ! | |||
b) 260 volt D.C. MCC 2PB 1. | |||
APPLICABillTY: OPERATIONAL CONDITIONS 1, 2, and 3. \ | |||
60: A cT10^l D J ,' | |||
l ACTION: -oLNC _ | |||
l a. With one of the above required A.C. distribution s_ystem division N | |||
fb A | |||
NCMDd g not energized, reenergize the division withinlB'60urs' or be in at l | |||
least HOT SHUTDOWN within the next 12 hours and'Tn' COLD SHUTDOWN i l /lCT70tdC within the fo 24 hours.' L,) i i g_rne(f, * | |||
: b. With one of The above required D.C. distribution system divisions N ON b not energized, reenergize the division withint[6oTSs~ lor be in at ACTioA) C least HOT SHUTDOWN within the next 12 hours and in~16LD SHUTDOWN within the following 24 hours, | |||
: c. [ With the swing bus not energized or the swing bus automatic I i'4 / throwover scheme inoperable, declare both low pressure coolant - | |||
Sec'efice hirr 55.l 1 injection (LPCI) system subsystems inoperable and take the ACTION | |||
< required by Specification 3.5.1. | |||
/ g j'coponentsThis ACTION may l < m made inoperable duebete delayed loss of EECW for upcooling to 16 provided hours fortheA.C. distribution ACTIONS of system I | |||
*/M. M. | |||
3,7 2. | |||
) Specification 3.7.1.2aretaken. | |||
i l g | |||
FERMI - UNIT 2 3/4 8 14 Amendment No. 29, 80 s | |||
l PAGE < | |||
OF 02 gg7 | |||
O C/ /C.Q f /0 [L * . - | |||
CAlso =ee specWictison ? a 8) | |||
FtECTRICAL POWER SYSTEMS ' | |||
CC"C . | |||
$URVEf tLANCE pf001REMENTS / | |||
crecScdo.ch 38.8} | |||
Sp' 3.5.2.3 4 .a.3.2. t least th aboverecuiradpoussdistributionsystemdivisions)and the swing bus shals ce outermined energized at least once per 7 days by ' 'l verifying correct breaker alignment and voltage on the busses / cabinets, f4.8.3. 2 The A.C. power distriovita system swt g bus automatic throw sch shall be demonstr ted OPERABLE at least ce per 31 days by man 11y * [f3 ope og position 3C bu 72C and verifying tha he automatic transfer scheme , | |||
ates. , , | |||
l I | |||
l i | |||
l FERM] . UNIT 2 3/4 B-15a Amenoment No. 29 PAGE 2T OF 08 | |||
n ; | |||
l INSERT THIS PAGE IN FRONT OF VOLUME 12 Volume 12: IMPROVED TECHNICAL SPECIFICATIONS l Remove Replace 3.5.1 ITS pg 3.5-3 Rev 0 3.5.1 ITS pg 3.5-3 Rev 7 j 3.5.1 ITS pg 3.5-4 Rev 0 3.5.1 ITS pg 3.5-4 Rev 7 3.5.1 ITS pg 3.5-5 Rev 0 3.5.1 ITS pg 3.5-5 Rev 7 3.5.1 ITS pg 3.5-6 Rev 0 3.5.1 ITS pg 3.5-6 Rev 7 ! | |||
3.5.1 ITS pg 3.5-7 Rev 0 3.5.1 ITS pg 3.5-7 Rev 7 3.5.1 ITS pg 3.5-8 Rev 0 3.5.2 ITS pg 3.5-8 Rev 7 3.5.2 ITS pg 3.5-9 Rev 0 3.5.2 ITS pg 3.5-9 Rev 7 l | |||
1 l 3.5.2 ITS pg 3.5-10 Rev 0 3.5.2 ITS pg 3.5-10 Rev 7 ' | |||
3.5.2 ITS pg 3.5-11 Rev 0 3.5.2 ITS pg 3.5-11 Rev 7 l 3.5.2 ITS pg 3.5 12 Rev 0 3.5.3 ITS pg 3.5-12 Rev 7 j 3.5.3 ITS pg 3.5-13 Rev 0 3.5.3 ITS pg 3.5-13 Rev 7 3.5.3 ITS pg 3.5-14 Rev 0 3.5.3 ITS pg 3.5-14 Rev 7 3.5.3 ITS pg 3.5-15 Rev 0 -- | |||
3.8.1 ITS pg 3.8-1 Rev 0 3.8.1 ITS pg 3.8-1 Rev 7 3.8.1 ITS pg 3.8-2 Rev 0 3.8.1 ITS pg 3.8-2 Rev 7 l | |||
l 3.8.1 ITS pg 3.8-3 Rev 0 3.8.1 ITS pg 3.8-3 Rev 7 3.8.1 ITS pg 3.8-4 Rev 0 3.8.1 ITS pg 3.8-4 Rev 7 3.8.1 ITS pg 3.8-6 Rev 0 3.8.1 ITS pg 3.8-6 Rev 7 l 3.8.3 ITS pg 3.8-13 Rev 0 3.8.3 ITS pg 3.8-13 Rev 7 3.8.3 ITS pg 3.8-14 Rev 0 3.8.3 ITS pg 3.8-14 Rev 7 3.8.3 ITS pg 3.8-15 Rev 0 3.8 3 ITS pg 3.8-15 Rev 7 3.8.4 ITS pg 3.8-17 Rev 1 3.8.4 ITS pg 3.8-17 Rev 7 3.8.6 ITS pg 3.8-22 Rev 0 3.8.6 ITS pg 3.8 22 Rev 7 3.8.6 ITS pg 3.8-23 Rev 0 3.8.6 ITS pg 3.8-23 Rev 7 3.8.7 ITS pg 3.8-26 Rev 0 3.8.7 ITS pg 3.8-26 Rev 7 1 | |||
1 Rev 7 06/18/99 | |||
ECCS-Operating l | |||
3.5.1 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME H. One ADS valve H.1 Restore ADS valve to 72 hours inoperable. OPERABLE status. | |||
SNQ gg D Condition A or . H.2 Restore low pressure 72 hours A Condition B entered. ECCS injection / spray | |||
-4 subsystem (s) to OPERABLE status. | |||
I. Two or more ADS valves I.1 Be in MODE 3. 12 hours inocerable. | |||
AN_Q DB I.2 Reduce reactor steam 36 hours Required Action and dome pressure to associated Completion 5 150 psig. | |||
Time of Condition E. | |||
F. G. or H not met. | |||
J. Two or more low J .1 -' Enter LC0 3.0.3. Immediately pressure ECCS injection / spray ; | |||
subsystems ino)erable ; | |||
for reasons otwr than i Condition B or C. ! | |||
08 HPCI System and one or mort ADS valves | |||
' inoperable. | |||
k Condition C and Condition G entered. . | |||
l FERMI UNIT 2 3.5 3 Revision 7 06/18/99 | |||
l ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE- FREQUENCY SR 3.5.1.1 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. | |||
SR 3.5.1.2 - ------ - | |||
- - - NOTE --- - - --- - | |||
When LPCI is placed in an inoperable status solely for performance of this SR. or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG 12 being paralleled to the bus for required testing, entry into Conditions and Required Actions | |||
'Y l may be delayed up to 12 hours for completion of the required testing. | |||
Perform a functional test of the LPCI swing 31 days bus automatic throwover scheme. | |||
SR 3.5.1.3 Verify for each ECCS injection / spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve. | |||
(continued) l FERMI - UNIT 2 3.5 4 Revision 7 06/18/99 | |||
i i | |||
l ECCS -Operating l 3.5.1 l i | |||
SURv tILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY l | |||
SR 3.5.1.4 ---- --- --- | |||
----NOTE------- - - -------- l Low pressure coolant injection (LPCI) l | |||
- subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3. and for 4 hours after exceeding the RFR cut in permissive pressure in MODE 3. | |||
if capable of being manually realigned and not otherwise inoperable. | |||
Verify each ECCS injection / spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | |||
SR 3.5.1.5 Verify primary containment pneumatic supply 31 days pressure is = 75 psig. | |||
SR 3.5.1.6 Verify the RHR System power operated cross 31 days tie valve is open. | |||
SR 3.5.1.7 04l Verify each recirculation pump discharge valve cycles through one complete cycle of 18 months full travel or is de energized in the closed position. | |||
(continued) i j FERMI UNIT 2 3.5 5 Revision 7. 06/18/99 I j | |||
I 1 | |||
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ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR. 3.5.1.6 Verify the following ECCS pumps develop the In.accordance specified flow rate against a system head with the corresponding to the specified reactor Inservice ! | |||
pressure. Testing j SYSTEM HEAD Program N0. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray a 6350 gpm 2 = 100 psig LPCI = 10.000 gpm 1 a 20 psig | |||
.SR 3.5.1.9 - -- ------- - | |||
NOTE- - ---- - --- | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify with reactor pressure 51045 and In accordance a 945 psig, the HPCI pump can develop a with the flow rate a 5000 gpm against a system head Inservice corresponding to reactor pressure. Testing Program i | |||
SR 3.5.1.10 - --- -- | |||
NOTE- --- ---- - - | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify with reactor pressure s 215 psig. 18 months the HPCI pump can develop a flow rate a 5000 gpm against a system head corresponding to reactor pressure. | |||
(continued) a g l FERMI - UNIT 2 3.5-6 Revision 7 06/18/99 | |||
ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.5.1.11- - | |||
- . -. - - - NOTE- --- - -- - --- - | |||
Vessel injection / spray may be excluded. | |||
Verify each ECCS injection / spray subsystem 18 months actuates on an actual or-simulated automatic initiation signal. | |||
SR 3.5.1.12 -- .- | |||
- .. - - - NOTE - ---- - - - | |||
Valve actuation may be excluded. | |||
Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal. | |||
SR 3.5.1.13 - -------- | |||
NOTE - ----- -- -- - | |||
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. | |||
Verify each ADS valve opens when manually 18 months actuated. | |||
SR'3.5.1.14 '- - . | |||
-NOTE- -- - - - -- - | |||
ECCS instrumentation response times are not required to be measured. | |||
Verify ECCS RESPONSE TIME.is within limits. 18 months J | |||
)! FERMI UNIT 2 3.5 7 Revision 7 06/18/99 | |||
. 1 ECCS-Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2' ECCS-Shutdown LCO 3.5.2 Two low pressure ECCS. injection / spray subsystems shall be . | |||
OPERABLE. | |||
l APPLICABILITY: MODE 4 MODE 5. except with the spent fuel storage pool gates i removed and water level = 20 *t 6 inches over the top of ' | |||
the reactor pressure vessel i nge. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l | |||
A. One required ECCS A.1 Restore required ECCS 4 hours injection / spray injection / spray subsystem inoperable. subsystem to OPERABLE status. | |||
B. Required Action and 8.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not' met. draining the reactor vessel (0PDRVs). | |||
C. Two required ECCS C.1 Initiate action to Immediately injection / spray suspend OPDRVs. | |||
subsystems inoperable. | |||
ANQ C.2 Restore one ECCS 4 hours injection / spray subsystem to OPERABLE status. | |||
(continued) hlFERMIUNIT2 3.5 8 Revision 7. 06/18/99 | |||
( ECCS-Shutdown 3.5.2 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary ! | |||
Completion Time net containment to , i met. OPERABLE status. | |||
M D.2 Initiate action to Immediately restore one standby l gas treatment I subsystem to OPERABLE status. | |||
m D.3 Initiate action to Immediately restore isolation ! | |||
capability in each required secondary containment | |||
' penetration flow path not isolated. | |||
i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify for each re 12 hours | |||
. coolant injection (quired LPCI) low pressure subsystem, the suppression pool water level is a -66 inches. | |||
(continued) h l FERMI UNIT 2 3.5-9 Revision 7 06/18/99 | |||
ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued) | |||
SURSEILLANCE FREQUENCY SR 3.5.2.2 Verify. for each required core spray (CS) 12 hours subsystem, the: | |||
: a. Suppression pool water level is | |||
= 66 inches: or | |||
: b. - ---- -- ---- --NOTE- - - ---------- | |||
Only one required CS subsystem may take credit for this option during OPDRVs. i Condensate storage tank water level is l = 19 ft. | |||
l I | |||
SR 3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. | |||
I SR 3.5.2.4 Verify, for each required ECCS injection / 31 days spray subsystem. the piping is filled with water from the pump discharge valve to the injection valve. | |||
1 (continued) l FERMI UNIT 2 3.5 10 Revision 7 06/18/99 | |||
n , | |||
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ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.5.2.5 - --- | |||
--- NOTE- - - - -- | |||
OA-l LPCI subsystem (s) may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. | |||
Verify each required ECCS injection / spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | |||
Ogl SR 3.5.2.6 Verify each required ECCS pump develo)s the specified flow rate against a system lead In accordance with the corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program N0. CORRESPONDING 0F TO A REACTOR SYSTEM FLOW RATE Pt)MPS PRESSURE OF CS = 6350 gpm 2 = 100 psig LPCI = 10.000 gpm 1 = 20 psig SR 3.5.2.7 : - -- | |||
NOTE-- -- -- -- - | |||
Vessel injection / spray may be excluded. | |||
Verify each required ECCS injection / spray 18 months subsystem actuates on an actual or simulated automatic initiation signal. | |||
l FERMI - UNIT 2 3.5 11 Revision 7. 06/18/99 | |||
i RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING ' | |||
l (RCIC) SYSTEM 3.5.3 RCIC System LC0 3.5.3 .The RCIC-System shall be OPERABLE. | |||
APPLICABILITY: MODE 1. | |||
MODES 2 and 3 with reactor steam dome pressure > 150 psig. | |||
ACTIONS CONDITION ' REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant 1 Injection System is l OPERABLE. | |||
8N_Q A.2 Restore RCIC System 14 days to OPERABLE status. | |||
B. Required Action and B.1- Be in MODE 3. 12 hours associated Completion Time not met. 6NQ B.2 Reduce reactor steam 36 hours i dome pressure to s 150 psig. | |||
4 l- FERMI - UNIT 2 3.5 12 Revision 7 06/18/99 | |||
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RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS , | |||
1 SURVEILLANCE FRE0VENCY l SR 3.5.3.1. Verify the RCIC System piping is filled 31 days l with water from the pump discharge valve to the injection valve. . | |||
SR 3.5.3.2 . Verify each RCIC System manual._ power 31 days operated, and automatic valve 'in the flow path. that is not locked, sealed, or otherwise secured in position, is in the correct position. | |||
l SR ~3.5.3.3 | |||
-- - - - -- - NOTE ------- -- | |||
'Not required to be performed until 12 hours | |||
' after reactor steam pressure and flow are adequate to perform the test. | |||
Verify, with reactor pressure s 1045 psig 92 days and a 945 psig. the RCIC pump can develop a flov rate = 600 gpm against a system head-cor p;onding to reactor pressure. | |||
SR 3.5.3.4 - - - | |||
- NOTE---- - - - --- - | |||
Not. required to be performed until 12 hours aft.er reactor steam pressure and flow are adequate to perform the test. | |||
Verify,' with reactor pressure s 200 psig. 18 months the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure. | |||
(continued) | |||
/PJ' FERMI--UNIT;2 3.5 13- Revision 7 06/18/99 l | |||
t RCIC System l 3.5.3 1 | |||
l SURVEILLANCE REQUIREMENTS '(continued) 1 SURVEILLANCE | |||
, FREQUENCY l | |||
e SR 3.5.3.5 - -- - -- | |||
- - - NOTE ---- --- - ---- -- | |||
Vessel injection may be excluded. | |||
~ | |||
l l | |||
Verify the RCIC System actuates on an 18 months actual or simulated automatic initiation signal . | |||
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)l FERMIUNIT 2: 3.5 14 Revision 7 06/18/99 L. | |||
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l AC Sources-0perating ! | |||
3.8.1 j 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating l LC0 3.8.1 . The following AC electrical power sources shall be OPERABLE: | |||
: a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and | |||
: b. Two emergency diesel generators (EDGs) per division. | |||
l 1 | |||
APPLICABILITY: MODES 1. 2. and 3. | |||
l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I | |||
A. . One or both EDGs in A.1 Perform SR 3.8.1.1 1 hour one division for OPERABLE offsite , | |||
inoperable. circuit (s). MQ Once per 8 hours thereafter MQ A.2 Declare required 4 hours from feature (s). su) ported discovery of an by the inopera)1e inoperable EDG EDGs. inoperable when concurrent with the redundant inoperability of required feature (s) redundant are inoperable. required feature (s) | |||
MQ A.3 Verify the status of Once per 8 hours | |||
} CTG 11 1. | |||
k @ | |||
(continued) l FERMI UNIT 2 3.8-1 Revision 7 06/16/99 | |||
l AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4.1 Determine OPERABLE 24 hours dl EDG(s) are not inoperable due to common cause failure. | |||
l A.4.2 Perform SR 3.8.1.2 24 hours for OPERABLE EDG(s). | |||
~i 5 | |||
6 A.5 Restore availability of CTG 11 1. | |||
72 hours from discovery of Condition A concurrent with CTG 11-1 not available V i l A.6 Restore both EDGs in 7 days the division to OPERABLE status. | |||
B. One or both EDGs in B.1 Restore both EDGs in 2 hours both divisions one division to inoperable. OPERABLE status. | |||
C. One or two offsite C.1 Be in MODE 3. 12 hours circuits inoperable. | |||
E @ | |||
Required Action and C.2 Be in MODE 4. 36 hours Associated Completion Time of Condition A or B not met. | |||
l FERMI UNIT 2 3.8 2 Revision 7 06/18/99 | |||
l AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days. | |||
indicated power availability for each offsite circuit. | |||
SR 3.8.1.2 -- -- | |||
-------...--NOTES----- --- - ----- | |||
: 1. All EDG starts may be preceded by an | |||
'@ l engine prelube period and followed by a warmup period prior to loading. | |||
: 2. A modified DG start involving idling h and gradual acceleration to synchronous speed may be used for this 6 | |||
4 SR as recommended by the manufacturer. l Verify each EDG starts and achieves steady 31 days state voltage a 3740 V and s 4580 V and frequency a 58.8 Hz and s 61.2 Hz. | |||
SR 3.8.1.3 - - | |||
-- NOTES - - - - --- | |||
: 1. EDG loadings may include gradual | |||
. loading as recommended by the manufacturer. | |||
: 2. Homentary transients outside the load range do not invalidate this test. | |||
: 3. lhis Surveillance shall be conducted on only one EDG at a time. | |||
Verify each EDG is synchronized and loaded 31 days and operates for a 60 minutes at a load a 2500 kW. | |||
(continued) l FERMI UNIT 2 3.8 3 Revision 7 06/18/99 | |||
AC Sources-Operating | |||
, 3.8.1 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains = 210 gal of 31 days , | |||
fuel oil. ' | |||
i i | |||
SR -3.8.1.5 Check for and remove accumulated water from 31 days each day tank. | |||
SR 3.8.1.6 Verify each fuel oil transfer system 31 days operates to automatically transfer fuel oil from storage tanks to the day tanks. | |||
SR 3.8.1.7 - ---- ---- - - | |||
- NOTE-- -- - - ------- | |||
s All EDG starts may be preceded by an engine T prelube period and followed by a warmup | |||
.4 g-period prior to loading. | |||
Verify each EDG starts from standby 184 days condition and achieves: | |||
: a. In s 10 seconds, voltage a 3740 V and frequency a 58.8 Hz: and l | |||
: b. Steady state voltage = 3740 V and 5 4580 V and frequency a 58.8 Hz and 5 61.2 Hz. | |||
i SR 3.8.1.8 Verify each EDG rejects a load greater than 18 months or equal to its associated single largest I post accident load, and following load rejection, the frequency is s 66.75 Hz. l l | |||
(continued) l FERMI UNIT 2 3.8-4 Revision 7. 06/18/99 j | |||
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS Jcontinued) | |||
SURVEILLANCE FREQUENCY SR 3.8.1.11 ----- - - | |||
---NOTE ---- -- - - - - | |||
All EDG starts may be preceded by an engine prelube period. | |||
Verify on an actual or simulated Emergency 18 months Core Cooling System (ECCS) initiation signal each EDG auto starts and: , | |||
l | |||
: a. In s 10 seconds after auto start and during tests, achieves voltage jl = 3740 V and frequency a 58.8 Hz: | |||
0 b. Achieves steady state frequency 4 a s4 hV an ! | |||
jl c. Operates for a 5 minutes. | |||
SR 3.8.1.12 Verify each EDG's automatic trips are 18 months bypassed on an actual or simulated ECCS initiation signal except: | |||
: a. Engine overspeed: | |||
: b. Generator differential current: | |||
: c. Low lube oil pressure: | |||
: d. Crankcase overpressure; and | |||
: e. Failure to start. | |||
(continued) ! | |||
l I | |||
I I FERMI - UNIT 2. 3.8-6 Revision 7 06/18/99 J | |||
@[ Diesel Fuel Oil and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS | |||
@ l 3.8.3 Diesel Fuel Oil and Starting Air 3.8.3 The stored diesel fuel oil and starting air subsystem shall | |||
@ l LC0 be within limits for each required emergency diesel generator (EDG). | |||
APPLICABILITY: When associated EDG is required to be OPERABLE. | |||
ACTIONS | |||
..................................---NOTE- - --- - ------ - - - - --- - -- | |||
Separate Condition entry is allowed for each EDG. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore fuel oil 48 hours EDGs with fuel oil level'to within level < 35.280 gal and limits. | |||
> 30.240 gal in storage tank. | |||
B. One or more required B.1 Restore fuel oil 7 days EDGs with stored fuel total particulates to oil total particulates within limit. | |||
not within limit. | |||
dl C. One or more required C.1 Restore stored fuel 30 days EDGs with new fuel oil oil properties to properties not within within limits. | |||
limits. | |||
(continued) l l FERMI UNIT 2 3.8-13 Revision 7 06/18/99 | |||
1 l | |||
rnl Diesel Fuel Oil and Starting Air | |||
.& 3.8.3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME i | |||
Required Action and D.1 Declare associated Immediately Ql D. | |||
associated Completion EDG inoperable. | |||
Time not met. | |||
.QB One or more required , | |||
EDGs with diesel fuel ' | |||
Ol W/ | |||
oil, or starting air subsystem not within l | |||
limits for reasons other than hl Condition A, B, or C. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each required EDG fuel oil storage 31 days tank contains = 35.280 gal of fuel. | |||
l . SR 3.8.3.2 Verify each required EDG fuel oil In accordance properties of new and stored fuel oil are with the tested in accordance with, and maintained Emergency within the limits of. the Emergency Diesel Diesel Generator Fuel Oil Testing Program. Generator Fuel Oil Testing Program (continued) | |||
J l FERMI UNIT 2 3.8-14 Revision 7.. 06/18/99 m | |||
hl- Diesel Fuel Oil and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)' | |||
SURVEILLANCE FRE0VENCY SR 3.8.3.3- . Verify each required EDG air start receiver 31 days Ok l . pressure is a 215 psig. | |||
[l SR 3.8.3.4 Check for and remove accumulated water from 31 days each required EDG fuel oil storage tank. | |||
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s 1 FERMI. UNIT 2- 3.8 15' Revision 7. 06/18/99 | |||
r DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY m SR 3.8.4.-l' Verify battery terminal voltage is a 130 V 7 days for Division I and = 125.7 V for D Division II on float charge. | |||
6 SR 3.8.4.2- Verify no visible corrosion at battery 92 days terminals and connectors. | |||
Verify each battery cell-to cell and terminal connection resistance is s 1.5E 4 ohm. | |||
d SR 3.8.4.3 Verify battery cells, cell plates, and . 18 months J. racks show no visual indication of physical T damage or abnormal deterioration that could | |||
%, degrade battery performance. 1 SR 3.8.4.4 Remove visible corrosion and verify battery 18 months cell to cell and terminal connections are coated with anti-corrosion material. | |||
SR 3.8.4.5 Verify each battery cell to cell and 18 months terminal connection resistance s 1.5E-4 ohm. | |||
SR 3.8.4.6 Verify each required battery charger 18 months O supplies for Division I: a 100 amps at g = 129 V for a 4 hours; and Division II: | |||
_% = 100 amps at = 124.7 V for a 4 hours. | |||
(continued) | |||
] FERMI UNIT 2 3.8 17 Revision 7 06/18/99 | |||
.t | |||
1 Battery Cell Parameters 3.8.6 | |||
) | |||
3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LC0 '3.8.6 - Battery cell parameters for the Division I and Division II batteries shall be within limits. | |||
APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE. | |||
ACTIONS | |||
....................................-NOTE - - --- ------ -------------- -- | |||
Separate Condition entry is allowed for each battery. | |||
CONDITION REQUIRED ACTION COMPLETION TIME i 1 | |||
A. One or more batteries A.1 Verify pilot cells 1 hour , | |||
with one or more electrolyte level and i battery cell float voltage meet i | |||
. parameters not within Table 3.8.6 1 J | |||
@l - | |||
, Table 3.8.6 1 Category . Category C limits. ; | |||
- A or B limits. l 1-6~ND k | |||
A.2 Verify battery cell 24 hours parameters meet Table 3.8.61 AN_D Category C limits. | |||
Once'per 7 days thereafter 6NJ A.3 Restore battery cell 31 days | |||
. parameters to Table 3.8.6 1 Category A and B | |||
-h- ll- limits. | |||
(continued) l FERMI UNIT 2 3.8 22 Revision 7 06/18/99 | |||
Battery Cell Parameters 3.8.6 3 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable. | |||
Time of Condition A not met. | |||
E | |||
'One or more batteries with average electrolyte temperature of the | |||
' representative cells not within limits. | |||
E One or more batteries with one or more battery cell parameters not within Table 3.8.6 1 Category C values. , | |||
l l | |||
i SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.61 Category A limits. | |||
(continued) l FERMI - UNIT 2 3.8 23 Revision 7 06/18/99 | |||
] | |||
1 Distribution Systems-Operating 3.8.7 { | |||
l 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating | |||
@ l LC0 3.8.7 The following Division I and Division II AC and DC electrical power distribution subsystems shall be OPERABLE: | |||
: a. AC electrical power distribution subsystemsi Division I Division II | |||
: 1. 4160 V Buses 11EA. 12EB 13EC. 14ED 648. 64C 65E. 65F | |||
: 2. 480 V Buses 72EA. 72EB 72EC 72ED 1 728. 72C 72E. 72F | |||
: 3. 120 V MPU 1 MPU 2 ! | |||
: b. DC electrical power distribution subsystems: | |||
Division I Division II | |||
: 1. 130 V Distribution 2PA 2 2PB 2 Cabinet i | |||
: 2. 260 V MCC 2PA-1 2PB 1 APPLICABILITY: MODES 1. 2. and 3. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore AC electrical AC electrical power 8 hours power distribution distribution subsystem (s) to 6NQ subsystems inoperable. OPERABLE status. | |||
16 hours from discovery of failure to meet | |||
, LCO (continued) l FERMI - UNIT 2- 3.8-26 Revision 7 06/18/99 | |||
' ~ | |||
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INSERT THIS PAGE IN FRONT OF VOLUME 13 t | |||
Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES Remove Replace B3.5.1 ITS pg B 3.5.1-3 Rev 0 B3.5.1 ITS pg B 3.5.1-3 Rev 7 B3.5.1 ITS pg B 3.5.1-9 Rev 0 l B3.5.1 ITS pg B 3.5.1-9 Rev 7 B3.5.1 ITS pg B 3.5.1-11 Rev 0 B3.5.1 ITS pg B 3.5.1-11 Rev 7 , | |||
l B3.5.1 ITS pg B 3.5.1-13 Rev 0 B3.5.1 ITS pg B 3.5.1-13 Rev 7 B3.5.1 ITS pg B 3.5.1-17 Rev 0 B3.5.1 ITS pg B 3.5.1-17 Rev 7 B3.5.2 ITS pg B 3.5.2-4 Rev 0 B3.5.2 ITS pg B 3.5.2-4 Rev 7 | |||
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B3.5.2 ITS pg B 3.5.2-5 Rev 0 B3.5.2 ITS pg B 3.5.2-5 Rev 7 B3.5.2 ITS pg B 3.5.2-6 Rev 0 B3.5.2 ITS pg B 3.5.2-6 Rev 7 B 3.8.1 ITS pg B 3.8.1-6 Rev 0 B 3.8.1 ITS pg B 3.8.1-6 Rev 7 B 3.',.1 ITS pg B 3.8.1-7 Rev 0 B 3.8.1 ITS pg B 3.8.1-7 Rev 7 B 3.8.1 ITS pg B 3.8.1-8 Rev 0 B 3.8.1 ITS pg B 3.8.1-8 Rev 7 B 3.8.1 ITS pg B 3.8.1-9 Rev 0 B 3.8.1 ITS pg B 3.8.1-9 Rev 7 B 3.8.1 ITS pg B 3.8.1 10 Rev 0 B 3.8.1 ITS pg B 3.8.1-10 Rev 7 B 3.8.1 ITS pg B 3.8.1-11 Rev 0 B 3.8.1 ITS pg B 3.8.1-11 Rev 7 B 3.8.1 ITS pg B 3.8.1-12 Rev 0 B 3.8.1 ITS pg B 3.8.1-12 Rev 7 l B 3.8.1 ITS pg B 3.8.1-13 Rev 0 B 3.8.1 ITS pg B 3.8.1-13 Rev 7 B 3.8.1 ITS pg B 3.8.1-14 Rev 0 B 3.8.1 ITS pg B 3.8.1-14 Rev 7 B 3.8.1 ITS pg B 3.8.1-15 Rev 0 B 3.8.1 ITS pg B 3.8.1-15 Rev 7 B 3.8.1 ITS pg B 3.8.1-16 Rev 0 B 3.8.1 ITS pg B 3.8.1-16 Rev 7 B 3.8.1 ITS pg B 3.8.!-17 Rev 0 B 3.8.1 ITS pg B 3.8.1-17 Rev 7 B 3.8.1 ITS pg B 3.8.1-18 Rev 0 B 3.8.1 ITS pg B 3.8.1-18 Rev 7 B 3.8.1 ITS pg B 3.8.1 19 Rev 0 B 3.8.1 ITS pg B 3.8.1-19 Rev 7 B 3.8.1 ITS pg B 3.8.1-20 Rev 0 B 3.8.1 ITS pg B 3.8.1-20 Rev 7 B 3.8.3 ITS pg B 3.8.3-1 Rev 0 B 3.8.3 ITS pg B 3.8.3-1 Rev 7 B 3.8.3 ITS pg B 3.8.3-2 Rev 0 B 3.8.3 ITS pg B 3.8.3-2 Rev 7 B 3.8.3 ITS pg B 3.8.3-3 Rev 0 B 3.8.3 ITS pg B 3.8.3-3 Rev 7 B 3.8.3 ITS pg B 3.8.3-4 Rev 0 B 3.8.3 ITS pg B 3.8.3-4 Rev 7 B 3.8.3 ITS pg B 3.8.3-5 Rev 0 B 3.8.3 ITS pg B 3.8.3-5 Rev 7 B 3.8.3 ITS pg B 3.8.3-6 Rev 0 B 3.8.3 ITS pg B 3.8.3-6 Rev 7 B 3.8.3 ITS pg B 3.8.3-7 Rev 0 B 3.8.3 ITS pg B 3.8.3-7 Rev 7 B 3.8.4 ITS pg B 3.8.4-2 Rev 1 B 3.8.4 ITS pg B 3.8.4-2 Rev 7 B 3.8.4 ITS pg B 3.8.4-3 Rev i B 3.8.4 ITS pg B 3.8.4-3 Rev 7 Rev7 06/18/99 | |||
Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES (cont'd) | |||
Remove Replace B 3.8.4 ITS pg B 3.8.44 Rev I B 3.8.4 ITS pg B 3.8.4-4 Rev 7 B 3.8.4 ITS pg B 3.8.4-5 Rev 1 B 3.8.4 ITS pg B 3.8.4-5 Rev 7 B 3.8.6 ITS pg B 3.8.6-6 Rev 0 B 3.8.6 ITS pg B 3.8.6-6 Rev 7 Rev7 06/18/99 | |||
ECCS -Operating B 3.5.1 BASES BACKGROUND (continued) provided for the four LPCI pumps to route water from the suppression pool, to allow testing of the LPCI pumps without l injecting water into the RPV. These test lines also provide suppression pool cooling capability. as described in LCO 3.6.2.3, "RHR Suppression Pool Cooling." | |||
The HPCI System (Ref. 3) consists of a steam driven turbine pump unit, piping, and valves to provide steam to the , | |||
turbine. as well as piping and valves to transfer water from ' | |||
the suction source to the core via the feedwater system line, where the coolant is distributed within the RPV through the feedwater sparger. Suction piping for the system is provided from the CST and the suppression pool. | |||
Pump suction for HPCI is normally aligned to the CST source to minimize injection of suppression pool water into the l RPV. However, if the CST water supply is low, or if the suppression pool level is high, an automatic transfer to the suppression pool water source ensures a water supply for continuous operation of the HPCI System. The steam supply to the HPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve. ' | |||
The HPCI System is designed to provide core cooling for a wide range of reactor pressures (165 psig to 1146 asig). | |||
Upon receipt of an initiation signal, the HPCI turaine stop valve and turbine control valve open simultaneously and the turbine accelerates to a specified speed. As the HPCI flow increases, the turbine governor valve is automatically adjusted to maintain design flow. Exhaust steam from the HPCI turbine is discharged to the suppression pool. A full flow test line is 3rovided to route water to the CST to allow testing of t1e HPCI System during normal operation without injecting water into the RPV, The ECCS pumps are provided with minimum flow bypass lines, which discharge to the suppression pool. The valves in these lines automatically open to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, all ECCS pump discharge lines are filled with water. The LPCI and CS System discharge lines are kept full of water using a " keep fill" system. The core spray lines are kept charged with demineralized water and the RHR lines are kept charged with condensate water by a pressure regulating valve. The HPCI System is normally l FERMI - UNIT 2 B 3.5.1 - 3 Revision 7, 06/18/99 | |||
F-ECCS- Operating B 3.5.1 BASES | |||
. ACTIONS (continued) | |||
L1-The LC0 requires five ADS valves to be OPERABLE in order to provide the ADS function. The ECCS analyses are performed | |||
. with the initial condition of one ADS valve out of service (Ref. 13). Per this analysis, operation of only four ADS valves will provide the required depressurization. However, overall reliability of the ADS is reduced. because a single failure in the OPERABLE ADS valves could result in a reduction in depressurization capability. Therefore, operation is only allowed for a limited time. The 14 day Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience. | |||
H.1 and H.2 7 If any one low pressure ECCS injection / spray subsystem, or 1l one LPCI pump in both LPCI subsystems, is inoperable in W addition to one inoperable ADS valve. adequate core cooling is ensured by the OPERABILITY of HPCI and the remaining low pressure ECCS injection / spray subsystem. However, overall ECCS reliability is- reduced because a single active component failure concurrent with a design basis LOCA could | |||
-result in the minimum required ECCS equipment not being available. Since both a high pressure system (ADS) and low pressure subsystem (s) are inoperable, a more restrictive Completion Time of 72 hours-is required to restore either the low pressure ECCS subsystem (s) or the ADS valve to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience. | |||
I-1 and I.2 i' | |||
If any Required Action and associated Completion Time of Condition E. F. G. or H is not met, or if two or more ADS valves are inoperable, the plant must be brought to a condition in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours and reactor steam dome pressure reduced.to - | |||
s 150 psig within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. ; | |||
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l ECCS- Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) discharge valves, and LPCI cross-tie valve. The swing bus automatic throwover scheme must be OPERABLE for both LPCI subsystems to be OPERABLE. The 31 day Frequency has been found acceptable based on engineering judgment and operating 1 experience. | |||
] | |||
This SR is modified by a Note to indicate that when this test results in LPCI inoperability solely for performance of l this required Surveillance, or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG-12 being l paralleled to the bus for required testing, entry into l associated Conditions and Required Actions may be delayed s* for up to 12 hours until the required testing is completed. | |||
( Upon completion of the Surveillance or expiration of the 12 hour allowance the swing bus must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. | |||
SR 3.5.1.3 The flow path piping has the potential to develop voids and pockets of entralned air. Maintaining the pump discharge lines of the HPCI System CS System. and LPCI subsystems full of water ensures that the ECCS will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent a water hammer following an ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. The 31 day Frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls governing system operation, and operating experience. | |||
SR 3.5.1.4 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a non accident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation rather, it involves | |||
{ FERMI - UNIT 2 B 3.5.1 - 11 Revision 7 06/18/99 | |||
ECCS-Operating i B 3.5.1 l l | |||
BASES: ! | |||
i SURVEILLANCE REQUIREENTS (continued)' | |||
SR 3.5.1.6 Verification every 31 days that the RHR System power operated cross-tie valve is open ensures that each LPCI - | |||
1 | |||
+ subsystem remains ca recirculation loop. pable of injaction A valve into the. selected that is inaccessible may be i | |||
verified by administrative controls; If a RHR System cross-tie valve is not o>en. both LPCI subsystems must be considered inopera)le. The 31 day Frequency has been found acceptable, considering that these valves are under strict administrative controls that will ensure the valves continue to remain open. 4 I | |||
SR 3.5.1.7 Cycling the recirculation pump discharge valves through one complete cycle of full travel demonstrates that the valves . | |||
are mechanically OPERABLE and will close when required. i | |||
-Upon initiation of an automatic LPCI subsystem injection ' | |||
signal, these valves are required to be closed to ensure i full LPCI subsystem flow injection in the reactor via the ' | |||
recirculation jet pumps. De energizing the valve in the | |||
. closed position will also ensure the proper flow path for the LPCI subsystem. Acceptable methods of de ener valve include de energizing breaker control power.gizing racking the out the breaker or removing the breaker. | |||
The specified Frequency is.18 months. Verification each i 18 months is an exception to the normal Inservice Testing Program generic valve cycling Frecuency of 92 days. but is considered acceptable due to the cemonstrated reliability of these valves. If the valve is inoperable and in the open position, both LPCI subsystems must be declared inoperable. | |||
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ECCS -Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) which this SR is to be performed is a 850 psig (the pressure recommended by the valve manufacturer). Adequate steam flow ; | |||
is represented by turbine bypass valves open at least 201. | |||
O/)l Reactor startup is allowed prior to performing this SR because valve OPERABILITY and the setpoints for overpressure. | |||
protection are verified, per ASME requirements', prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be . | |||
performed until 12 hours after reactor steam pressure and I flow are adequate to perform the test. The 12 hours allowed I for manual actuation after the required pressure and flow are reached is sufficient to achieve stable conditions and provides adequate time to complete the Surveillance. | |||
SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TEST performed , | |||
in LC0 3.3.5.1 overlap this Surveillance to provide complete I testing of the assumed safety function. | |||
The Frequency is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a plant outage. Operating | |||
' experience has shown that these components usually pass the | |||
' SR when performed at the 18 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. | |||
SR 3.5.1.14 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Response time testing acceptance criteria are included in Reference 15. This SR is modified by a Note stating that the ECCS instrumentation response times are not required to be measured. The contribution of the instrument response times to the overall ECCS response j time are assumed based on guidance of Reference 16. l The 18 month Frequency is based or, the need to perform this Surveillance under the conditions that apply during a plant ; | |||
outage and the potential for an un)lanned transient if the i Surveillance were performed with t1e reactor at power. | |||
Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency. | |||
l FERMI UNIT 2 B 3.5.1 17 Revision 7 06/18/99 l | |||
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ECCS-Shutdown B 3.5.2 BASES ACTIONS (continued) to OPERABLE status. In this case, the Surveillance may need to be performed to restore the component to OPERABLE status. | |||
Actions must continue until all required components are l OPERABLE. : | |||
The 4 hour Completion Time to restore at least one low pressure ECCS injection / spray subsystem to OPERABLE status ensures that prompt action will be taken to provide the required cooling capacity or to initiate actions to place the plant in a condition that minimizes any potential fission product release to the environment. | |||
SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 REQUIREMENTS The minimum water level indication of 66 inches (9 ft 0 inches actual level) required for the suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for j the CS System and LPCI subsystem pumps, recirculation volume. and vortex prevention. With the suppression pool water level less than the required limit, all ECCS injection / spray subsystems are inoperable unless they are aligned to an OPERABLE CST. | |||
When suppression pool level is < -66 inches, the CS System I is considered OPERABLE only if it can take suction from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a verification that either the suppression pool water level is = -66 inches or that CS is aligned to take suction from the CST and the | |||
'[d CST contains a 300.000 gallons of water, equivalent to 19 ft W/ plus margin to preclude vortex formation, ensures that the CS System can supply at least 150,000 gallons of makeup water to the RPV. The CS suction is uncovered at the 150,000 gallon level. However, as noted, only one required CS subsystem may take credit for the CST option during OPDRVs. During OPDRVs. the volume in the CST may not provide adequate makeup if the F.PV were completely drained. | |||
Therefore, only one CS subsystea is allowed to use the CST. | |||
This ensures the other required ECCS subsystem has adequate makeup volume. | |||
The 12 hour Frequency of these SRs was developed considering operating experience related to suppression pool water level i FERMI UNIT 2 B 3.5.2-4 Revision 7 06/18/99 T | |||
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ECCS - Shutdown . | |||
B 3.5.2 ) | |||
BASES SURVEILLANCE REQUIREMENTS (continued) 1 and CST water level variations and instrument drift during ! | |||
the applicable MODES. Furthermore, the 12 hour Frequency is j considered adequate in view of other indications available in the control room including alarms. to alert the operator to an abnormal suppression pool or CST water level , | |||
condition. 1 SR 3.5.2.3 i The LPCI System injection valves. recirculation pump discharge valves, and LPCI cross tie valve are powered from the LPCI swing bus, which must remain energized to support , | |||
OPERABILITY of any required LPCI subsystem. Therefore. l verification of proper voltage and correct breaker alignment l to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate electrical power sources are available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability ensures that the required voltage is readily available for critical system loads connected to this bus. The 7 day Frequency takes into 3 account the redundant capability of the AC. DC. and AC swing j bus electrical power sources, and other indications available in the control room that alert the operator to subsystem malfunctions. l SR '3.5.2.4. SR 3.5.2.6. and SR 3.5.2d I k The Bases provided for SR 3.5.1.3 SR 3.5.1.8. and SR 3.5.1.11 are applicable to SR 3.5.2.4. SR 3.5.2.6. and SR 3.5.2.7. respectively. l l | |||
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ECCS - Shutdown l B 3.5.2 BASES | |||
-SURVEILLANCE REQUIREMENTS (continued) | |||
: l. , | |||
SR 3.5.2.5 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides , | |||
assurance that the proper flow paths will exist for ECCS ! | |||
operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since I these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation: rather. it i involves verification that those valves capable of potentially being mispositioned are in the correct position. | |||
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is appropriate because the valves are operated under procedural control and the probability of their being mispositioned during this time period is low. | |||
In H0 DES 4 and 5. the RHR System may operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal. | |||
Therefore, this SR is modified by a Note that allows one or both LPCI subsystems of the RHR System to be considered OPERABLE for the ECCS function if all the required valves in the LPCI flow path can be manually realigned (remote or local) to allow injection into the RPV and the system is not otherwise inoperable. This will ensure adequate core cooling if an inadvertent RPV draindown should o.ccur. | |||
REFERENCES 1. UFSAR. Section 6.3.2. | |||
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l FERMI UNIT 2 B 3.5.2-6 Revision 7 06/18/99 I | |||
AC Sources-Operating B 3.8.1 BASES ACTIONS (continued) events existing concurrently is acceptable because it | |||
. _ minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown. | |||
'The remaining OPERABLE EDGs and offsite circuits are adequate to supply electrical power to the onsite Class 1E-Distribution System. Thus, on a component basis, single failure protection for the required feature's function may have been lost: however, function has not been lost. The 4 hour Completion Time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required feature. Additionally, the 4 hour Completion Time takes into accoent the capacity and capability of the remaining AC. sources, reasonable time for repairs, and low probability of a DBA occurring during this period. | |||
Al To minimize the impact of operation with an inoperable EDG, it is necessary to periodically ensure the availability of CTG 11-1. The verification of the status of CTG 111 is performed by an administrative check of breaker and line availability, and the CTG 111 ability to supply Division I loads. Since this Required Action or.ly specifies ** verify 6 the status " even when CTG 11 1 is not available it does not l result in this Required Actions being not met. However, upon discovery that CTG 111 is unavailable, the limitations 4 of Required Action A.5 are imposed l A.4.1 and A.4.2 ) | |||
.I l Required Action A.4.1 provides an allowance to avoid W | |||
W unnecessary testing of OPERABLE EDGs. If it can be determined that the cause of the inoperable EDG(s) does not exist on the OPERABLE EDGs, SR 3.8.1.2 does not have to be performed. If the cause of inoperability exists on other | |||
. EDG(s), they are declared inomrable upon discovery, and Condition B of LCO 3.8.1 may a entered. Once the failure is repaired, and the common cause failure no longer exists. | |||
l Required Action A.4.1 is satisfied. :If the cause of the initial inoperable EDG cannot be confirmed not to exist on the remaining EDG(s), performance of SR 3.8.1.2 suffices to provide assurance of continued OPERABILITY of those EDGs. | |||
% In the event the inoperable EDG(s) are restored to OPERABLE , | |||
l ' status prior to completing either A.4.1 or A.4.2, the plant ' | |||
l FERMI ' UNIT 2' B 3.8.1- 6 Revision 7 06/18/99 | |||
AC Sources-0perating I B 3.8.1 i | |||
BASES ACTIONS (continued) corrective action )rogram will continue to evaluate the common cause possi)ility. This continued evaluation. l however, is no longer under the 24 hour constraint imposed | |||
~ | |||
while in Condition A. l According to Generic Letter 84-15 (Ref. 7), 24 hours is a reasonable time to confirm that the OPERABLE EDGs are not l affected by the same problem as the inoperable EDG. l 4l A.5 and A.6 According to Regulatory Guide 1.93 (Ref. 6), operation may ) | |||
continue with no OPERABLE EDGs to one division for a period ' | |||
that should not exceed 72 hours. With one or both EDGs in , | |||
one division inoperable, the remaining OPERABLE EDGs and ' | |||
offsite circuits are adequate to supply electrical power to l | |||
~ the onsite Class 1E Distribution System. Required Action i d A.5 imposes this 72 hour Completion Time from the discovery i Q of the non availability CTG 111. However, if CTG 111 is available to sup)1y Division I loads (determined by administrative cleck of breaker. line availability, and CTG 111 status) Recuired Action A.5 would be met and Required Action A.6 woulc allow the restoration time of 7 days. | |||
The 72 hour Completion Time to restore to at least one EDG in the division in OPERABLE status takes into account the capacity and capability of the remaining AC sources, reasonable time for repairs, and low probability of a DBA yl occurring during this period. The 7 day Completion Time to restore all EDGs to OPERABLE status takes into account the 1 capacity and capability of the remaining AC Sources, as well as the additional reliability afforded by the availability of CTG 11-1. | |||
IL1 With one or both EDGs on both divisions inoperable, there may be no remaining standby AC source. Thus, with an assumed loss of offsite electrical power, insufficient standby AC sources are available to power the minimum required ESF functions. Since the offsite electrical power system is the only source of AC Jower for a significant percentage of ESF equipment at t1is level of degradation, the risk associated with continued operation for a very short time could be less than that associated with an immediate controlled shutdown. (The immediate shutdown | |||
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l, FERMI UNIT 2 B 3.8.1 - 7 Revision 7 06/18/99 | |||
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AC Sources-Operating B 3.8.1 l BASES ACTIONS (continued) l L could cause grid instability, which could result in a total i | |||
loss of AC power.) Since any inadvertent unit generator trip could also result in a total loss of offsite AC power. | |||
! however, the time allowed for continued operation is | |||
, severely restricted. The intent here is to avoid the risk l I associated with an immediate controlled shutdown and to minimize the risk associated with this level of degradation. | |||
According to Regulatory Guide 1.93 (Ref. 6), with both l divisions with EDGs inoperable, operation may continue for a period that should not exceed 2 hours. | |||
l C.1 and C.2 l If the inoperable AC electrical power sources cannot be restored to OPERABLE status within the associated Completion Time. the unit must be brought to a MODE in which the LC0 does not apply. Furthermore, with one or both offsite . | |||
circuits inoperable, the Fermi design and subsequent plant response is such that power operation is not justified, and c plant shutdown is required. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours and to MODE 4 within 36 hours. 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. | |||
SURVEILLANCE The AC sources are designed to permit inspection and REQUIREMENTS testing of all important areas and features. especially those that have a standby function, in accordance with 10 CFR 50. GDC 18 (Ref. 8). Periodic component tests are supplemented by extensive functional tests during refueling outages (under simulated accident conditions). The SRs for demonstrating the OPERABILITY of the EDGs are based on the recommendations of Regulatory Guide 1.9 (Ref. 3). Regulatory Guide 1.108 (Ref. 9), and Regulatory Guide 1.137 (Ref.10), | |||
as addressed in the UFSisR. | |||
Where the SRs discussed herein specify voltage and frequency tolerances, the following summary is applicable. The minimum steady state output voltage of 3740 V is 90% of the nominal 4160 V output voltage. This value, which is l | |||
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k l FERMI UNIT 2 B 3.8.1 - 8 Revision 7 06/18/99 | |||
AC Sources-Operating ; | |||
B 3.8.1 | |||
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BASES SURVEILLANCE. REQUIREMENTS (continued) specified in ANSI C84.1'(Ref.11), allows for voltage drop to the terminals of 4000 V motors whose minimum operating voltage is specified as 90% or 3600 V. It also allows for voltage drops to motors and other equipment down through the 120 V. level where minimum operating voltage is also usually specified as 90% of name I; late rating. The specified | |||
. maximum steady state output. voltage of 4580 V is equal to the maximum operating voltage specified for 4000 V motors. | |||
It ensures that for a lightly loaded distribution system. | |||
the voltage at the terminals of 4000 V motors is no more than the maximum rated operating voltages. . The specified minimum and maxhum frequencies of the EDG are 58.8 Hz and 61.2 Hz respectively. These values are equal to | |||
* 2% of the 60 Hz nominal frequency and are derived from the recommendations found in Regulatory Guide 1.9 (Ref. 3). | |||
SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite' distribution network and availability of offsite AC electrical power. . The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads | |||
.are connected to their preferred power source and that appropriate independence of offsite circuits is maintained. | |||
The.7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room. | |||
SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the . standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown condition. | |||
To minimize the mechanical stress and wear on moving parts that do not get lubricated when the engine is not running. | |||
.l.. these SRs have been modified by a Note (Note 1 for SR 3.8.1.2 and Note 1 for SR 3.8.1.7) to indicate that all EDG starts for these Surveillances may be preceded by an ; | |||
g engine prelube period and followed by a warmup prior to j | |||
., loading. | |||
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l l FERMI UNIT 2 B 3.8.1- 9 Revision 7 06/18/99 | |||
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AC Sources-Operating i B 3.8.1 l BASES ! | |||
. SURVEILLANCE REQUIREMENTS (continued) | |||
For the purposes of SR 3.8.1.2 testing, the EDGs are started anywhere from standby to hot conditions by using one of the following signals: | |||
Manual. | |||
Simulated loss of-offsite power by itself. | |||
Simulated loss of offsite power in con,iunction with an ESF actuation test signal, or | |||
- An ESF actuation test signal by itself. | |||
'In order to reduce stress and wear on diesel engines, the EDG manufacturer recommends a modified start in which the starting speed of EDGs is limited, warmup is limited to this lower speed, and the EDGs are gradually accelerated to g synchronous speed prior to loading. These start procedures | |||
.i are the' intent of Note 2, which is only allowed to satisfy | |||
'fl SR 3.8.1.2 but are not applicable when performing SR 3.8.1.7. | |||
SR 3.8.1.7 requires that, at a 184 day Frequency, the EDG starts from standby conditions and achieves required voltage and frequency within 10 seconds. Standby conditions for an EDG mean that the diesel engine coolant and oil are being continuously circulated and temperature is being maintained consistent with manufacturer recommendations. The 10 second start requirement supports the assumptions in the design basis LOCA analysis of UFSAR. Section 6.3 (Ref.12). The 10 second start. requirement is not applicable to SR 3.8.1.2. | |||
Since SR 3.8.1.7 does require a 10 second start. it is more | |||
~ | |||
restrictive than SR 3.8.1.2, and it may be performed in lieu of SR 3.8.1.2. . In addition to the SR requirements, the time for the EDG to reach steady state operation, unless the 9 modified EDG start method is-employed, is periodically | |||
' monitored and the trend evaluated to identify degradation of 4- governor and voltage regulator performance. | |||
!$ -The normal 31 day Frequency for SR 3.8.1.2 is consistent A with Regulatory Guide 1.9.(Ref. 3). The 184 day. Frequency 4 . | |||
-for SR 3.8.1.7 is:a reduction in cold testing consistent with Generic Letter 84 15'(Ref. 7). These Frequencies provide adecuate assurance of EDG OPERABILITY, while | |||
' minimizing cegradation resulting from testing. | |||
'l'-FERMI UNIT 2- ' B 3. 8.1 Revision 7. 06/18/99 | |||
o AC Sources'-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
SR 3.8.1.3 This Surveillance provides assurance that the EDGs are capable of synchronizing and accepting greater than or equal to the equivalent of the maximum expected accident loads al | |||
;- without the risk of overloading the EDG. The EDG is tested at approximately 90% of its continuous load rating, which provides margin to excessive EDG loading, while demonstrating the EDG capability to carry loads near the maximum expected accident loads. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the EDG is connected to the offsite source. | |||
~ | |||
Although no power factor requirements are established by this SR, the EDG is normally operated at a power factor between 0.8 lagging and 1.0. The 0.8 value is the design 3 rating of the machine, while 1.0 is an operational limitation to ensure circulating currents are minimized. | |||
D Routine overloading may result in more frequent teardown | |||
.L inspections in accordance with vendor recommendations in | |||
& order to maintain EDG OPERABILITY. | |||
The normal 31 day Frequency for this Surveillance is kll consistent with Regulatory Guide 1.9 (Ref. 3). | |||
Note 1 modifies this Surveillance tc indicate that diesel engine runs for this Surveillance may include gradual loading. as recommended by the manufacturer, so that mechanical stress and wear on the diesel engine are minimized. | |||
Note 2 modifies this Surveillance by stating that momentary transients (e.g., because of changing bus loads) do not invalidate this test. Similarly, momentary power factor transients o.itside the normal range do not invalidate the test. | |||
Note 3 indicates that this Surveillance should be conducted on only one EDG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations. | |||
l I | |||
l l FERMI UNIT 2 F, 3.8.1 - 11 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 l | |||
BASES SURVEILLANCE REQUIREMENTS (continued) | |||
, SR 3.8.1.4 | |||
, This SR provides verification that the level of fuel oil in l the day tank is at or above the level at which fuel oil is L ' automatically added. The level is expressed as an l- ecuivalent volume in gallons, and is selected to ensure acequate fuel oil for a minimum of 1 hour of EDG operation at full load. | |||
- The 31 day Frequency is adequate to ensure that a sufficient | |||
! . supply of fuel oil is available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period. | |||
l 'SR- 3.8.1.5 Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in | |||
, fuel oil and cause fouling, but all must have a water l | |||
environment in order to survive. Reinoval of water from the fuel oil day tanks once every 31 days eliminates the . | |||
necessary environment for bacterial survival. _ This is the i most effective means of controlling microbiological fouling. | |||
In addition, it eliminates the potential for water entrainment in the fuel oil during EDG operation. Water may come from any of several sources. including condensation, ground water, rain water. contaminated fuel 011. and breakdown of the fuel. oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and . | |||
provides data regarding the watertignt integrity of the fuel ' | |||
oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref.10). This SR is for preventive i maintenance. The presence of water does not necessarily represent- a failure of this SR providod that accumulated water is removed during performance of this Surveillance. | |||
SR 3.8.1.6 This Surveillance demonstrates that each required fuel oil transfer pump operates' and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This Surveillance provides assurance that the fuel | |||
' oil transfer pump is OPERABLE. the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the l FERMI - UNIT 2 B 3.8.1 - 12 Revision 7 06/18/99 e | |||
c AC Sources-Operating B 3.8.1 BASES ! | |||
SURVEILLANCE REQUIREMENTS (continued) ; | |||
controls and control systems for automatic fuel transfer systems are OPERABLE. | |||
l The design of fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG , | |||
testing. As such, a 31 day Frequency is appropriate, since l proper o)eration of fuel transfer systems is an inherent part of EDG OPERABILITY. | |||
SR 3.8.1.7 See SR 3.8.1.2. | |||
SR 3.8.1.8 Each EDG is provided with an engine overspeed trip to l prevent damage to the engine. Recovery from the transient caused by the loss of a large load could cause diesel engine overspeed, which, if excessive might ' result in a trip of the engine. This Surveillance demonstrates the EDG load response characteristics and capability to reject the largest single load while maintaining a specified margin to the overspeed trip. The largest single load for each EDG is a residual heat removal pump (1684 kW). This Surveillance may be accomplished by: | |||
: a. Tripping the EDG output breaker with the EDG carrying areater than or ecual to its associated single largest | |||
;ost accident loac while paralleled to offsite power, or while solely supplying the bus: or | |||
: b. Tripping its associated single largest )ost accident load with the EDG solely supplying the aus. | |||
As required by IEEE-308 (Ref.14), the load rejection test is acceptable if the increase in diesel s)eed does not exceed 75% of the difference between sync 1ronous speed and the overspeed trip setpoint, or 15% above synchronous speed, whichever is lower. This represents 66.75 Hz, equivalent to 75% of the difference between nominal speed and the overspeed trip setpoint. | |||
: 1. FERMI UNIT 2 B 3.8.1 - 13 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
The frequency tolerances specified in this SR are derived | |||
- from Regulatory Guide 1.9 (Ref. 3) recommendations for j response during load sequence intervals. The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9). | |||
SR '3.8.1.9 This Surveillance demonstrates the EDG capability to reject a full load without overspeed tripping or exceeding the predetermined voltage limits. The EDG full load rejection may occur because of a system fault or inadvestent breaker i tripping. This Surveillance ensures proper engine generator i lead response under the simulated test conditions. This l test simulates the loss of the total connected load that the i EDG ex>eriences following a full load rejection and verifies ; | |||
that t7e EDG does not trip upon loss of the load. These I acceptance criteria provide EDG damage 3rotection. While ; | |||
the EDG is not expected to experience t11s transient during l an event, and continues to be available, this response ensures that the EDG is not degraded for future application, including reconnection to the bus if the trip initiator can be corrected or isolated. | |||
The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9) and is intended to be consistent with expected fuel cycle lengths. | |||
SR 3.8.1.10 As required by Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(1), this Surveillance demonstrates the as designed operation of the standby power sources during loss of the offsite source. This test verifies all actions encountered from the loss of offsite power. including shedding of the nonessential loads and energization of the emergency buses and respective loads from the EDG, including automatic start of the EDG cooling water pump. It further demonstrates the capability of the EDG to automatically achieve the required voltage and frequency within the specified time. | |||
The EDG auto start time of 10 seconds is derived from requirements of the accident analysis for responding to a design basis large break LOCA. The Surveillance should be continued for a minimum of 5 minutes in order to demonstrate FERMI UNIT 2 B 3.8.1- 14 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 i | |||
BASES l | |||
SURVEILLANCE REQUIREMENTS (continued) that all starting transients have decayed and stability has been achieved. | |||
The requirement to verify the connection and power supply of permanent and auto-connected loads is intended to i satisfactorily show the relationship of these loads to the EDG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For instance. Emergency Core Cooling Systems (ECCS) injection valves are not desired to be stroked open, or systems are not capable of being operated at full flow, or RHR systems performing a decay heat removal function are not desired to be realigned to the ECCS mode of operation. In lieu of actual demonstration of the connection and loading of these loads, testing that adequately shows the capability of the EDG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified. | |||
The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(1), takes into consid2 ration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. | |||
This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the Note is to minimize wear and tear on the EDGs during testing. | |||
SR 3.8.1.11 This Surveillance demonstrates that the EDG (including its associated cooling water pump) automatically starts and achieves the required minimum voltage and frequency within the specified time (10 seconds) from the design basis actuation signal (LOCA signal) and operates for a 5 minutes. | |||
The 5 minute period provides sufficient time to demonstrate stability. | |||
The Frequency of 18 months takes into consideration plant conditions required to perform the Surveillance and is intended to be consistent with the expected fuel cycle lengths. Operating experience has shown that these l FERMI - UNIT 2 B 3.8.1 - 15 Revision 7 06/18/99 | |||
l l | |||
l AC Sources-Operating B 3.8.1 l BASES SURVEILLANCE REQUIREMENTS (continued) l l components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is acceptable | |||
! from a reliability standpoint. | |||
l This SR is modified by a Note allowing EDG starts to be l preceded by an engine prelube period. The reason for the ! | |||
l Note is to minimize wear and tear on the EDGs during ) | |||
l testing. l i | |||
SR 3.8.'1.12 l l | |||
This Surveillance demonstrates that EDG non critical l protective functions (e.g. high jacket water temperature) are bypassed on an actual or simulated ECCS initiation signal and critical protective functions (engine overspeed. | |||
generator differential current low lubricating oil pressure crankcase overpressure, and failure to start) trip the EDG to avert substantial damage to the EDG unit. The non-critical trips are bypassed during DBAs and provide an alarm ) | |||
on an abnormal engine condition. This alarm provides the l l operator with sufficient time to react appropriately. The L EDG availability to mitigate the DBA is more critical than I protecting the engine against minor problems that are not immediately detrimental to emergency operation of the EDG. | |||
The 18 month Frecuency is based on engineering judgment, takes into consiceration plant conditions required to l per form the Surveillance, and is intended to be consistent l with ex>ected fuel cycle lengths. Operating experience has shown t1at these components usually pass the SR when 4 performed at the 18 month Frequency. Therefore, the l Frequency was concluded to be acceptable from a reliability j standpoint. ' | |||
SR 3.8.1.13 Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(3). requires q l | |||
demonstration once per 18 months that the EDGs can start and ! | |||
run continuously at full load capability for an interval of ' | |||
not less than 24 hours-22 hours of which is at a load equivalent to the continuous rating of the EDG, and 2 hours of which is at a load equivalent to 110% of the continuous duty rating of the EDG, Fermi 2 has taken an exception to ' | |||
this requirement and performs the 22 hour run at approximately 90% of the continuous rating (2500 kW-2600.kW), and performs the 2 hour run at approximately the | |||
.y. | |||
l FERMI UNIT.2 B 3.8.1 - 16 Revision 7 06/18/99 L | |||
AC Sources-Operating B 3.8.1 1 | |||
BASES SURVEILLANCE REQUIREMENTS (continued) continuous rating (2800 kW 2900 kW). The EDG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for prelube and warmup, discussed in SR 3.8.1.2. and for gradual loading. discussed in SR 3.8.1.3. are applicable to this SR. | |||
Although no power factor requirements are established by to this SR, the EDG is normally operated at a power factor i between 0.8 lagging and 1.0. The 0.8 value is the desian R rating of the machine, while the 1.0 is an operational 4t limitation to ensure circulating currents are minimized. A load band is provided to avoid routine overloading of the EDG. Routine overloading may result in more frequent ; | |||
teardown inspections in accordance with vendor i recommendations in order to maintain EDG OPERABILITY. | |||
The 18 month Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(3); takes into consideration plant conditions required to perform the Surveillance: and is intended to be consistent with expected fuel cycle lengths. | |||
This Surveillance has been modified by a Note. The Note states that momentary transients due to changing bus , | |||
loads do not invalidate this test. | |||
SR 3.8.1.14 This Surveillance demonstrates that the diesel engine can I restart from a hot condition, such as subsequent to shutdown i from normal Surveillances. and achieve the minimum required ! | |||
voltage and frequency within 10 seconds and maintain a ' | |||
steady state voltage and frequency range. The 10 second time is derived from the requirements of the accident analysis to respond to a design basis large break LOCA. The 18 month Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(5). | |||
This SR is modified by two Notes. Note 1 ensures that the test is performed with the diesel sufficiently hot. The | |||
> requirement that the diesel has operated for at least T 2 hours near full load conditions prior to performance of | |||
-5 this Surveillance is based on manufacturer recommendations Vi for achieving hot conditions. Routine overloads may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY. | |||
n l FERMI UNIT 2 B 3.8.1 - 17 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
Homentary transients due to changing bus loads do not invalidate this test. Note 2 allows all EDG starts to be preceded by an engine prelube period to minimize wear and tear on the diesel during testing. | |||
SR 3.8.1.15 As required by Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(6), this Surveillance ensures that the manual synchronization and load transfer from the EDG to the offsite source can be made and that the EDG can be returned to standby status when offsite power is' restored. It also ensures that the auto start logic is reset to allow the EDG to restart and reload if a subsequent loss of offsite power occurs. The EDG is considered to be in standby status when the EDG is shutdown with the output breaker open, the load sequence timers are reset, and is able to restart and reload on a subsequent bus under voltage. | |||
The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(6), and takes into consideration plant conditions desired to perform the Surveillance. | |||
SR 3.8.1.16 Under accident conditions with loss of offsite power loads are. sequentially connected to the bus by the automatic load sequencer. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading of the EDGs due to high motor starting currents. The 10% load sequence time interval tolerance' ensures that sufficient time exists for the EDG to restore frequency and voltage ; | |||
prior to applying the next load and that safety analysis | |||
. assumptions regarding ESF equipment time delays are not violated. Reference 2 provides a summary of the automatic loading of ESF buses. | |||
The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), | |||
paragraph 2.a.(2): takes into consideration plant conditions required to perform the Surveillance: and is intended to be consistent with expected fuel cycle lengths. | |||
~ | |||
j FERMI - UNIT 2 B 3.8.1-18 Revision 7 06/18/99 | |||
7 . ) | |||
AC Sources-Operating B 3.8.1 BASES | |||
-SURVEILLANCE REQUIREMENTS (continued) | |||
SR 3.8.1.17 l In the event of a DBA coincident with a loss of offsite power, the EDGs are required to supply the necessary power | |||
-to ESF systems so that the fuel, RCS, and containment design limits are not exceeded. | |||
This Surveillance demonstrates EDG operation, as discussed in the Bases for SR 3.8.1.10. during a loss of offsite power | |||
~ actuation test signal in conjunction with an ECCS initiation signal .- In lieu of actual demonstration of connection and ' | |||
loading of loads testing that adequately shows the i capability of the EDG system to perform these functions is ) | |||
acce table. This testing may include any series of ' | |||
seqr 'tial, overlapping, or total steps so that the entire i cor tion and loading sequence is verified. ; | |||
Th. ~requency of 18 months takes into consideration plant ' | |||
conc..tions required to perform the Surveillance and is ! | |||
intended to be consistent with an expected fuel cycle length of 18 months. , | |||
This SR is modified by a Note allowing EDG starts to be i preceded by an engine prelube period. The reason for the i Note is to minimize wear and tear on the EDGs during testing. | |||
SR 3'.8.1.18 l This Surveillance demonstrates that the EDG starting independence has not been compromised. Also, this Surveillance demonstrates that each engine can achieve proper speed within the specified time when the EDGs are started simultaneously. | |||
The 10 year Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). ' | |||
This SR is modified by a Note allowing EDG starts to be | |||
) receded by an engine prelube period. The reason for the ete is to minimize wear on the EDG during testing. | |||
1 | |||
[. FERMI UNIT 2 B 3.8.1 -19 Revision 7 06/18/99 | |||
AC Sources-Operating B 3.8.1 BASES REFERENCES 1. 10 CFR 50, Appendix A. GDC 17. | |||
: 2. UFSAR. Sections 8.2 and 8.3. | |||
: 3. Regulatory Guide 1.9. | |||
: 4. UFSAR Chapter 6. | |||
: 5. UFSAR, Chapter 15. | |||
: 6. Regulatory Guide 1.93. | |||
: 7. Generic Letter 84-15. | |||
: 8. 10 CFR 50. Appendix A, GDC 18. | |||
: 9. Regulatory Guide 1.108. | |||
: 10. Regulatory Guide 1.137. | |||
: 11. ANSI C84.1. 1982. | |||
: 12. UFSAR. Section 6.3. | |||
: 13. ASME Boiler and Pressure Vessel Code. Section XI. | |||
: 14. IEEE Standard 308. | |||
4 I | |||
4 l' FERMI UNIT 2 B 3.8.1 - 20 Revision 7. 06/18/99 1 | |||
L | |||
I l Diesel Fuel Oil and Starting Air B 3.8.3 8 3.8 ELECTRICAL POWER SYSTEMS | |||
}lB3.8.3 Diesel Fuel Oil and Starting Air BASES BACKGROUND Each emergency diesel generator (EDG) is provided with a storage tank having a fuel oil capacity sufficient to operate that EDG for a period of 7 days while the EDG is supplying maximum continuous load discussed in UFSAR. | |||
Section 9.5.4 (Ref. 1). This onsite fuel oil ca)acity is i sufficient to operate the EDGs for longer than tie time to | |||
- replenish the onsite supply from outside sources. | |||
Fuel oil is transferred from storage tank to day tank by either of two transfer pumps associated with each storage i tank. Redundancy of pumps and piping precludes the failure of one pump. or the rupture of any pipe, valve, or tank to result in the loss of more than one EDG. | |||
For proper operation of the standby EDGs. it is necessary to ensure the proper quality of the fuel oil. Regulatory Guide 1.137 (Ref. 2) addresses the recommended fuel oil practices as supplemented by ANSI N195 (Ref. 3). The fuel oil properties governed by these SRs are the water and sediment content, the kinematic viscosity, specific gravity (or API gravity), and impurity level. | |||
Each EDG has an air start system with adequate capacity for five successive start attempts on the EDG without recharging the air start receiver (s). | |||
APPLICABLE The initial conditions of Design Basis Accident '(DBA) and SAFETY ANALYSES transient analyses in UFSAR Chapter 6 (Ref. 4), and Chapter 15 (Ref. 5) assume Engineered Safety Feature (ESF) systems are OPERABLE. The EDGs are designed to provide sufficient capacity, capability. redundancy, and reliability to ensure the availability of necessary power to ESF systems so that fuel Reactor Coolant System, and containment design limits are not exceeded. These limits are discussed in more detail in the Bases for Section 3.2. Power Distribution Limits: Section 3.4, Reactor Coolant System (RCS): and Section 3.6. Containment Systems. | |||
l FERMI UNIT 2 B 3.8.3 - 1 Revision 7 06/18/99 | |||
: f. 1 j | |||
l . | |||
l l | |||
@ Diesel Fuel Oil and Starting Air B 3.8.3 l | |||
I BASES APPLICABLE SAFETY ANALYSES (continued) | |||
Since diesel fuel oil and starting air subsystem support the hl . operation of the standby AC power sources, they satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). | |||
l LC0 Stored diesel fuel oil is required to have sufficient supply l for 7 days of full load operation. It is also required to I | |||
gl meet specific standards for quality. This requirement. in conjunction with an ability to obtain replacement supplies within 7 days, supports the availability of EDGs required to | |||
, shut down the reactor and to maintain it in a safe condition i for an anticipated operational occurrence (A00) or a postulated DBA with loss of offsite power. EDG day tank l fuel oil requirements, as well as transfer capability from the storage tank to the day tank, are addressed in LC0 3.8.1. "AC Sources-0perating." and LC0 3.8.2. "AC Sources - Shutdown. " | |||
l The starting air system is required to have a minimum capacity for five successive EDG start attempts without recharging the air start receivers. | |||
l | |||
, APPLICABILITY The AC sources (LC0 3.8.1 and LC0 3.8.2) are required to l ensure the availability of the required power to shut down l the reactor and maintain it in a safe shutdown condition l after an A00 or a postulated DBA. Because stored diesel fuel oil and starting air subsystem support LC0 3.8.1 and LC0 3.8.2. stored diesel fuel oil and starting air are required to be within limits when the associated EDG is ; | |||
required to be OPERABLE. | |||
ACTIONS- The ACTIONS Table is modfied by a Note indicating that separate Condition entry is allowed for each EDG, This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable i EDG subsystem. Complying with the Required Actions for one inoperable EDG subsystem may allow for continued operation, i and subsequent inoperable EDG subsystem (s) governed by l separate Condition entry and application of associated Required Actions. | |||
l I | |||
l FERMI - UNIT 2 B 3.8.3 - 2 Revision 7 06/18/99 l | |||
c | |||
i l l l 1 I I l | |||
J j--.j Diesel Fuel Oil and Starting Air B 3.3.3 BASES ! | |||
. ACTIONS (continued). | |||
M In'this Condition, the 7 day fuel oil supply for a required ) | |||
EDG is not available. However, the Condition is restricted ! | |||
, ~to fuel oil level reductions that maintain at least a 6 day i l supply. These circumstances may be caused by events such ' | |||
as: | |||
: a. Full load operation required for an inadvertent start , | |||
; while at minimum required level: or l l | |||
, b. Feed and bleed operations that may be necessitated by I increasing particulate levels or any number of other l oil quality degradations. ; | |||
1 < | |||
This restriction allows sufficient time for obtaining the requisite replacement volume and performing the analyses required prior to addition of the fuel oil to the tank. A i i | |||
period of 48 hours is considered sufficient to complete ' | |||
restoration of the required level prior to declaring the EDG inoperable. This period is acceptable based on the remaining capacity (> 6 days), the fact that procedures will be initiated to obtain replenishment. and the low i probability of an event during this brief period. l i | |||
This Condition is entered as a result of a failure to meet I the acceptance criterion for particulates in one or more required EDG storage tanks. Normally, trending of particulate levels allows sufficient time to correct high particulate levels prior to reaching the limit of acceptability. Poor sample procedures (bottom sampling), | |||
i- contaminated sampling equipment, and errors in laboratory I | |||
analysis can produce failures that do not follow a trend. | |||
Since the presence of particulates does not mean failure of ! | |||
the fuel oil to burn properly in-the diesel engine, since | |||
, particulate concentration 11 unlikely to change l significantly between Surveillance Frequency intervals, and since proper engine performance has been recently demonstrated (within 31 days). it is' prudent to allow a i brief period prior to-declaring the associated EDG inoperable. The 7 day Completion Time allows for further evaluation. resampling, and re analysis of the EDG fuel oil. | |||
'l~. FERMI UNIT 2 B 3.8.3-3 Revision 7. 06/18/99 L | |||
@ Diesel Fuel Oil and Starting Air B 3.8.3 BASES ACTIONS (continued) h! . | |||
With the new fuel oil pro)erties defined in the Bases for l | |||
$l SR 3.8.3.2 for new fuel t1at has already been added to a required EDG storage tank not within the required limits a l period of 30 days from the time of obtaining new fuel oil I sample results is allowed for restoring the stored fuel oil l properties. This period provides sufficient time to test the stored fuel oil to determine that the new fuel oil, when mixed with previously stored fuel oil, remains acceptable. | |||
or to restore the stored fuel oil properties. This restoration may involve feed and bleed procedures. ; | |||
filtering, or combination of these procedures. Even if a. | |||
EDG start and load was required during this time interval and the fuel oil properties were outside limits. there is I high likelihood that the EDG would still be capable of | |||
; performing its intended function. | |||
l M A With a Required Action and associated Completion Time not l met, or the stored diesel fuel oil or starting air subsystem not within limits for reasons other than addressed by "l Conditions A through C. the associated EDG may be incapable i of performing its intended function and must be immediately I | |||
declared inoperable. | |||
SURVEILLANCE SR 3.8.3.1 REQUIREMENTS This SR provides verification that there is an adequate inventory of fuel oil in the storage tanks of each required EDG to support each EDG's operation for 7 days at full load. | |||
The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. | |||
The 31 day frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and unit operators would be aware of any large uses of fuel oil during this period. | |||
v l l FERMI UNIT 2 B 3.8.3 -4 Revision 7 06/18/99 e | |||
l Diesel Fuel Oil and Starting Air | |||
@l B 3.8.3 BASES SURVEILLANCE REQUIREMENTS (continued) gl SR 3.8.3.2 , | |||
The tests of fuel oil prior to addition to the storage tank l are a means of determining whether new . fuel oil is of the ! | |||
appropriate grade and has not been contaminated with ! | |||
substances that would have an immediate detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the fuel oil may be added to the storage tanks without concern for contaminating the entire volume of fuel oil in the storage tanks. These tests are to be conducted prior to adding the new fuel to the storage tank (s), but in no case is the time between sampling (and associated results) of new fuel and addition of new fuel oil to the storage tank to exceed 31 days. The tests, limits, and applicable ASTM Standards for the new fuel oil tests listed in the Emergency Diesel Generator Fuel Oil Testing Program of Specification 5.5 are as follows: | |||
: a. Sample the new fuel oil in accordance with ASTM D4057 88 (Ref. 6) h b. Verify that the sample has an API Gravity of within 0.3 degrees at 60*F or a specific gravity of within 0.0016 at 60/60*F. when compared to the suppliers certificate, or an absolute specific gravity at 60/60*F of a 0.83 and s 0.89 or an API gravity at 60'F of a 27* and 5 39*. Also, verify in accordance with the tests specified in ASTM D975 91 (Ref. 6) a kinematic viscosity at 40*C of a 1.9 centistokes and s 4.1 centistokes, and a flash point of a 125'F: and | |||
: c. Verify that the new fuel oil has a clear and bright appearance with proper color when tested in accordance with ASTM D4176 86 (Ref. 6). | |||
Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the LC0 since the fuel oil is not added to the storage tanks. | |||
Following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in Table 1 of ASTM D975 91 (Ref. 6) are met for new fuel oil when tested in accordance with ASTM D975 91 (Ref. 6), except that the analysis for sulfur may be performed in accordance with ASTM D1552 90 (Ref. 6) or ASTM D2622 87 (Ref. 6). | |||
v l FERMI UNIT 2 B 3.8.3 - 5 Revision 7 06/18/99 i | |||
I L | |||
. h' Diesel Fuel Oil and Starting Air B 3.8.3 4 | |||
BASES SURVEILLANCE-REQUIREMENTS (continued) | |||
These additional analyses are required by Specification ! | |||
'5.5.9, " Emergency Diesel Generator Fuel Oil Testing ; | |||
Program " to be performed within 31 days following sampling ) | |||
and addition. This 31 days is intended to assure: 1) that | |||
-the sample taken is not more than 31 days old at the time of adding the fuel oil to the storage tank, and 2) that the results of a new fuel oil sample (sample obtained prior to , | |||
addition but not more than 31 days prior to) are obtained ' | |||
-within 31 days after addition. The 31 day period is i acce) table because the fuel oil properties of interest, even if t1ey were not within stated limits, would not have an immediate effect on EDG operation.. This Surveillance ensures the availability of high quality fuel oil for the required EDGs. | |||
Fuel oil degradation during long term storage shows up as an 'l increase in particulate, mostly due to oxidation. The I presence of particulate does not mean that the fuel oil will. | |||
not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel 011' injection equipment, however, which can cause engine failure. | |||
Particulate concentrations should be determined in , | |||
accordance with ASTM D2276 88 (Ref. 6) Method A. This ! | |||
method involves a gravimetric determination of total ~ | |||
particulate concentration in the fuel oil and has a limit of 10 mg/1. It is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing. | |||
The Frequency of this test takes into consideration fuel oil degradation trends that indicate that particulate concentration is unlikely to change significantly between Frequency intervals, h- SR 3.8.3.3 This Surveill'ance ensures that, without the aid of the refill compressor, sufficient air start capacity for each ' | |||
EDG is available. The system design requirements provide for a minimum of five engine start cycles without recharging. The pressure specified in this SR is intended to reflect the-lowest-value at which the five starts can be accomplished. | |||
The 31 day Frequency takes into account the capacity, capability, redundancy.-and diversity of the AC sources and l c FERMI -' UNIT. '2 - B 3.8.3 - 6 Revision 7.. 06/18/99 | |||
l h Diesel Fuel Oil and Starting Air B 3.8.3 BASES > | |||
SURVEILLANCE REQUIREMENTS (continued) | |||
< 1 other indications available in the control room, including. ) | |||
- alarms, to alert the operator to below normal air start pressure. | |||
h SR' 3.8.3.4-Microbiological fouling is a' major cause of fuel oil i degradation. There are numerous bacteria that can grow in I fuel oil and cause fouling. but all must have a water environment in order to survive. Removal of water from the required EDG fuel storage tanks once every 31 days eliminates the necessary environment for bacterial survival. | |||
This is the most effective means of controlling i microbiological fouling. In addition, it eliminates the I potential .for water entrainment in the fuel oil during EDG operation. Water may come from any of several sources. I | |||
-including condensation, ground water, rain water. | |||
contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily i represent failure of this SR, provided the accumulated water | |||
,. is removed during performance of the Surveillance. | |||
I i | |||
REFERENCES 1. UFSAR. Section 9.5.4.- | |||
: 2. Regulatory Guide 1.137. | |||
: 3. ANSI N195. 1976. | |||
: 4. .UFSAR. Chapter 6. | |||
: 5. UFSAR. Chapter 15. | |||
: 6. -ASTM Standards: D4057 88: D975-91: D4176 86: D1552 90: | |||
D2622 87: and D2276 88. | |||
l FERMI. - UNIT 2 B 3.8.3 -7 Revision 7 06/18/99 L | |||
DC Sources-Operating B 3.8.4 BASES BACKGROUND (continued) | |||
Each DC battery subsystem is separately housed in a | |||
. ventilated room a) art from its charger and distribution cente;rs. Each su) system is located in an physically and electrically from the othe, rarea separated subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels. | |||
The batteries for DC electrical power subsystems are sized 4 to produce required capacity at 80% of nameplate rr.'ing. | |||
(n corresponding to warranted capacity at end of life cyt.1es | |||
: a. and the 100% design demand. The minimum design voltage ' | |||
{ limit is 105/210 V. | |||
Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation. while at the same time maintaining its battery bank fully charged. | |||
Each battery charger has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 24 hours while supplyin0 normal steady state loads (Ref.11). | |||
APPLICABLE The initial conditions of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses in the UFSAR. Chapter 6 (Ref. 4) and Chapter 15 (Ref 5). assume that Engineered Safety Feature (ESF) systems are OPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the EDGs, emergency auxiliaries and control and switching during all MODES of operaticr. The OPErJSILITY of the DC subsystems is consistent with the initidi assumptions of the accident analyses and is based upon meeting the design basis of the unit. This includes maintaining sufficient DC sources OPERABl.E during accident conditions in the event of: | |||
: a. An assumed loss of all offsite AC power or all onsite AC power; and | |||
: b. A worst case single failure. | |||
i The DC sources satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). | |||
4 j FERMI -' UNIT 2 B 3.8.4- 2 Revision 7 06/18/99 | |||
DC Sources-0perating B 3.8.4 BASES LC0 . The DC electrical power subsystems-with each 'DC subsystem 1 | |||
.. consisting of two 130 VDC batteries in series, two battery J charpers,.and the corresponding control equi ment and | |||
. interconnecting cabling supplying power to tw associated bus, are required to be OPERABLE to ensure the-availability 4 of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (A00) or a postubted DBA. Loss of any DC electrical power subsystes does not prevent the minimum safety function from being performed (Ref. 3). | |||
APPLICABILITY The DC electrical power sources are required to be OPERABLE in MODES 1, 2, and 3 to ensure safe unit operation and to ensure that: | |||
: a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of A00s or. abnormal transients: and | |||
: b. Adequate core cooling is provided, and containment integrity and other vital functions are maintained in the event of.a postulated DBA. | |||
The DC electrical power requirements for MODES 4 and 5 are addressed in the Bases for LC0 3.8.5, "DC Sources-Shutdown." | |||
-ACTIONS A.1 and B.1 Conditions A and B represent one division with a loss of ability to completely respond to an event, cnd a potential loss of ability.to remain energized during normal operation. | |||
If one of the re inoperable (e.g. ,quired DC electrical inoperable power subsystems battery, inoperable battery is charger (s), or inoperable battery charger and associated inoperable battery). the remaining DC electrical power subsystems have tne capacity to support a safe shutdown and to mitigate an accident condition. A subsequent worst case single failure could, however. result in the loss of minimum necessary DC electrical subsystems to mitigate a worst case accident. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the hlFERMIUNIT2 B 3.8.4 -3 Revision 7 06/18/99 i ) | |||
r | |||
]m DC Sources-0perating B 3.8.4 | |||
(- i i | |||
BASES | |||
. ACTIONS (continued) . | |||
potential for com)lete loss of DC power to the affected- | |||
. division. The 41our Completion Time (Required Action A.1) for restoration of an inoperable battery charger allows time to replace the inoperable charger with an OPERABLE spare battery charger, if available. The four hour limit is reasonable based on the remaining capability of the battery , | |||
to carry the loads for this period. The 2 hour limit for l Required Action B.1 is consistent with the allowed time for 1 an inoperable DC Distribution System division. The 2 hour Completion Time is based on Regulatory Guide 1.93 (Ref. 6) and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown. | |||
C.1 and C.2 If the station service DC ' electrical power subsystem cannot be restored to OPERABLE status within the required Completion Time.-the unit must be brought to a MODE in which the LC0 doe not apply. To achieve this status, the unit must be brought to at least MODE.3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the l required plant conditions from full power conditions in an j orderly manner and without challenging plant systems. The ' | |||
Completion mae to bring the unit to MODE 4 is consistent I with the time required in Regulatory Guide 1.93 (Ref. 6). | |||
. SURVEILLANCE SR- 3.8.4.1 REQUIREMENTS l Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effecti'leness of the ; | |||
charging system and the ability of the batteries to perform their intended function. . Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a batiery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are | |||
. consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with , | |||
manufacturer recommendations and IEEE 450 (Ref. 7). ; | |||
- gFERMIUNIT2 B 3.8.4 -4 Revision 7, 06/18/99 L _ | |||
L i | |||
DC Sources-Operating ! | |||
B 3.8.4 l i | |||
l BASES- . | |||
i SURVEILLANCE REQUIREMENTS'(continued) | |||
SR 3.8.4.2-Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each | |||
; inter-cell and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. | |||
The connection resistance limits procedurally established , | |||
for this SR are no more than 20% above the resistance as l measured during installation and not above the ceiling value established by the manufacturer. This provides conservative measures to assure the Technical ~ Specification limit is not exceeded. | |||
The Frequency for these inspections, which can detect conditions that can cause power losses due to resistance heating.- is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends. | |||
SR 3.8.4.3- . | |||
Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.. The presence of physical damage or d deterioraticn does not necessarily represent a failure of J this SR. provided an evaluation determines that the physical 4 , | |||
damage or deterioration does not affect the OPERABILITY of the battery (its ability to perform its design function). | |||
The 18 month Frequency is based on engineering judgement, taking intn consideration the desired plant conditions to ' | |||
perform the Surveillance. -Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable frou a standpoint of maintaining reliability. | |||
.s | |||
- l - FERMI . UNIT _2 B 3.8.4 - 5 Revision 7, 06/18/99 | |||
f B tery Cell Parameters B 3.8.6 BASES SURVEILLANCE REQUIREMENTS (continued) | |||
Category C defines the limits for each connected cell. | |||
These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function and maintain a margin of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and the battery must be declared inoperable. | |||
l The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value for voltage is based on IEEE 450 (Ref. 3), which ; | |||
states that a cell voltage of 2.07 V or below, under float - | |||
conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement. | |||
,' The Category C limit on average specific gravity a 1.190. is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit, it is required that the specific gravity foi each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery. | |||
M 4 Footnote (b) to Table 3.8.6-l'is applicable to Category A. | |||
Ql B, and C specific gravity. Footnote (b) of Table 3.8.6-1 , | |||
i requires the above mntioned correction for electrolyte level and temperature. | |||
Because of specific gravity gradients that are produced during the recharging process, delays of several days may occur while waiting for the specific gravity to stabilize. | |||
A stabilized charger current is an acceptable alternative to s)ecific gravity measurement for determining the state of n curge of the designated pilot cell. This phenomenon is | |||
,L discussed in IEEE 450 (Ref. 3). Footnote (c) to (l Table 3.8.6 1 is applicable to Category A and C. and allows the float charge current to be used as an alternate to specific gravity. | |||
l FERMI - UNIT 2 B 3.8.6- 6 Revision 7.. 06/18/99 i | |||
s .}} | |||
Latest revision as of 01:27, 13 November 2020
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| Issue date: | 06/24/1999 |
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Text
{{#Wiki_filter:- 1 INSERT THIS PAGEIN FRONT OF VOLUME 6 Volume 6 SECTION 3.5 Remove Replace 3.5.1 ITS pg 3.5-3 Rev 0 3.5.1 ITS pg 3.5-3 Rev 7 3.5.1 ITS pg 3.5-4 Rev 0 3.5.1 ITS pg 3.5-4 Rev 7 3.5.1 ITS pg 3.5-5 Rev 0 3.5.1 ITS pg 3.5-5 Rev 7 3.5.1 ITS pg 3.5-6 Rev 0 3.5.1 ITS pg 3.5-6 Rev 7 3.5.1 ITS pg 3.5-7 Rev 0 3.5.1 ITS pg 3.5-7 Rev 7 3.5.1 ITS pg 3.5-8 Rev 0 -- B3.5.1 ITS pg B 3.5.1-3 Rev 0 B3.5.1 ITS pg B 3.5.1-3 Rev 7 B3.5.1 ITS pg B 3.5.19 Rev 0 B3.5.1 ITS pg B 3.5.1-9 Rev 7 B3.5.1 ITS pg B 3.5.1-11 Rev 0 B3.5.1 ITS pg B 3.5.1-11 Rev 7 B3.5.1 ITS pg B 3.5.1-13 Rev 0 B3.5.1 ITS pg B 3.5.1 13 Rev 7 B3.5.1 ITS pg B 3.5.1-17 Rev 0 B3.5.1 ITS pg B 3.5.1-17 Rev 7 3.5.1 CTS M/U (3/4 3-23) pg 1 of 10 3.5.1 CTS M/U (3/4 3-23) pg i of 10 Rev 7 3.5.1 CTS M/U (3/4 4-2) pg 2 of 10 3.5.1 CTS M/U (3/4 4-2) pg 2 of 10 Rev 7 3.5.1 CTS M/U (3/4 5-3) pg 5 of 10 3.5.1 CTS M/U (3/4 5 3) pg 5 of 10 Rev 7 3.5.1 CTS hW (3/4.7-3) pg 8 of 10 3.5.1 CTS M/U (3/4 7-3) pg 8 of 10 Rev 7 3.5.1 DOCS pg 6 Rev 0 3.5.1 DOCS pg 6 Rev 7 3.5.1 DOCS pg 7 Rev .0 3.5.1 DOCS pg 7 Rev 7 3.5.1 DOCS pg 8 Rev 0 3.5.1 DOCS pg 8 Rev 7 3.5.1 DOCS pg 9 Rev 0 3.5.1 DOCS pg 9 Rev 7 3.5.1 DOCS pg 10 Rev 0 3.5.1 DOCS pg 10 Rev 7 3.5.1 DOCS pg 11 Rev 0 3.5.1 DOCS pg 11 Rev 7 j 3.5.1 DOCS pg 12 Rev 0 3.5.1 DOCS pg 12 Rev 7 3.5.1 NUREG M/U pg 3.5-2 3.5.1 NUREG M/U pg 3.5-2 Rev 7 3.5.1 NUREG M/U pg 3.5-3 3.5.1 NUREG M/U pg 3.5-3 Rev 7 3.5.1 NUREG M/U pg 3.5-4 (insert) Rev 0 3.5.1 NUREG M/U pg 3.5-4 (insert) Rev 7 3.5.1 NUREG M/U pg 3.5-5 3.5.1 NUREG M/U pg 3.5-5 Rev 7 B3.5.1 NUREG M/U pg B3.5-3 B3.5.1 NUREG M/U pg B3.5-3 Rev 7 B3.5.1 NUREG hW pg B3.5-8 B3.5.1 NUREG hW pg B3.5-8 Rev 7 ' B3.5.1 NUREG M/U pg B3.5 9 (insert) Rev 0 B3.5.1 NUREG M/U pg B3.5-9 (insert) Rev 7 B3.5.1 NUREG M/U pg B3.5-11 B3.5.1 NUREG M/U pg B3.5-11 Rev 7 ! B3.5.1 NUREG hW pg B3.5-12 B3.5.1 NUREG hW pg B3.5-12 rev 7 B3.5.1 NUREG M/U pg B3.5-15 B3.5.1 NUREG M/U pg B3.5-15 Rev 7 9906290213 990624 PDR ADOCK 05000341 _ P PDR Rev 7 06/18/99 m
t Volume 6 SECTION 3.5 (cont'd) . Remove Replace 3.5.1 JFD's pg 2 Rev 0 3.5.1 JFD's pg 2 Rev 7 3.5.1 JFD's pg 3 Rev 0 3.5.1 JFD's pg 3 Rev 7 3.5.1 NSHC pg 10 Rev 0 3.5.1 NSHC pg 10 Rev 7 3.5.2 ITS pg 3.5-8 Rev 7 3.5.2 ITS pg 33 9 Rev 0 3.5.2 ITS pg 3.5-9 Rev 7 3.5.2 ITS pg 3.5 10 Rev 0 3.5.2 ITS pg 3.5-10 Rev 7 3.5.2 ITS pg 3.5-11 Rev 0 3.5.2 ITS pg 3.5-11 Rev 7 3.5.2 ITS pg 3.5-12 Rev 0 - B3.5.2 ITS pg B 3.5.2-4 Rev 0 B3.5.2 ITS pg B 3.5.2-4 Rev 7 B3.5.2 ITS pg B 3.5.2-5 Rev 0 B3.5.2 ITS pg B 3.5.2-5 Rev 7 B3.5.2 ITS pg B 3.5.2-6 Rev 0 B3.5.2 ITS pg B 3.5.2-6 Rev 7 3.5.2 GS M/U (3/4 5-3) pg 1 of 8 3.5.2 GS M/U (3/4 5-3) pg 1 of 8 Rev 7 3.5.2 CTS M/U (3/4 5-4) pg 2 of 8 3.5.2 GS M/U (3/4 5-4) pg 2 of 8 Rev 7 3.5.2 CTS M/U (3/4 5-6) pg 3 of 8 3.5.2 CS M/U (3/4 5-6) pg 3 of 8 Rev 7 3.5.2 CTS M/U (3/4 5-8) pg 5 of 8 3.5.2 CS M/U (3/4 5-8) pg 5 of 8 Rev 7 3.5.2 CTS M/U (3/4 8-15a) pg 8 of 8 3.5.2 GS M/U (3/4 8-15a) pg 8 of 8 Rev 7 3.5.2 DOCS pg 2 Rev 0 3.5.2 DOCS pg 2 Rev 7 3.5.2 DOCS pg 3 Rev 1 3.5.2 DOCS pg 3 Rev 7 3.5.2 DOCS pg 4 Rev 0 3.5.2 DOCS pg 4 Rev 7 3.5.2 DOCS pg 5 Rev 0 3.5.2 DOCS pg 5 Rev 7 3.5.2 DOCS pg 6 Rev 0 3.5.2 DOCS pg 6 Rev 7 3.5.2 DOCS pg 7 Rev 0 3.5.2 DOCS pg 7 Rev 7 3.5.2 DOCS pg 8 Rev 0 3.5.2 DOCS pg 8 Rev 7 l 3.5.2 DOCS pg 9 Rev 7 3.5.2 NUREG M/U pg 3.5-9 3.5.2 NUREG M/U pg 3.5-9 Rev 7 3.5.2 NUREG M/U pg 3.5-9 (insen) Rev 0 3.5.2 NUREG M/U pg 3.5-9 (insen) Rev 7 3.5.2 NUREG M/U pg 3.5-10 3.5.2 NUREG M/U pg 3.510 Rev 7 3.5.2 NUREG M/U pg 3.5-20 3.5.2 NUREG M/U pg 3.5-20 Rev 7 { 3.5.2 NUREG M/U pg 3.5-21 3.5.2 NUREG M/U pg 3.5 21 Rev 7 3.5.2 NUREG M/U pg 3.5-21 (insen) Rev 0 3.5.2 NUREG M/U pg 3.5-21 (insen) Rev 7 f 3.5.2 NUREG M/U pg 3.5-22 3.5.2 NUREG M/U pg 3.5-22 Rev 7 3.5.2 JFD's pg i Rev 0 3.5.2 JFD's pg i Rev 7 ; 3.5.2 NSHC pg 3 Rev 7 l l Rev 7 06/18/99 a
i Volunae 6 SECTION 3.5 (cont'd) Reasove Replace 3.5.2 NSHC pg 4 Rev 7 3.5.2 NSHC pg 5 Rev 7 3.5.2 NSHC pg 6 Rev 7 3.5.3 ITS pg 3.5-12 Rev 7 3.5.3 ITS pg 3.5-13 Rev 0 3.5.3 ITS pg 3.5-13 Rev.7 3.5.3 ITS pg 3.5-14 Rev 0 3.5.3 ITS pg 3.5-14 Rev 7 l 3.5.3 ITS pg 3.5-15 Rev 0 -- l l i l \ i i l Rev7 06/18/99 (_
1 ECCS-Operating 3.5.1 1 ACTIONS (continued) I CONDITION REQUIRED ACTION COMPLETION TIME H. One ADS valve H.1 Restore ADS valve to 72 hours inoperable. OPERABLE status. AND @ D Condition A or H.2 Restore .cw pressure 72 hours 4 Condition B entered. ECCS injection / spray 4 subsystem (s) to OPERABLE status. I. Two or more ADS valves I.1 Be in MODE 3. 12 hours inoperable. AND 2 I.2 Reduce reactor steam 36 hours Required Action and come pressure to associated Completion s 150 psig. Time of Condition E, F. G or H not met. I J. Two or more low J.1 Enter LC0 3.0.3. Immediately 1 pressure ECCS injection / spray subsystems ino>erable for reasons otler than Condition B or C. 2 HPCI System and one or more ADS valves p inoperable.
& 5 Condition C and Condition G entered.
_l FERMI - UNIT 2' 3.5 3 Revision 7 06/18/99
)
ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify correct voltage and breaker 7 days i alignment to the LPCI swing bus. SR 3.5.1.2 - ---- - -- - NOTE------ - -- --- - -- When LPCI is placed in an inoperable status solely for performance of this SR. or when the LPCI swing bus automatic throwover scheme is inoperable due to EDG-12 being paralleled to the bus for required testing. entry into Conditions and Required Actions
}l may be delayed up to 12 hours for completion of the required testing.
Perform a functional test of the LPCI swing 31 days bus automatic throwover scheme. SR 3.5.1.3 Verify for each ECCS injection / spray 31 days subsystem the piping is filled with water from the pump discharge valve to the injection valve. (continued) l FERMI UNIT 2 3.5 4 Revision 7 06/18/99
l.' L l ECCS-Operating l 3.5.1 ; f r SURVEILLANCE REQUIREMENTS (cor.tinued) { SURVEILLANCE FREQUENCY SR 3.5.1.4 -- - -- ------ NOTE---- -- ---- - ---- Low pressure coolant injection (LPCI)
. subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3. and for 4 hours after exceeding the RHR cut-in permissive pressure in MODE 3.
if capeble of being manually realigned and not otherwise inoperable. Verify each ECCS injection / spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. I SR 3.5.1.5 Verify primary containment pneumatic supply 31 days pressure is a 75 psig. I SR 3.5.1.6 Verify the RHR System power operated cross 31 days tie valve is open.
?>R 3.5.1.7 04l Verify each recirculation pump discharge valve cycles through one comr':'e cycle of 18 months full travel or is de-energiz;d n the closed position.
(continued) l l FERMI UNIT 2 3.5 5 Revision 7 06/18/99
p l l. ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY l SR 3.5.1.8 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head with the
- corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RAE PUMPS PRESSURE OF Core Spray = 6350 gpm 2 = 100 psig LPCI = 10.000 gpm 1 = 20 psig SR 3.5.1.9 - - ---- --
NOTE - - - --- -- Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify, with reactor pressure s 1045 and In accordance
= 945 psig, the HPCI pump can develop a with the flow rate = 5000 gpm against a system head Inservice corresponding to reactor pressure. Testing Program SR 3.5.1.10 - - -
- NOTE - ---- --
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify with reactor pressure s 215 psig. 18 months the HPCI pump can develop a flow rate
= 5000 9pm against.a system head corresponding to reactor pressure.
(continued) l g l. FERMI. . UNIT 2 3.5-6 Revision 7 06/18/99 j
ECCS - Operating 3.5.1
. SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.11 -- --- -- NOTE -- - - - -- --- Vessel injection / spray may be excluded. i Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated automatic initiation signal. 1 SR 3.5.1.12 - - ----- -----
-NOTE- ----- ------ ----
Valve actuation may be excluded. Verify the ADS' actuates on an actual or 18 months simulated automatic initiation signal. 1 SR 3.5.1.13 ----
-- -- - -- NOTE - -- - --- - -
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify each ADS valve opens when manually 18 months actuated. SR 3.5.1.14 ----- - - --
--NOTE-- - - -----
ECCS instrumentation response times are not required to be measured. Verify ECCS RESPONSE TIME is within limits. 18 months s i FERMI UNIT 2 3.5 7 Revision 7 06/18/99
ECCS -Operating B 3.5.1 BASES BACKGR0lA4 (continued) provided for the four LPCI pumps to route water from the suppression pool, to allow testing of the LPCI pumps without l injecting water into the RPV. These test lines also provide.
. suppression pool cooling capability, as described 'in LCO 3.6.2.3,."RHR Suppression Pool Cooling."
^
The HPCI System (Ref. 3) consists of a steam driven turbine pus) unit, piping, and valves to provide steam to the tur)ine, as well as piping and valves to transfer water from the suction source to the core via the feedwater system line, where the coolant.is distributed within the RPV through the feedwater sparger. Suction piping for the system is provided from the CST and the suppression pool. Pump suction for HPCI is normally aligned to the CST source to minimize injection of suppression pool water into the RPV. However, if the CST water supply is low, or if the suppression pool level is high, an automatic transfer to the suppression pool water source ensures a water supply for continuous operation of .the HPCI System. The steam supply to the HPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve. The HPCI System is designed to provide core cooling for a wide range of reactor pressures ~ (165 psig to 1146 psig). Upon receipt of an initiation signal, the HPCI turbine stop valve and turbine control valve open simultaneously and the turbine accelerates to a specified speed. As the HPCI flow increases, the turbine governor valve is automatically adjusted to maintain design flow. Exhaust steam from the ! HPCI turbine is discharged to the suppression pool. A full flow test line is provided to route water to the CST to allow tcsting of the HPCI System during normal operation j without injecting water into the RPV. i The ECCS pumps are provided with minimum flow bypass lines, which discharge to the suppression pool. The valves in these lines automatically o>en to prevent pump damage due to overheating when other disc 1arge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, all ECCS pump discharge lines are filled with water. The LPCI and CS System discharge lines i are kept full of water using a " keep fill" system. The core l spray lines are kept charged with demineralized water and the RHR lines are kept charged with condensate water by a pressure regulating valve. The HPCI System is normally l l l FERHI > UNIT 2 B 3.5.1-3 Revision 7. 06/18/99 i m_ . -. - ___
l l 1 ECCS-Operating B 3.5.1 i BASES
' ACTIONS-(continued) i L1 '
The LC0 requires five ADS valves to be OPERABLE in order to provide the ADS function. - The ECCS analyses'are performed with the initial condition of one ADS valve out of service (Ref. 13). Per this analysis, operation of only four ADS volves will provide the required depressurization. However, ,
.overall reliability of the ADS is reduced, because a single .
failure in the OPERABLE ADS valves could result in a ! reduction in depressurization capability. Therefore. ! operation is only allowed for a limited time. The 14 day Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience. ' 7 any on low Itj one LPCI' pump i ressureECCSinjection/skraysubsystem,or both LPCI subsystems. i inoperable in W addition to one inoperable ADS valve. adequate core cooling is ensured by the OPERABILITY of HPCI and the remaining low pressure ECCS injection / spray subsystem. However, overall ECCS reliability is reduced because a single active component failure concurrent with a design basis LOCA could result in the minimum required ECCS equipment-not being available. Since both a high pressure system (ADS) and low pressure subsystem (s) are inoperable, a more restrictive Completion Time of 72 hours is required to restore either 4 the low pressure ECCS subsystem (s) or the ADS valve to i OPERABLE status. This Completion Time is based on a ! reliability study cited in Reference 12 and has been found to be acceptable through operating experience. L 1 and I .2 , 'If any Required Action and associated Completion Time of ; Condition E. F. G or H is not met, or if two or more ADS , L valves are inowrable, the plant must be brought to a ' condition in w11ch the LCO does not apply. To achieve this l status, the plant must be brought to at least MODE 3 within l 12 hours and reactor steam dome pressure reduced to i s 150 psig within 36 hours. 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. u i
- l-FERMI' UNIT 2 83.5.1-9' Revision 7-. 06/18/99
ECCS - Operating B 3.5.1 i BASES
-SURVEILLANCE REQUIREMENTS (continued) discharge valves, and LPCI cross tie valve. The swing bus automatic throwover- scheme must be OPERABLE for both LPCI subsystems-to be OPERABLE. The 31 day Frequency has been found acceptable based on engineering judgment and operating experience.
This SR is modified by a Note to indicate that when this test results in LPCI inoperability solely for performance of this required Surveillance, or when the LPCI swing bus automatic throwover scheme is inoperable due to EDG 12 being paralleled to the bus for required testing, entry into associated Conditions and Required Actions may be delayed.
-si .for up to 12 t m until the required testing is completed.
Upon completion vi the Surveillance or expiration of the
- g. - 12 hour allowance the swing bus must be returned to OPERABLE
-status or the applicable Condition entered and Required Actions taken.
SR 3.5.1.3 The flow path piping has the potential to develop voids and pockets of entrained air. Maintaining the pump discharge lines of the HPCI System, CS System, and LPCI subsystems full of water ensures that the ECCS will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent a water hammer following an ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. The 31 day Frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls
. governing system operation, and operating experience.
SR 3.5.1.4 LVerifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal'is allowed to be in a non accident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation: rather, it involves
.y
;[ FERMI UNIT 2 B 3.5.1- 11 Revision 7 06/18/99
u ECCS-Operating B 3.5.1 BASES
- SURVEILLANCE REQUIREENTS (continued)
SR 3.5.1.6 Verification every 31 days that the Rm System power' 1 operated cross tie valve is open ensures that each LPCI . subsystem remains ca recirculation loop. pable A valveof injection into the- selected that is inaccessible may be verified by administrative controls. If a RHR System cross-tie valve is not o)en. both LPCI subsystems must be considered inopera)le. The 31 day Frequency has been found acceptable, considering that these valves are under strict administrative controls that will ensure the valves continue to remain open. SR 3.5.1.7 Cycling the recirculation pump discharge valves through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will close when required. Upon initiation of an automatic LPCI subsystem injection signal, these valves are required to be closed to ensure full LPCI subsystem flow injection in the reactor via the recirculation jet pumps. De energizing the valve in the closed position will also ensure the proper flow path for the LPCI subsystem. Acceptable methods of de ener valve include de energizing breaker control power,gizing racking the out the breaker or removing the breaker.
' The specified Frequency is 18 months. Verification each 18 months is an exception ~to the normal Inservice Testing Program generic valve cycling Frequency of 92 days, but is considered acceptable due to the demonstrated reliability of these valves. If the valve is inoperable and in the open position, both LPCI subsystems must be declared inoperable.
l-FERMI UNIT 2- B 3.5.1 - 13 Revision 7 06/18/99
ECCS -Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) which this SR is to be performed is a 850 psig (the pressure recommended by the valve manufacturer). Adequate steam flow is represented by turbine bypass valves open at least 20%. O/}] Reactor startup is allowed prior to performing this SR because valve OPERABILITY and the setpoints for overpressure. protection are verified, per ASME requirements ~. prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. The 12 hours allowed for manual actuation after the required 3ressure and flow are reached is sufficient to achieve sta)le conditions and l provides adequate time to complete the Surveillance. { SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TEST performed ' in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function. The Frequency is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a )lant outage. Operating
~ experience has shown that t1ese components usually pass the SR when performed at the 18 month Frequency, which is based i on the refueling cycle. Therefore, the Frequency was l concluded to De acceptable from a reliability standpoint.
SR 3.5.1.14 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Response time testing acceptance criteria are included in Reference 15. This SR is modified by a Note stating that the ECCS instrur,entation response times are not required to be measured. The contribution of the instrument response times to the over all ECCS response time are assumed based on guidance of Reference 16. I The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency. l FERMI UNIT 2 B 3.5.1 - 17 Revision 7. 06/18/99 l
5pecuFimou 2. S'. I SoSu.SpecNc4Nm.3.35./) INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMEN T ON tiMITING CONDITION FOR OPERATION 6 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2. APPLICABILITY: 'As shown in Table 3.3.3-1. ACTION:
- a. Vith an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted g consistent with the Trip Setpoint value,
- b. With one or more ECCS actuation instrumentation channels M 4 3l inoperable, take the ACTION required by Table 3.3.3-1.
Q c. With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within:
- 1. 7 days, provided that the HPCI and RCIC systems are OPERABLE, otherwise,
- 2. 72 hours.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours. SURVEILLANCE REOUTREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK', CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1. 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of l1 channels shall be perfomed at least once per 18 months.* fR3.5.l.N 4.3.3.1 The ECCS RESPONSE TIME of each ECCS trip function ** shall be j demonstrated to be within the limit at least once per 18 months. g i I l
@ for the diesel generator output breakers: Completion of logic system Sf *"g h% , functional testing, for the loss of power function, to positively verify that l the breaker reclosure permissive relay'(52xx) is re-energized by the '
3Od*i associated bus load shedding logic contact closing, rather than the 52XX t being re-energized by a parallel path, may be deferred and must be completed l no later than during the first plant outage after September 29, 1995. _ j SR 3.5.1.19 **ECCS actuation instromantation resoonto time need not be measured and may be (aisumeg to be tne/ design instrpfhentation respoffse time]
-'y l poTE
- FERMI - UNIT 2 3/4 3-23 Amendment No.199, JM,lli PAGE I 0F 10 8'" 7
specir-,cenW 5. 5 / [#so sce $cclOor4% 5.% / ) REACTOR COOLANT SYSTEM SURVETLLANCE RFOUIREMENTS 4.4.1.1.1 Each pump discharge valve shall be demonstrated OP8RABLE by ,th
.st 3.5.l.'? cycling each valve through at least one complete cycle of full travel at least once per 18 months.
h.1.1.2 DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in Su. operation, at least once per 12 hours verify that: ' SpeciMenh% 3'4 8 i a. THERMAL POWER is less than or equal to 67.2% of RATED THERMAL POWER, and
- b. The individual recirculation pump flow controller for the operating recirculation pump is in the Manual mode, and
- c. The speed of the operating recirculation pump is less than
( or equal to ~5% of rated pump speed. I 4.4.1.1.4 With one reactor coolant system loop not in operation with THERMAL POWER les:: than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase: M \q a. Less than or equal to 145*F between reactor vessel steam I"f space coolant and bottom head drain line coolant, and
- b. Less than or equal to 50*F between the reactor coolant 3.'I. ! within the loop not in operation and the coolant in the
/ reactor pressure vessel **, and
- c. Less than or equal to 50*F between the reactbr coolant
( within the loop not in operation and the operating loop.** 5
' Joe-creT.
l g u. [*Reouirement does not apply when the recirculation loop not ih operation is Grenfim kS isolated from the reactor pressure vessel. 3M.t FERMI . UNIT 2 3/4 4-2 Amendment No. 83. 59, 87, DB,1 w PAGE d 0F 10
Sp&c. lFacAT704 3,F.1 LSO See Spet\CcuWer. B.C.2 EMERGENCY CORE COOLING SYSTEMS tIMITING CONDITION FOR OPERATION (Continued) ACTION: (Continued)
- 3. F.1_ d. For the ADS: (ADOAcliersll) 1.
Mc7,on r (HPCI systeQ Oe CSS and the iPEIWith one of the a_bove reautred ADS system are OPERABLE, restore the A C '/7a d Ci inoPeraDie ADS valve to OPERABLE status within 14 days or be in at dCDON I least HOT SHUTDOWN within the next 12 hours and reduce reactor steam dome pressure to 4 150 psig within the next 24 hours. MC7 tom I 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam dome pressure to s 150 psig within the next 24 hours.
- e. With a CSS h sder AP, instrumentation channel inoperable annel to OPERABLE status with operable, restore d' k CSS head AP locally at least once per 72 hours hours; or detern ethh otherwise.
tthe as ciated CSS subsystem inoperabl f clare/ f.~ f ith an LPCI or 5 system discharge line " keep / filled" al M (,R,) instrumentatio operable. Derfom Surveillante Requirement)
.5.1.a.1.a.
g.
, the event an tcc5 system is ctuated and injects water into the eactor Coolant System, a Sp tal Report shall be prep ed and I' submitted to the Connissio pursuant to Specification .9.2 within 90 days describing the circ stances of the actuation d the total accumulated actuation c es to date. The current alue of the usage factor for each affee safety injection nozzle hall be provided in j
_Special Report enever its value exceeds .70 7
$URVElllANCE REOUTREMENTS 4.5.1 The emergency core cooling systems shall be demonstrated OPERABLE by:
- a. At least once per 31 days:
- 1. For the CSS, the LPCI system, and the HPCI system:
sA 3613 a) Verifying b entino Et the hiah 011nt lents that the system piping from the. pump discharse valve to t e system isoiation valve is filled with water.
.5R35.t.f b) Verifying that each valve, manual, power operated or automatic, in the flow path that is not lockedi sealed, or othentise secured in {
i position, is in its correct
- position.
g 3,q ,),6 2. For the LPCI system, verifying that the ross tie vaTve is open. l .(6/1165} [iExcept t%t an autytnatic valve r,dpable of automafic return tofts ECCS position g 3g,g,4when arJ/ CCS sion41 is present.4ay be in positi4n for another mode of operation]/ g l FERMI - UNIT 2 3/4 5-3 PAGE 5 0F 10 ggy 7 1
)
)
SPgccprc&noid 5.s .( PLANT SYSTEMS MioSc66fcc)hfdMA--3,7)
/
.. EMERGENCY EDUfPMENT COOLING WATER SYSTEM ,
A [so 6 4 fjou ) b'da d dh 8 ' tINITING CONDITION FOR OPERATION 3.7.1.2 'fwo independent emergency equipment cooling water (EECW) system subsystems shall be OPERABLE with each subsystem comprised of: , p6 ap "a. One OPERABLE EECW pump, and g'Qc
- b. An OPERABLE flow path capable of removing heat from the associated 3,9 safety-related equipment.
APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. 3, 4, and 5. 6(IlDE: L
- a. In OPERATIONAL CONDITION 1. 2 or 3, with one EECW system subsystem Aoperable:
.g 1. Within 2 hours:
68 L a) Verify that all required systems, subsystems, trains, N . components and devices that depend upon the remaining s, OPERABLE EECW system subsystem are also OPERABLE, and AC.Tto d d - [lb) Verify that s OPERABLE. d.k
' 5g (Otherwise", be in at least HOT SHUTDOWri within the next 12 hours and in COLD SHUTOOWN within the following 24 hours.
5pocikcAlh < 3.7 2. Declare the associated safety related equipment inoperable and take the ACTIONS required by the applicable Specifications. Ac r7og C, 3. a-4aoperabh EEC" ;y M ubsystem to OPERABLE Restore status w [itnin 14 hours or be in at least HOT SHU ACT70V D the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- b. In OPERATIONAL CONDITION 4 or 5, determine the OPERABILITY of the safety-related equipment associated with an inoperable EECW system 5fecibcaNon subsystem and take any ACTIONS required by the applicable J.7 Specifications.
A.
'Y[l;g,W/;yADSisnotrequiredtobeOPERABLEwhenreactorsteamdomepressureisless
/ than or equal to 150 PSIG.
"Except for an inoperable Drywell Cooling Unit, required by Specification 8
[QC#y 3.7.11 channel, or.an inoperable required primary by Specification containment 3.3.7.S, that depends oxygen raonitoring instrumentatio on the remaining U gE OPERABLE EECW system subsystem. In these cases, take the ACTION required by , 6[ Specification 3.7.11 for the inoperability of both required Drywell Cooling Units or Specification 3.3.7.5 for the inoperability of both required primary containment oxygen monitoring instrumentation channels. I FERMI UNIT 2 3/4 7 3 Amendment No. JJ Ef,132 PAGE F 0F 10 gev '7
,.i - -
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating M.2 CTS 4.5.1.d.1 requires only a functional test of the low pressure alarm circuit for the ADS pneumatic supply (refer to Discussion of lh Change "LR.2" for relocation of this requirement). However, no CTS requirement exists for verification of the necessary pneumatic supply pressure to assure ADS function. ITS SR 3.5.1.5 provides a more restrictive requirement by requiring verification of the
&ctual supply pressure once per 31 days. This change will have no negative impact on safety. and will provide increased assurance of ADS Operability.
TECHNICAL CHANGES LESS RESTRICTIVE
" Generic" LA.1 CTS LCO 3.5.1 includes details relating to system design, function, and Operability for the Core Spray System. the Low Pressure Coolant Injection System and the High Pressure Coolant Injection System. ITS 3.5.1 includes only a requirement for Operability and does not include the details of system design and specific Operability requirements. This is acceptable because these details do not impact the requirement to maintain the equipment Operable and the ITS definition for Operability ensures T that all equipment required to maintain Operability is o functioning. These details will be adequately defined and o ,
controlled in the Bases which require change control in - ' accordance with ITS 5.5.10. Bases Control Program. These details k j are not required to be in the ITS to provide adequate protection ; of.the public health and safety acceptable because these details ; do not impact the requirement to maintain the equipment Operable. LA.2 Not used. LA.3 Not used. l i LA.4 The following CTS details for performing Surveillances are not included in the ITS. These detailed methods for performing l Surveillances are moved to the Bases: ;
- a. CTS 4.5.1.a.1.a details a requirement for verifying that ,
the system is filled with water. "by venting at the high point vents": I
- b. CTS 4.5.1.a.1.b contains a footnote "*~ which details a '
requirement for the correct position of ECCS valves: FERMI - UNIT 2 6 REVISION 7, 06/18/99l ,
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating LA.4 -(continued)
- c. CTS 4.5.1.a.3 details a requirement for the HPCI pump flow controller to be in the correct position. The function of the flow controller is to provide the control signal to ensure correct positioning of the HPCI steam governor valve. 'ITS SR 3.5.1.4. requires all system valves be in their correct position, without separately detailing the HPCI pump flow controller. Therefore, as deta.iled in the Bases, the verification of the " correct position" of the governor valve is accomplished by proper flow controller positioning:
- d. CTS 4.5.1.b.1 and 4.5.1.b.2 details test line pressure requirements for the CSS and LPCI pumps:.
e.' CTS 4.5.1.b.3 and 4.5.1.c.2.a details requirements for verifying HPCI pump flow "in the test flow path" with a system head " including injection line losses":
- f. . CTS 4.5.1.c.2.b details requirements for verifying automatic HPCI system transfer:
- g. CTS 4.5.1.d.2.b details requirements for ADS pressure i testing:
- h. CTS 4.5.1.d.2.b.1'and 4.5.1.d.2.b.2 details requirements for verifying ADS valve open; and
- 1. CTS 4.8.3.1.2 details requirements for verifying automatic. j throwover scheme'for the AC power distribution system swing l bus.
These details can be ' adequately defined and controlled in the Bases, which require change control in accordance with Chapter 5 ) of the ITS. These details are not required to be in the ITS to provide adequate protection of.the public health and safety since the details in the ITS are adequate for assuring proper i performance of the required Surve111ances. 1 J FERMI' - UNIT 2 7 REVISION 7 06/18/99l
l DISCUSSION OF CHANGES ITS: SECTION 3.5.1 - ECCS-Operating
.'LA.5 CTS 4.3.3.3. note **. allows the response time for ECCS actuation instrumentation to be exempted from being tested with the value
" assumed to be.the design instrumentation response time." ITS
~
'SR 3.5.1.14 includes.a Note to specifically detail this allowance, however, the specific method of accounting for the response time (assuming the design sensor response) is relocated to the Bases. -
, This detail'of performance can be adequately controlled in k accordance With ITS 5.5.10. Bases Control Program. The relocation continues to provide adequate protection of the public health and safety since the requirement for the ECCS response time testing remains a Technical Specification requirement. LR.1 The following Actions and Surveillances of alarm only functions are not assumed in any accident analysis. Alarm only functions do not relate directly to the Operability requirements for the system. ITS does not specify indication-only or alarm-only to be Operable to support Operability of a system or component:
- a. CTS 3.5.1.e details a requirement for restoring an
!- inoperable CSS header differential pressure alarm;
- b. CTS 3.5.1.f details a requirement for performing an SR when a LPCI or CSS system " keep filled" alarm is inoperable: and )
- c. CTS 4.5.1.c.3 and 4.5.1.c.4 details requirements for performing Channel Calibrations on CSS and LPCI instrumentation.
Regulatory control of changes to these requirements (e.g.. Technical. Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since alarm-only functions do not relate directly to the l Operability requirements for the system or analysis assumptions. 1 _/ 1 l. L l FERMI UNIT 2 8' REVISION 7 06/18/99l 1
I I 1 DISCUSSION OF CHANGES ITS: SECTION 3.5.1 - ECCS-Operating LR.2 CTS 4.5.1.d.1 and 4.5.1.d.2.c require surveillance tests of ADS l pneumatic supply pressure alarm channels. ITS SR 3.5.1.5 replaces ! these with a requirement directly related to Operability of ADSi a l Surveillance to verify greater than a minimum supply pressure, which assures ADS Operability. The alarm only functions are not ! assumed in any accident analysis. Alarm-only functions do not j relate directly to the Operability requirements for the system. I These details of alarm surveillances are not required to be in the ITS to provide adequate protection of the public health and safety i since alarm only functions do not relate directly to the Operability requirements for the system. The replacement of these 3 Surveillances with ITS SR 3.5.1.5 is a more restrictive change (which is discussed here for clarity), which provides a more ) direct Surveillance of ADS Operability with no impact on safety. LR.3 CTS 3.5.1. Action 9. requires submitting a special report to the NRC following any ECCS actuation and injection of water into the j reactor coolant system. ITS does not retain the requirement for l this special report because reporting requirements are adequately l addressed by 10 CFR 50.73(a)(2)(iv). 10 CFR 50.73(a)(2)(iv) l requires an LER to be submitted for any event or condition that resulted in manual or automatic ECCS " actuation." Therefore, an ] a LER will cover any " actuation and injection" as is currently ! required by CTS 3.5.1. Action 9 An LER is required to be O f submitted within 30 days which also meets the Special Report J. j requirement of 90 days. CTS 3.5.1. Action 9. requirements governing the tracking and reporting to the NRC of accumulated Q l actuation cycles and the current value of the usage factor are accomplished in accordance with plant procedures. Compliance with ! 10 CFR 50.73(a)(2)(iv) and plant procedures will ensure that the NRC is informed of events as required. These details are not required to be in the ITS to provide adequate protection of the public health and safety because reporting requirements are adequately addressed by 10 CFR 50.73(a)(2)(iv). l TECHNICAL CHANGES - LESS RESTRICTIVE "Speci fic" l L.1 CTS 3.5.1. Action a.2 (loss of both CS subsystems). Action b.3 (LPCI cross connect closed) and Action b.4 (loss of both LPCI subsystems), require that the reactor be in Mode 3 within 12 hours and Mode 4 within 36 hours. Under the same conditions. ITS 3.5.1 Condition J. requires immediate entry into LC0 3.0.3. LC0 3.0.3 FERMI - UNIT 2 9 REVISION 7 06/18/99l
DISCUSSION OF CHANGES
-ITS: SECTION 3.5.1 - ECCS-Operating allows.13 hours to reach Mode 3 and 37 hours to reach Mode 4 and, therefore, is less restrictive. However, the ITS LC0 3.0.3 actions also include a more restrictive requirement: to be in' Mode 2 within 7 hours. The requirement to enter LCO 3.0.3 following the loss of both CS subsystems or the loss of both LPCI subsystems recognizes that a significant plant transient (reactor shutdown and cooldown)' will be performed without the required complement of emergency core cooling systems. Under these circumstances, entry into LC0 3.0.3 and the resulting associated requirements is appropriate. The additional hour allowed to reach Mode 3 and Mode .
4 is not significant and has no impact on the level of plant safety. Furthermore, any impact is offset by the associated more restrictive requirement to be in Mode 2 in 7 hours.
. L.2 . ITS 3.5.1 includes two new Actions. Action F is added for the condition of HPCI Inoperable coincident with: 1) one low pressure ECCS injection / spray. subsystem inoperable: 2) one LPCI pump in one or both LPCI subsystems inoperable: or 3) one CSS and one LPCI subsystem inoperable. Action H is added for.the condition of one ADS valve inoperable coincident with: 1) one low pressure ECCS ,
i_njection/ spray subsystem ~ inoperable: 2) one LPCI pump in one or l both LPCI subsystems inoperable: or 3) one CSS and one LPCI l subsystem inoperable. Both Action F and Action H require restoration.of either the inoperable high pressure (HPCI or ADS) ,
'or the inoperable low pressure ECCS system within 72 hours. This !
change is less restrictive than the same conditions addressed in ' CTS 3.5.1. Actions c and d, which would default to LC0 3.0.3. and require Mode 3 within 13 hours and Mode 4 within 37 hours. (Note ; that some specific combinations of ECCS inoperability addressed in this change are allowed in CTS action c. in accordance with footnote #. However, all combinations' are discussed as part of this overall'less restrictive change for completeness.) This change is acceptable because ITS 3.5.1. Condition F and Condition H. result in adequate ECCS systems available to respond to a design basis LOCA although the ability to tolerate a single failure may be lost. In Condition F, adequate core cooling is ensured by the Operability of the ADS and the remaining low pressure ECCS subsystems. However. ECCS reliability is reduced because a single failure in one of the remaining Operable subsystems concurrent with a LOCA may result in the ECCS not being r able to perform its' intended safety function. In Condition H, adequate core cooling is ensured by the Operability of HPCI and the remaining low pressure'ECCS injection / spray subsystems. However. ECCS reliability is reduced because a single failure
~
FERMI UNIT 2- -10 REVISION 7 06/18/99
l DISCUSSION OF CHANGES ITS: SECTION 3.5.1 - ECCS-Operating l concurrent with a LOCA could result in the minimum required ECCS equipment not being available. Therefore. ITS 3.5.1. Action F and Action H. require restoration of either the inoperable high pressure (HPCI or ADS) or the inoperable low pressure ECCS system within 72 hours. This Completion Time is based on a reliability study cited in memorandum from R.L. Baer (NRC) to V. Stello. l Jr.(NRC). " Recommended Interim Revisions to LCOs for ECCS l Components." December 1. 1975. This change is consistent with NUREG 1433. Rev. 1. L.3 CTS Actions (LCO 3.7.1.2. Action a.3 and LCO 3.5.1 Actions. Footnote
"#") for one CSS subsystem and one LPCI subsystem inoperable due to lack of EECW cooling, allow 72 hours to restore the inoperable EECW (and therefore the inoperable CSS and LPCI subsystems). However. ,
the CTS Actions for one CSS subsystem and one LPCI subsystem I inoperable for any other reason, requires immediate shutdown. The l ITS eliminate the restriction on the inoperabilities of CSS and LPCI l having to be due to lack of EECW cooling: allowing 72 hours for one CSS subsystem and one LPCI subsystem inoperable for any reason. In the condition of one CSS and one LPCI subsystem inoperable. provided all other safety related equipment is available to perform its function (which is assured by other ITS Specifications and the ITS Safety Function Determination Program). the remaining ECCS subsystems are adequate to perform the assumed ECCS function in the event of an accident. L.4 CTS 4.5.1.b.3 (HPCI high pressure flow verification). CTS 4.5.1.c.2.a (HPCI low pressure flow verification), and CTS 4.5.1.d.2.b (ADS valve manual operation) are modified by a footnote ~ allowing performance to be deferred until ~12 hours after reactor steam pressure is adequate to perform the test" but also states that the test is performed at 2 150 psig. This allowance to defer testing is based on the need to establish appropriate conditions for testing. The corresponding ITS SRs. 3.5.1.9. 3.5.1.10 and 3.5.1.13 are modified by a similar Note that allows deferring the performance of these tests until reactor steam pressure "and flow" are adequate to perform the test. This change is necessary because the CTS allowance to reach only the required reactor steam pressure only partially addresses the issue of
-adequate test conditions. Requiring performance of these tests before adequate steam flow can be maintained creates the potential I for an undesired reactor depressurization. This change is less
~
, restrictive because it may allow additional time before the tests are required to be performed. This change is acceptable because FERMI - UNIT 2 11 REVISION 7 06/18/99h
DISCUSSION OF CHANGES ITS: SECTION 3.5.1 ECCS-Operating the-allowance permits the test to be delayed until appropriate conditions are established and will not normally result in a significant delay in performing these tests. Additionally, the'
- Bases which detail the conditions defining " adequate pressure and flow" specify adequate pressure as 2 850 psig. This pressure is that recommended by the valve manufacturer and. represents clarification of the CTS presentation that states testing is done at 2 150 psig after " adequate pressure" to perform the test has been achieved.
L.5 CTS 4.8.3.1.2 and ITS SR 3.5.1.2. requires demonstration of the LPCI swing bus automatic transfer scheme. Performance of this test requires that the swing bus (and therefore both LPCI subsystems) be made inoperable. Additionally, performance of EDG surveillances that require the EDG to be paralleled to its bus, render the automatic throwover scheme inoperable. As a result. these tests would result in ITS requiring an intentional entry into LC0 3.0.3 (LC0 3.5.1. Condition J). To preclude this intentional LC0 3.0.3 entry, the ITS adds a Note to SR 3.5.1.2 allowing a 12 hour delay in entering the actions for the lq inoperability caused by performing these required Surveillances. Since this test: 1) is not expected to de-energize the swing bus: T
- 2) is performed under control of a dedicated individual in communication with the control room operator: and 3) results in the period of inoperability being much less than 12 hours. an l+d avoidance of an intentional entry into LC0 3.0.3 will not significantly affect safety.
RELOCATED SPECIFICATI0NS' None TECHNICAL SPECIFICATION BASES The CTS Bases for this Specification have been replaced by Bases that reflect the format and applicable content of ITS 3.5.1 consistent with the BWR STS. NUREG-1433. Rev. 1.
.s FERMI - UNIT 2. 12 REVISION 7 06/18/99l !
ECCS-Operating 3.5.1 ACTIONS (continued) CONDITION. REQUIRED ACTION COMPLETION TIME HPCI System Restore HPCI System. 72 hours inoperable. to OPERABLE status. poc /, .2 ) f. P = (.ondifim R h e 1e. ;-;;;ere CCC, Restore low pressure 72 hours pr fond; Hon, -injedier./;prq ECCS injection / spray c L .2 g, g su g a. Ie- subsyste to OPERABLE ddic a t...,....,... status. C, eniere . h One ADS valve inoperable. 1 Restore ADS valve to 14 days (3,f,/ 3agg,a d, OPERABLE status. One ADS valve Restore ADS valve to inoperable. 1 72 hours (2)ocL,") OPERABLE status. { m a & E: ::e pressure ECC^ Restore low pressure Q(ond,mg ' injection / spray 2 ECCS injection / spray 72 hours (poc L,2 (ubsystem-inoperabi 6 eng subsyste to OPERABLE status. [3 7.1,'2. Adrn o.l. b) Two or more ADS valves 1 Be in MODE 3. 12 hours inoperable. g g3,3,g,ocg,,,l,g) e c.s. i,ar- a .2) 2 Reduce reactor steam 36 hours Required Action and dome pressure to ' associated Completion [ (3, S , /,q c-li.n c- If Ti Conditio 5g50gpsig. . y Enr-F not-met [ o r // (continued) flot rnc f .
-- M/4 STS - - 3.5-2 - Rev-1 ;-0+/0NSE.-
RW 7
ECCS-Operating 3.5.1 ACTIONS (continued) < C 75 h CONDITION REQUIRED ACTION COMPLETION TIME Two or more low Enter LC0 3.0.3. Isenediately
, pressure ECCS injection / spray subsystemsinoperable.( [o f., f ea raft 3 gg other f/ G /L HPCI System and one or *E ' ##4 ## '
'># ##U #'
more ADS valves inoperable. 4 b3> P, l ( 6. Q 77 < c.>
/ < 87 f,x are C.s.3.i m c >
c.am.,c a s o ( oas c{ i$ e'a #1 G ert if l~C
~ '
W ! 2 ) 9""./' !TS - 3.5-3 - R., 1, 04/07/05
ECCS-Operating 3.5.1 INSERT 3.5.1 02 SR 3.5.1.1 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. LH.s.5.lb SR 3.5.1.2 - - ---- --- - NOTE---- ---- - --- When LPCI is placed in an inoperable status solely for performance of this SR. or when [ Doc L.5) the LPCI swing bus automatic throwaver scheme is inoperable due to EDG 12 being paralleled to the bus for required testing. entry into Conditions and Required Actions
?'ty be delayed up to 12 hours for y
completion of the required testing, lb Perform a functional test of the LPCI swing 31 days bus automatic throwover scheme. 497,3./.O l l l 1 f FERMI UNIT 2 Page 3.5 4 (Insert) REVISION 7 06/18/99l
p .i . - . . , ECCS-Operating 3.5.I SURVEILLANCE REQUIREB.VTS (continued) SURVEILLANCE FREQUENCY SR 3.5.I.E - - - - - - - NOT ------ (I. [ /* /* / <L ot quire o be rf d if rfo d
,l w 'hin he pr ous da .
[4, e/ /, / . / foe &o{e
- Verify each recirculation pump discharge ITnt %S n .ee valve [=d typ::: :.h ] cycles through one ta up r r complete cycle of full travel tpr is t e ee n de-energized in the closed positiony'.*- 25 R
'8 =W -
SR 3.5. I 3. Verify the following ECCS pumps develop the In accordance specified flow rate (against a system head with the corresponding to the specified reactor Inservice pressuret.- Testing b(SYSTEMHEAD Program-se=- NO. CORRESPONDING Of A _- g 0F TO A REACTOR -
-P SYSTEM FLOW RATE ft2iPJ PRESSURE OF:#
Core 6350 Spray 2-, gpm 2[ too sig g, g,f, g, j ) LPCI 2 [I7,00P gpm , 2S sig / Qo,ooo (g, p, /. f . p p SR '.5.I. 3 -----------------NOTE------------------ ( f, ,/. b. 3 h Not required to be performed until 12 hours after reactor steam pressure and flow are adequa.te to perform the test. hl Ve ty , ,,with Treactor pressurefs v u20)- U sys -_ and 2 {e20t psig, the HPCI pump can develop [In accordanc4 + a flow rate 2- 42 gpm fagainst a system w;& ik l.nservice. headcorrespon{dingtoreactorpressureJ. 4,- Prop (continued) (4, fr, l. 6. 3)
-DWRpW, 3.5-5 %'kv-4,- Ci/07/Z '
I ECCS-Optrating B 3.5.1 BASES BACKGROUND hjecftcl.)ing arer;rf recirculation loop, begins. The water then ! (continued) enters the reactor through the jet pumps. Full flow test ' lines are provided for the four LPCI pumps to route water p'g from the suppression pool, to allow testing of the LPCI i pumps without injecting water into the RPV. These test p lines also provide suppression pool cooling capability, as- i i described in LCO 3.6.2.3, 'RHR Suppression Pool Cooling." g ; The HPCI System (Ref. 3) consists of a steam driven turbine pump unit, piping, and valves to provide steam to the 5 turbine, as well as piping and valves to transfer water from the suction source to the core via the feedwater system line, where the coolant is distributed within the RPV through the feedwater sparger. Suction piping for the system is provided from the CST and the suppression pool. i Pump suction for HPCI is normally aligned to the CST source l to minimize injection of suppression pool water into the RPV. However, if the CST water supply is low, or if the suppression pool level is high, an automatic transfer to the suppression pool water source ensures a water supply for continuous operation of the HPCI System. The steam supply to the HPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve. The HPCI System is designed to provide core cooling for a g O f'I f, wide range of reactor pressures (15? Mid te !!?! arid - UVff8/3
# m ee' te 7 P t Ma). Upon receipt of an initiation signal, the HPCI turbine stop valve and turbine control N
~
valve open simultaneously and the turbine accelerates to a specified speed. As the HPCI flow increases, the turbine governor valve is automatically adjusted to maintain design fl ow. Exhaust steam from the HPCI turbine is discharged to the suppression pool. A full flow test line is provided to route water fr= =d to the CST to allow testing of the HPCI bb System during normal operation without injecting water into the RPV. The ECCS pumps are provided with minimum flow bypass lines, which discharge to the suppression pool. The valves in these lines automatically open to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, all ECCS pump discharge' lines are filled with water. The LPCI and CS System discharge lines are kept full of water using a " keep fill" system,(-jockey M _ ystan). The HPCI System is normally alioned to the Ilus r.re Qray Mcs a re k e C /u r g rv:/ f4e RHR /.kes are keM c/pt a rg ed ,fAf edcude,uate e r ith c{er,,,; a f e e-c ra t, teal Mfer ] k2_ a p rm e.re e c m In ton 9 Volve- f- -b yy(continued) _.___ j WD/' STS
- B 3.5-3 Rc.- 1, 04/07/35-ffe7
I ECCS-Operating B 3.5.1 l BASES t, p- .
/ . Th El C S
- M' \ ' 5' a re rr k a I ACTIONS
/g j L1 (continued) fhc {fc.'Icom],f'yoi~ >
(2rfl3 T
- d-awnebW *+ eva'"O=d the effech:f one ADS valve Detag out of service" Per this analysis, operation of only l
-fove +4* ADS valves will provide the required depressurization.
However, overall reliability of the ADS is reduced, because
/% a single failure in the OPERABLE ADS valves could result in i
/Q a reduction in depressurization capability. Therefore, operation is only allowed for a limited time. The 14 day l
Completion Time is based on a reliability study cited in Reference 12 and has been f nd to be accentable throuah _ operating experience.
,oc one g.per, p p ;n j ag j.g to S a bS piru s I N
/.1and/.2 --
If any one low pressure ECCS injection / spray subsystem is inoperable in addition to one inoperable ADS valve, adequate core cooling is ensured by the OPERABILITY of HPCI and the remainin However,g low pressure overall ECCS is ECCS reliability injection reduced/ spray becausesubsystem. a single active component failure concurrent with a design basis LOCA could result in the minimum required ECCS equipment not be available. Since both a high pressure system (ADS) and ow pressure subsystem 4are inoperable, a I'$ more restrictive pletion Time of 72 hours is required to restore either the low pressure ECCS subsystemgor the ADS 4(5) valve to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience. 1 l % $.1 and d.2 ' E, h 6
/
If any Required Action nd associated Completion Time of Condition ($, n L er is not met, or if two or more ADS b valves are inoperable %e plant must be brought to a condition in which the LCO does not apply. To achieve this ' status, the plant must be brought to at least MODE 3 within 12 hours nd reactor steam dome pressure reduced to s 150 psig within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. l (continued)
'"R/f STSm B 3.5-8 L ;, 0;/C7/h Re 1
[ L l ECCS Operating B 3.5.1 LNSERT B 3.5.13 l SR 3.5.1.1 The LPCI System injection valves, recirculation pump discharge valves, and LPCI cross tie valve are powered from the LPCI swing bus, which must remain energized to support OPERABILITY of both LPCI subsystems. Therefore, verification of proper voltage and correct breaker alignment to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate separation and independence of the electrical power sources are maintained and appropriate sources of electrical power are available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability ensures that the required voltage is readily available for critical system loads connected to this bus. The 7 day Frequency takes into account the redundant capability of the AC, DC, and AC swing bus electrical power sources - and other indications available in the control room that alert the operator to subsystem malfunctions. SR 3.5.12 The LPCI System injection valves, recirculation pump discharge valves, and LPCI cross tie valve are powered from the LPCI swing bus, which must remain energized during any single failure, including loss of power from the normal feed to the swing bus. Therefore the automatic throwaver scheme is functionally tested (by manually opening position 3C of bus 72C) to verify the capability of the throwover scheme to detect loss of normal power, and initiate an automatic transfer to the swing bus emergency power source. Verification every 31 days that the LPCI swing bus automatic throwover scheme functions properly demonstrates that AC electrical power is available to ensure proper operation of the associated LPCI injection valves, recirculation pump discharge valves, and LPCI cross-tie valve. The swing bus automatic throwover scheme must be OPERABLE for both LPCI subsystems to be OPERABLE. The 31 day Frequency has been found acceptable based on engineering judgment and operating experience. This SR is modified by a Note to indicate that when this test results in LPCI inoperability solely for performance of this required Surveillance, or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG 12 being paralleled to the bus for required testing, entry into associated Conditions and Required Actions may be delayed for up to 12 hours l l until the required testing is completed. Upon completion of the %g ! Surveillance, or expiration of the 1 hour allowance, the swing bus must be
~ , returned to OPERABLE status or the applicable Condition entered and Required Actions taken.
FERMI - UNIT 2 Page B 3.5 9 (Insert) REVISION 7. 06/18/99 l l
~
Avalve,Yhef[S ,1 ECCS-Operating in a ccessahlt i'uay k B 3.5.1 Veri' fled b gg5g5-
&inis t'ra% .fIve. Lo d ro h SURVEILLANCE SR 3.5.1 (continued)
REQUIREMENTS g, removing-ths breaker., f-tae RHR System cross tie valve is p,p oo en er a-- hu aa+ k-- = = -d <--- +ke s'-- ape ste , th LPCI subsystems must be considered inoperable. The 31 day Frequency has been found acceptable, considering that these valves are under strict administrative controls that will ensure coa +*a' a- the valves continue to remain 'e: P ith efther
=at4": ;::::r -- :::d.
SR -3%1 , Veriff to [has vo ge r[31 days,that each I inverter p[570)fV and 5 [63 Ywhilejup/tput plying it r pe ve bus delmonstrates that the AC electrical power is; f, l l v abledojtisure p' f roper operdion of the associated E),CI ard'inj(ction nd mini rec.i(culgionp discha flow valves'and the / OPERABkE for valve. Ea'ch invert r'eust be I associal d LPCI subsfystem to OPE .
'The,21 day F quency has been fou_nd accepta bas n ggineeri judgment /and operatirig experijffce.
7 SR 3. 5.1.1t ) i Cycling the recirculation pump discharge in.d L,r.ee] valves through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will close when required. Upon initiation of an automatic LPCI subsystem injection signal, these valves are required to be closed to ensure full LPCI subsystem flow injection in the reactor via the recirculation jet pumps. De-energizing the valve in the closed position will also ensure the proper flow path for the LPCI subsystem. Acceptable methods of de-ener valve include de-energizing breaker control power,gizing racking the out the breaker or removing the breaker. The specified Frequency is-once tr'_ t :- e- *={/8'ntoni S
+ e -+ S--
b:fx. THERMAt-POWE" i; , 25% "'". Howev:r, thi. ^e si modified i,, . Net, thet stet;; the-Sur":il':::: i: tr f,3 T**uir'.d4*-b*-pedon"'d i f th' ' "*"'a"-""" r*' Ay **r* t than 31. days-age- "*-afe-:, imp'::::tet t en .T tMs-Note-- l
~ requires-th4s-tast- te k perJormed-during reecter ittrtup--
-before-eweeedhg 2",% "Th Verification d"rf ; eset_. l l
l
'k I
(continued) I
'BWRTtST3 ' B 3.5-11 i
-Rev-17-04/07f95.-- i l
i Rev 7 \
L ECCS-Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1 (continued) REQUIREMENTS Ai
- tir r. ;., .. x d ; ' * "T" is an exception to the W normal Inservice Testing Program generic valve cycling Frequency of 92 days, but is considered acceptable due to the demonstrated reliability of these valves. If the valve is inoperable and in the open position, t " :: ht LPCI f, 'd.
subsyste must be declared inoperable. SR 3.5. SR 3.5. and SR 3.5.1 The performance requirements of the low pressure ECCS pumps are determined through application of the 10 CFR 50, Appendix K criteria (Ref. 8). This periodic Surveillance is
- performed (in accordance with the ASME Code, Section XI, -
requirements for the ECCS pumps) to verify that the ECCS i pumps will develop the flow rates required by the respective y analyses.- The low pressure ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of Reference 10. The pump flow ratestere verified p 6,. c against a system head equivalent to the RPV pressure = Spro y, 2 , j expected during a LOCA. The total system pump outlet pressure is adequate to overcome the elevation head pressure pa rkmr5 raille'n( between the pump suction and the vessel discharge, the aferaf,%) ) i __. piping LOCA. friction losses, and RPV pressure present during a ; testing These a values may be established during preoperational 5 l ygj-The flow tests for the HPCI System are performed at two different pressure ranges such that system capability toL6 3 f'I' b ' l provide rated flow is tested at both the higher and lower i operating ranges of the system. Additionally, adequate - i steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor W pressure when the HPCI_ System diverts steam flow. Reacto steam pressure must ce Z W psig and 2.4,140] psig to perform SR 3.5.1 form SR 3.5.1
/6 dequate steam f ow is represented by 4*t-lepst-h25-tur ,= Li v >> vabu e or-to t aT-s team 41 ow-t--10-l b/h e}r Therefore, sufficientve n I time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal ,
(continued) } , BWR/4 STS I B 3.5-12 Rev 1, 04/07/95 l l inain tubine. y erseca % on line or t41.a b y p ss. p skdves open a t les s+ i ia, Rufo press 4 ec. (S'7s ce> <, tro I ,
~
Rev7
ECCS-Operating B 3.5.1
< BASES
~
SURVEILLANCE SR 3.5.1.1' continued) REQUIREMENTS that no blockage exists in the V discharge lines. This is demonstrated by the response of the turbine control or bypass valve or by a change in the measured flow or by any other method suitable to verify steam flow. Adequate. reactor steam done pressure must be available to perform this test to avoid damaging the valve. Also, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when j the ADS valves divert steam flow upon opening. Sufficien )# S'o time is therefore allowed after the required pressure and Ofeb flow are achieved to perform this SR. dequate pressure at which this SR is to be performed is psig):-(the pressure recommended by the valve manufacturer). Adequate steam flow is represented by
[- t lep t 1.25 L.. M;.e L.w.n vaivas
.htbe,hfa55 er--teta! -+- -
- 1Lj;n . Reactor startup is u,,.u, g(ges , p.am d allowed prior to performing this SR because valve ,
lea 5 D ,I' OPERABILITY and the setpoints for overpressure protection A.
-- ^ are verified, per ASME requirements, prior to valve installation. Therefore, this SR is modified by a Note that ,
states the Surveillance is not required to be performed until 12 hours adequate after reactcr to perform the test.steam The 12pressure and flow hours allowed for_ are Q.p)g 1 manual actuation after the required pressureMeached is
- sufficient to achieve stable conditions and adequate time tn complete the Surveillance. providesSR 3.5.1 and the LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.1 overlap this Surveillance to provide complete testing of the assumed safety function.
P,2- Me T..yuancy of is , nth: :: : !T*00E"E0 T[ T "'S!? -aenre
= =. 2 :u: # - er ,:l= = lte-t:ly
*testar The Frequency is based on the need to perform the n,{ N r
Survei31aate under the conditions that apply just prior ta or duriag a startup from a plant outage. Operating experience has shown that these components usually pass the jy$67 SR when performed at the 18 month Frequency, which is based BMM7 g on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. r REFERENCES 1. FSAR,Sectionp.3.2.2.3A 2. l FSAR,Sectiong.3.2.2.4g i 1 (continued) ! BWR/4 STS B 3.5-15 Rev 1, 04/07/95 l { W i StN ] l
I
- JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.5.1 - ECCS Operating P.1 -(continued)
- c. ITS SR 3.5.1.4 Note is modified to include a provision from CTS 3.5.1. Action b.5 that provides 4 hours after entering the ECCS Applicability. This CTS provision is modified by DOC "M.1" to the CTS markup. repeated below for reference:
, CTS Action b.5 provides an allowance for Mode changes
(" provisions of Specification 3.0.4 are not applicable") when LPCI is not correctly aligned for the LPCI' mode of operation. This allowance provides 4 hours after reactor vessel pressure exceeds the RHR cut-in permissive prior to having to establish the correct LPCI alignment. The allowed Mode changes could include Mode 2 as well as Mode 3 (even Mode 1 if sufficient time were available to proceed from Mode 2 to Mode 1). The Note to ITS SR 3.5.1.4 provides this same 4 hour allowance, but limits its application to Mode 3 only. Therefore the ITS is more restrictive in requiring the proper LPCI alignment prior to entr. ng Mode 2. This is a more restrictive change with no impact on safety. d. ITS includes new SRs (SR 3.5.1.1 and SR 3.5.1.2) that result from CTS surveillances 4.8.3.1.1 and 4.8.3.1.2. These reflect the Fermi-specific design equivalent to the standard design reflected in NlREG 1433 SR 3.5.1.5 (for LPCI inverter). Additionally. CTS 4.8.3.1.2 is modified by DOC "L.5" to the CTS markup (repeated below for rettrence): CTS 4.8.3.1.2 and ITS SR 3.5.1.2. requires demonstration of the LPCI swing bus automatic transfer scheme. Performance of this test requires that the swing bus (and therefore both LPCI subsystems) be made inoperable. As a result, this test would result in ITS requiring an intentional entry into LCO 3.0.3 (LC0 3.5.1. Condition J). To preclude this intentional LCO 3_.0.3 entry, the ITS adds a Note to SR 3.5.1.2 allowing a 12 , hour' delay in entering the actions for the inoperability caused by performing this required Surveillance. Since this test: 1) is not expected to de-energize the swing bus: 2) is performed 3
,4 )
under control of a dedicated individual in communication with the control room operator; and 3) results in the period of q
.inoperability being much less than 12 hours. A 12 hour avoidance of an intentional entry into LCO 3.0.3 will not lQ l significantly affect safety.
FERMI UNIT 2 2 REVISION 7 06/18/99l ! 1
JUSTIFICATION FOR DIFFERENCL3 FROM NUREG 1433 i ITS: SECTION 3.5.1' ECCS - Operating i
- e. ITS SR 3.5.1.6 is modified to reflect the CTS 4.5.1.a.2 requirement for the LPCI cross connect valve to be open. This CTS Surveillance is implicitly addressing the power operated cross connect valve (note the singular form " valve"). There is however, a second valve: a locked open manual maintenance valve, that is not explicitly addressed with a periodic CTS (or . ,
ITS) surveillance. _ Therefore, as an editorial clarification ! (refer also to DOC "A.13") " power operated" is added to ITS SR 3.5.1.^6 to a.fferentiate the valve required to be surveilled each 31 days. As further clarification, the manual maintenance valve is also addressed in the Bases for this SR. P.2 Bases changes are made to reflect plant specific design details. , equipment terminology, and analyses. Some of these changes are specifically discussed below:
- a. Backaround. Anolicable Safety Analysis. LCO. and Surveillances:
Specific ECCS response to large break DBAs is revised to reflect i Fermi 2 design of " loop selection logic." The change to ITS SR l 3.5.1.7 reflects the loop selection logic design (which includes both LPCI subsystems being cross tied such that the inability to isolate one recirculation loop may result in both LPCI-subsystems injecting into the broken loop and therefore neither performing their intended function). I
- b. Surveillances: Since ADS is designed with only one solenoid, the
" Staggered Test Basis" is not applicable.
P.3 Bases changes are made to reflect changes made to the Specification. Refer to the Specification change (and associated JFD) for additional detail. P.4 Not used. l u i FERMI UNIT 2 3 REVISION 7, 06/18/99l l
NO SIGNIFICANT HAZARDS EVALUATION I ITS: SECTION 3.5.1 ECCS - Operating 4 TECHNICAL CHANGES LESS RESTRICTIVE
. (Soecification 3.5.1 "L.5" Labeled Comments / Discussions) 4
- 2. Does the change create the possibility of a new or different kind of l accident from any accident previously evaluated?
This proposed change will not involve any physical changes to plant i systems, structures, or components (SSC). nor changes in normal plant i operation. The test will continue to be conducted as previously i required, with the expected result being confirmed Operability of the : system. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
- The proposed change does not involve a significant reduction in a margin of safety because this test: 1) is not expected to de energize the swing bus: 2) is performed under control of a dedicated individual in communication with the control room operator: and 3) results in the period of delayed Actions being less than 12 hours (i.e., a reasonably T I minimal period of time). Additionally, the expected result is a satisfactory demonstration of Operability, with no impact on safety.
f W 9 FERMI . UNIT 2 10 REVISION 7. 06/18/99l
ECCS -Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2' ECCS-Shutdown i LCO 3.5.2 Two low pressure ECCS injection / spray subsysteris shall be . OPERABLE. i APPLICABILITY: MODE 4 MODE 5. except with the spent fuel storage pool gates removed and water level = 20 ft 6 inches over the top of the reactor pressure vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A, One required ECCS A.1 Restore required ECCS injection / spray 4 hours injection / spray subsystem inoperable. subsystem to OPERABLE status. B. Required Action and B.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not met, draining the reactor vessel (OPDRVs). C. Two required ECCS C.1 Initiate action to Immediately injection / spray suspend OPDRVs. subsystems inoperable. MQ C.2 Restore one ECCS 4 hours injection / spray subsystem to OPERABLE status. _ (continued) l FERMI - UNIT 2 3.5 8 Revision 7. 06/18/99
ECCS-Shutdown 3.5.2 ACTIONS (continued) C0leITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status. M D.2 Initiate action to Immediately restore one standby gas treatment i subsystem to OPERABLE status. M D.3 Initiate action to Immediately ; restore isolation capability in each ! required secondary ; containment
', penetration flow path not isolated.
i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each re 12 hours coolant injection (quired low pressure LPCI) subsystem, the ! suppression pool water level is
= 66 inches. ,
(continued) l' FERMI UNIT 2 3.5 9 Revision 7. 06/18/99 k
*f:. .
ECCS -Shutdown 3.5.2 , I I SURVEILLANCE REQUIREMENTS (continued) {
. SURVEILLANCE FREQUENCY
)
J i SR 3.5.2.2 Verify. for each required core spray (CS) 12 hours subsystem, the: l
- a. Suppression pool water level is
= 66 inches: or
- b. . -.-..........- N0TE--. - ---.... .-
Only one required CS subsystem may take credit for this option during OPDRVs. Condensate storage tank water level is l = 19 ft. SR 3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus, ! i l SR 3.5.2.4 Verify. for each required ECCS injection / 31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve. (continued) j FERMI - UNIT 2 3.5 10 Revision 7 06/18/99
m
)
1 . 1 i l ECCS - Shutdown j 3.5.2 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY l SR 3.5.2.5 -- -- -
. NOTE -- - --
LPCI subsystem (s) may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. Verify each required ECCS injection / spray 31 days subsystem manual, power operated, and
. automatic valve in the flow path, that is not locked, sealed, or otherwise secured in j position, is in the correct position.
1 SR 3.5.2.6 Verify each required ECCS pump develoas the In accordance Ogl specified flow rate against a system wad with the j l l corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program N0. CORRESPONDING 0F TO A REACTOR SYSTEM FLOW RATE PQMPS PRESSURE OF l CS = 6350 gpm 2 = 100 psig i LPCI = 10,000 gpm 1 = 20 psig l SR 3.5.2.7 : ---- - NOTE - -- - - Vessel injection / spray may be excluded. I Verify each required ECCS injection / spray 18 months I subsystem actuate s on an actual or simulated automecic initiation signal. l 1 . l
- j. FERMI UNIT 2 3.5 11 Revision 7 06/18/99 l
l-
ECCS-Shutdown B 3.5.2 BASES ACTIONS (continued) to OPERABLE status. In this case, the Surveillance may need l to be performed to restore the component to OPERABLE status. l Actions must continue until all required components are OPERABLE.
. The 4 hour Completion Time to restore at least one low pressure ECCS injection / spray subsystem.to OPERABLE status ensures that prompt action will be taken to provide the required cooling capacity or to initiate actions to place the plant in a condition that minimizes any potential fission product release to the environment. l SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 REQUIREMENTS The minimum water level indication of 66 inches (9 ft 0 inches actual level) required for the suppression pool is periodically verified to ensure that the su)pression pool will provide adecuate net positive suction lead (NPSH) for the CS System anc LPCI subsystem pumps, recirculation volume, and vortex prevention. With the suppression pool water level less than the required limit, all ECCS injection / spray subsystems are inoperable unless they are aligned to an OPERABLE CST.
When suppression pool level is < 66 inches, the CS System is considered OPERABLE only if it can take suction from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a verification that either the suppression pool water level is = -66 inches or that CS is aligned to take suction from the CST and the M CST contains = 300.000 gallons of water, equivalent to 19 ft T/ plus margin to preclude vortex formation, ensures that the CS System can supply at least 150.000 gallons of makeup water to the RPV. The CS suction is uncovered at the 150.000 gallon level. However, as noted, only one required CS subsystem may take credit for the CST option during OPDRVs. During OPDRVs. the volume in the CST may not provide adequate makeup if the RPV were completely drained. Therefore, only one CS subsystem is allowed to use the CST. This ensures the other required ECCS subsystem has adequate makeup volume. The 12 hour Frequency of these SRs was developed considering operating experience related to suppression pool water level l FERMI UNIT 2 B 3.5.2 -4 Revision 7. 06/18/99
ECCS- Shutdown B 3.5.2 BASES
. SURVEILLANCE REQUIREMENTS (continued) and CST water level variations and instrument drift during i
^
the applicable MODES. Furthermore, the 12 hour Frequency is I considered adequate in view of other indications available in the control room, including alarms, to alert the operator i to an abnormal suppression pool or CST water level i condition. SR 3.5.2.3 The LPCI System injection valves, recirculation pump discharge valves, and LPCI cross-tie valve are powered from the LPCI swing bus, which must remain energized to support OPERABILITY of any required LPCI subsystem. Therefore, verification of proper voltage and correct breaker alignment to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate electrical power sources are available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability ensures that the required voltage is readily available for critical system loads connected to this bus. The 7 day Frequency takes into i account the redundant capability of the AC. DC. and AC swing 4 bus electrical power sources, and other indications avail 6ble in the control room that alert the operator to subsystem malfunctions. SR 3.5.2.4. SR 3.5.2.6. and SR 3.5.2.7 : I The Bases provided for SR 3.5.1.3. SR 3.5.1.8. and SR 3.5.1.11 are applicable to SR 3.5.2.4. SR 3.5.2.6. and SR 3.5.2.7. respectively. l_ FERMI - UNIT 2 B 3.5.2-5 Revision 7 06/18/99
1 l
- l l
i i ECCS - Shutdown B 3.5.2 , 1
' BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.2.5 Verifying the correct alignment for manual, power operated. and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS I operation. This SR does not apply to valves that are ) locked, sealed, or otherwise secured in position, since i
- these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation: rather, it involves verification that those valves capable of potentially being mispositioned are-in the correct position.
This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is appropriate because the valves are o)erated under procedural control and the probability of t1eir being mispositioned during this time period is low. In N0 DES 4 and 5, the RHR System may operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal. Therefore, this SR is modified by a Note that allows one or both LPCI subsystems of the RHR System to be considered OPERABLE for the ECCS function if all the required valves in the LPCI flow path can be manually realigned (remote or local) .to allow injection into the RPV, and the system is not otherwise inoperable. This will ensure adequate core cooling if an inadvertent RPV draindown should occur. REFERENCES 1. UFSAR, Section 6.3.2. l FERMI - UNIT 2 B 3.5.2-6 Revision 7, 06/18/99
W /c /2. 8, 5,1 (#so see spwmdun e.s.O g[RGENCY COE.E COOLING SYSTD!$ llM111NG t'ONDITION FOR OPf pATION (Continued) ACTION': (Continued)
- d. For the ADS:
- 1. With one of the above required ADS valves inoperable, provided the HPCI system, the CSS and the LPCI system are OPERABLE, restore the inoperable ADS valve to OPERABLE status within 14 days or be in at least HOT SIAITDOWN within the next 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours.
- 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours. 1
- e. With a CSS header AP instrumentation channel inoperable, restore the
<g
- inoperable channel to OPERABLE status within 72 hours or determine the CSS header AP locally at least once per 12 hours; otherwise, declare ggfr. 80 the associated CSS subsystem inoperable.
3,6,I f. With an LPCI or CSS system discharge line " keep filled' alarm instrumentation inoperable, perform Surveillance Requirement 4.5.1.a.1.a. 9 In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.10. SUPVElllANCE REQUTREMENTS r yC C-l 4.5.1 The emergency core cooling systeias shall be demonstrated OPERABLE by:
~
*h a. At least once per 31 days:
$fff$
- 1. For the CSS, the LPCI system, and the HPCI system h.
a) Verifying [by v/ntino at the dah noint untDthat the system SR35oq ** pipin from the pump otscharge valve to'the system isolation valve is ft led with water, f b) Verifying that each valve, manual, power operated or automatic, in 0R 3.5 7-( the flow path that is not locked, sealed, or otherwise secured in , position, is in its correct
- position. l M,4
- 2. For the LPCI system, verifying that the cross-tie valve is open.
SP( [
*Except fhat an automati valve capable of automat c return to its ECCS po/ tion for another mode of op(ration.
when af ECCS signal is present may be in positt FERMI - UNIT 2 3/4 5 3 PAGE l OF 08 Rev 7
;. ,_...... P. .
. . . . .. ..A . .
......v. . C.' ,a .1 Spec 4ca.bo n. 35.2 (Als see spee;.sca-(sn. e. s.O Al EMERGENCY CORE COOLING . SYSTEMS SURVEILLANCE REQUIREMENTS (continued)
- 3. For the FCI system, verifying that the HPCI pump flow controller is gc(,,[i&p
~, ' in the correct position.
- b. Verifying that, when pursuant to Specification 4.0.5:
SR =;*E 2* /g 11. The two CSS pumps uala flow[ of~
,Q 7ressur.e.pf a in,each irefhubs stem together develop
~~
J3:335j0 1 jus 4Tspst ' te no 270 Aigy.colVesinin' din'g to a reac6r~ vessel pressure of a 100 psig.
- 2. Each LPCI pump in each subsystem develops a[ low of at least 10,000 gpm(Ana'tht Go 'line.pftstarftf a nuAsi esponding to a ressure of a 20
~
reactor vessel o pri ri con 6ai. .d d iii.. ...o a psig. - /l, / O
$CO 3. The HPCI pump develops a flow of at least 5000 gpm in the test flow
*t path with a system head corresponding to reactor vessel operating gflQ;Mion, 3'
l pressure including injection line losses when steam is being supplied ( Q o the turbine at 1025 +20. -80 psig.* i
- c. At least once per 18 months g-[g ( o f- M./f
- 1. FortheCSS,theLPCIsystem,ddtheHPCIsystem)performinga G R, 5.E.2 7 system functional test which includes, simulated automatic actuation gg of the system throughout its emergency operating sequence and ,
verifying that each automatic valve in the flow path actuates t.9 its correct position. Actual injection of coolant into the reactor vessel may be excluded from this test.
- 2. or the HPCI system verifying that:
a) The systes develops a flow of at least 5000 gpa in the test flow path with a system head corresponding to reactor vessel operating pressure including injection line losses when steam is being supplied to the turbine s at 165 + 50. ,0 psig.*
$" 60' ,
I b) The suction for the HPCI system is automatically transferred from gyCO {', gat /ou the condensate storage tank to the suppression chamber on a bq ,) condensate storage tank water level - low signal and on a suppression chamDer - water levei high signal.
- 3. Performing a CHANNEL CAllBRATION of the CSS and the LPCI system discharge line ' keep filled" alarm instrumentation.
4 Performing a CHANNEL CAllBRATION of the CSS header AP instrumentation and verifying the setpoint to be s the allowable value of 1.0 psid. L qcd
*The provisions of Specification 4.0.4 are not appitcable provided the th.e surveillance is performed within 12 hours after reactor steam pressure is sfeCII 3,6,I adequate to perforu the test.
FERMI - UNIT 2 3/4 5 4 Amendment No. 87 PAGE c2 0F 08 kel 7
- ji ' f. h . g.S r- .
\
$fECtF1cAnerl 55.2-rMrRCfNEY r0Rr root TNG SVUFNS 3/4 5 7 F rrS - SHUTD alN '
IIMITING CONDITION FOR OPERATION
/
3.5.2 At least two f the f lowing (subsystemsshallbeOPERABLE: [ a. re spray syst (CSS) subsyst with a subsystem rised of:
- 1. At leas two OPERABLE C5 p g s and
- 2. An E ficw path apable of taking s tion from at 1 st one f the following ater sources and t nsferring the t ths spray = caer to the reacto vessel f q
-4 %Lew,;;;;; it, e l' i 1 When the suppression chamber water level is less than h SR 3.6,7.7- limit required in Specification 3.5.3 or is drained. rom the condensate storage tank with an indicated level of at least 19 ft.
. Low essure coolant inj ion u.P w system uusmcm. . m .
su ystem conprised of: LA.l At least two OP LE LPCI (RHR) , and l
. An OPERABLE path capable of aking suction from t suppression amberandtransferingthewatertothefeactor
, cem1**
APPL TrARfl ITY: OPERATIONAL CONDITION 4 cnd $*. ACIIDti: 4 Cries A .<r- Witn one of the above required subsystem (s) inoperable, restore at least two subsystem (s) to OPERABLE status within 4 hours or suspend ' I AGD# D all operations with a potential for draining the reactor vessel. AcTto4 C / ,With both of the
;Xn=:""U:nd allabove required operations withsubsystem a potential(s)for inoperable. suspen 40RE, draining the rearte: vessel. Restore at least one subsyntem to OPERABLE 4tatus Mod p wi's.m 4 hours or tabli h(5ECONDARY CONTA' mirNT Ihi hlTDyithin.
v- - - : r .. in;4;a .
'~~.. usm ro -
g;V The ECCS is not required to RABLE provided that t R c: r'r- = ' pplW f -heart-trymurramrr the cavity is flooded, the spent fuel pool cates are T .2O
,. removed.andwaterlevelismaintainedwithinthelimitsof(SmiGiet;E e JZ.
.) "1 E1 et -J in in
**Ni's'ubsyith[s)maybeconsideredOPERABLEduringalignmentandoperation
$235.2.E for decay heat removal if capable of being manually realigned and not NN otherwise inoperable. FERMI - UNIT 2 3/4 5 6 Amendment No. 226.131 PAGE 3' 0F 08 /fev '7
I I l SPecSic+ nod 3.5 2-(Aiso n %,n 3.c. 2.2) \ 6 ' LINf71NS CONDfTION FOR OPERATION 3.5.3 The suppression chamber shall be OPEMBLE: f *-c a. In OPEMTIONAL CON 0!TIONS 1, 2, and 3 with a contained water volume of LLo 3,6.2 2 <(at least 121.080 fts, equivalent to a level of 24'4' (.! inches i findication). 44.3
$ 4 3 5'.2 .I b. In W aa"t m i m a m m a w se e a 4 dnad 4 une ofit led car saaj ;e. -- ^'elent to agevel af t'0"_A.55 < nches ' natcat1on),
g4 3 5,2 2.cl 'except taat the suppression enameer sevel may be less than the limit or may be drained provided that: cJ SCT!pA) 6 .h Nooperationsareperformedthathaveapotentialfordrainingf s 8. 35 2.2.b Nole. the reactor vessel, T or switch is kedinthe5[tdownorfj pt3 5.2.~1.b 4 The condensate storage tank water level is at least 19 ft., and
-4. The core spray system is OPEMBLE per Specification 3.5.Z with g g'g,1 an OPEMBLE flow path capable of taking suction from the 4 g g, 3,g,2,? . h conjensate storace tank ano sr.nsp.. mv uir -- J -- --- snur l
-rar soarnerAo the reattor vesstl.1 L n.
APPLICARILITY: OPERATIONAL CON 0!T10N$(I, 2, 3h4, and 5*} l
- g. Sa.c Lt.h 3.G.7..'L L g3,gy g* In OPEMTIONAL CONDIT!0N 1. 2. or 3 with the suppression chamber water
- a. (level less than the above limit, restore the water level to within the
/Lo 34 2.'2- limit within I hour or be in at least HOT SHLTTDOWN within the next 1 N i 1@/ rs and in CDLD SHL1TDOWN w thin t ollowing 24 hqurs.
9 bas i .lC5s encsy)
,3 1
{
- b. In OPERATIONAL CONDITION or5'withthesuppression)chamberwater Acy;ndC,O level less than the above limit orJrained and the ahnve reevired l'l conditions not satisfied, suspendkDKt ALnRATIDNS andlall operations that have a potential for draining the reactor vesse' M M ' 14 A.I Ir I(I i( .Y. FhT{I' ~* j GniBay ufn W
*The sunoressten e"=h-r is not required to be OPERABLE provided that the h
g'3 MgcaYg dyactor vessel head is removeTJthe cavity is flooded, or being flooded j rom the . ,,sssion pool, the spent fuel pool gates are .. - .. wnen tne cavity is flooded, and the water level is maintained within the limits of g (Specif'Ications 3.3.5 and 3.3.v. 3 , FERMI . UNIT 2 3/4 5 8 Amendment No.131 PAGE 5' 0F 08 Rev 7
Sgec/ka t/o 7; 7. S. '_ (h5O MC SPecMed to rt y.3.y) ELECTReCAL A,yj D STEMS Ccc . SURVEf ttANCE REOUIREMENTS / crec$cdr.oh 3 8. B '/ g o.5.2.3 4 .8.3.2. t least the bove reauired a~-- Mistribution system division)and the swing bus snais ou cetermined energized at least once per 7 days by ~~ verifying correct breaker alignment and voltage on the busses / cabinets, f4.8.3. 2 The A.C. power distribution system swi g bus automatit throw i sch shall be demonstr ted OPERABLE at least ce per 31 days by man 11y
- ope ng position 3C bu 72C and verifying that he automatic transfe scheme df3 }
I j i i i FERMI UNIT 2 3/4 8-15a Amenament No. 29 .) PAGE F 0F 08
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 - ECCS-Shutdown A.5 CTS 4.5.3.2.b requires verification every 12 hours that footnote
"*" to the' Applicability of CTS 3.5.3. Suppression Chamber, is satisfied. ' Footnote "*" is a list of the conditions required before the suppression pool may be made inoperable. When plant conditions are in accordance with CTS 3.5.3. footnote "*". the LC0 i is not required to be met, and therefore CTS 4.5.3.2.b is not required to be performed. As such this surveillance is never required to be performed. Therefore, deletion of CTS 4.5.3.2.b is an administrative change. I A6 CTS 4.5.3.2.a requires verification every 12 hours that the conditions of CTS 3.5.3.b are satisfied whenever the suppression chamber is drained or less than the required level. If the suppression pool is at less than the required level. Core Spray must be lined up to the Condensate Storage Tank. Additionally, in l accordance with CTS 3.5.3.b. operations with a potential to drain the reactor vessel (0PDRVs) are prohibited under these conditions and the CST level must be maintained within required limits. ITS SR 3.5.2.2 verifies the same requirements at the same Frequency as '
CTS 4.5.3.2.a. Therefore, this is an administrative change with no impact on safety. A.7 In Modes 4 and 5, with the suppression pool drained or less than the required limit CTS LCO 3.5.2 allows the two Operable ECCS l systems to be satisfied by two CS subsystems with suction aligned to the CST. In the event one of the two CS subsystems becomes ! inoperable. Action a requires suspending operations with a potential for draining the vessel (0PDRV) after 4 hours, but i allows unrestricted continued operation with only one Operable CS subsyste'm once OPDRV are suspended. Similarly CTS 3.5.3.b ! permits both CS subsystems to be Operable when lined up to the CST. but only if no OPDRV are in progress (CTS 3.5.3 b.1). ITS I implements the same requirements: LC0 3.5.2. Actions A and B. provide the same 4 hours as CTS 3.5.2 to suspend OPDRV when one of b l the required CS subsystems becomes inoperable: and the Note to SR 3.5.2.2.b precludes OPDRV while the two required ECCS subsystems d consist of two CS subsystems aligned to the CST. This is an ' administrative change with no impact on safety because the ITS requirement is consistent with the requirements of CTS 3.5.2. The j k additional 4 hours compared to CTS 3.5.3 is addressed by DOC L.3. FERMI.- UNIT 2 2 REVISION 7 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown A8 CTS LC0 3.8.3.2.a.3 requires the LPCI swing bus to be Operable, and I the associated Action c requires declaration of LPCI inoperability with the swing bus-inoperable (i.e.. not energized or automatic ^ throwover scheme inoperable). The ITS provides this intent within the ECCS Specification, without separately specifying Operability of the swing bus in another Specification. The ITS recognizes that LPCI is inoperable with the swing bus inoperable (ITS Bases specifically discusses). Therefore both the ITS ar.d CTS Actions for an inoperable swing bus are the same. This administrative presentation preference does not result in any technical changes. Therefore, this is an administrative change with no impact on safety. C A.9 Not used. e
)
A.10 CTS 4.5.1.b.2 specifies that the LPCI pump flow verification test " be performed at a pressure corresponding to a reactor vessel to primary containment differential pressure (psid) greater than or equal to the value assumed in the safety analysis. ITS SR 3.5.1.8 and SR 3.5.2.6 specify that the LPCI pump flow test be performed l at a system head corresponding to a reactor pressure greater than or equal to the value assumed in the safety analysis. This change was made to make the test description for the LPCI test the same as that currently used for the CS test. Both tests are intended to verify the flow rates at the reactor pressures assumed in the safety analysis, NEDC 32071P. . Table 4 3. NEDC 32071P, Table 4-3 footnote (1), indicates that the pressures assumed for LPCI or CS pump injection and the values at which the pumps are tested is expressed in' " vessel to drywell differential pressure." The acceptan~ce criteria used for ITS SR 3.5.1.8 (and ITS SR 3.5.2.6) l A> l 1s expressed as minimum flow rate against a system head j corresponding to reactor pressure. This criteria is clarified in the Bases which states that pump flow rates are verified against a system head equivalent to the elevation head pressure between the pump. suction and the vessel discharge, the piping friction losses, and RPV pressure present during a LOCA. The SR acceptance criteria is presented in "psig" (instead of psid) and clarified in the Bases to ensure that the flow verification test .is not I l I I FERMI UNIT 2 3 REVISION 7 06/18/99l 1
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown performed based on pump differential pressure alone. This is an administrative change because there is no change to the existing requirement to test the CS and LPCI pumps at the pressures and flows assumed in the safety analysis. A.11 CTS 4.5.1.c.1 requires the performance of a system functional test that includes " simulated automatic actuation." ITS SR 3.5.2.7 permits the system functional to be initiated by an " actual or lh simulated" automatic initiation signal. This change allows satisfactory automatic system initiations to be used to fulfill the system functional Surveillance Requirement. Operability is adequately demonstrated because the ECCS subsystem can not discriminate between " actual" or " simulated" initiation signals. This is an administrative change with no impact on safety because it is a reasonable interpretation of the existing requirement. A.12 CTS 3.5.2 and 3.5.3, Applicability footnote "*", provides an allowance for ECCS to be not required when the refueling cavity water level is "within the limits of Specification 3.9.8 and 3.9.9." l The ITS simply states this provision as a single required water level. Since the allowance only applies when the spent fuel pool gates are removed, the water level can be referenced from a single point, and be known to satisfy both CTS 3.9.8 and 3.9.9. This bounding level is presented in the ITS. This is a presentation , preference only, with no technical change. Therefore, this change is administrative. A.13 CTS 4.8.3.2.2 requires demonstration of the LPCI swing bus automatic throwover scheme; however the associated LC0 only requires ~ that the LPCI swing bus be energized from the one required energized division. In this condition (only one division energized), the automatic throwover performs no safety function since there is not a second division to throwover to. Furthermore, the associated actions only provide for actions to be taken if the swing bus is de energized: no action is provided for an inoperable throwover scheme, and the provisions of LCO 3.0.3 are also not applicable. Therefore, the CTS presentation for LPCI swing bus automatic throwover scheme while in the shutdown Modes, does not contain any functional requirements or limitations. As such. ITS provides an enhanced presentation by not including the superfluous Surveillance wording. Therefore, this change is solely an administrative presentation preference. FERMI UNIT 2 4 REVISION 7 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 - ECCS-Shutdown TECHNICAL CHANGES - MORE RESTRICTIVE j M.1 CTS 3.5.2 and 3.5.3. Action b. require that secondary containment integrity be established "within 8 hours" when both required ECCS
' subsystems are inoperable while shutdown. ITS 3.5.2. Action D.
requires operators to " Initiate action" immediately to establish the essential elements of secondary containment but does not specify a completion time. The CTS establishes completion times for Required Actions that, depending on plant conditions, may not be achievable in the required time. Conversely, plant conditions may be such that the actions could be accomplished in c shorter time than is required. Therefore. CTS Required Actions appear to I provide a period of time in which it is not necessary to establish the desired plant conditions even if those conditions can be readily established. Conversely, if plant status is such that the desired plant conditions cannot be established in the required time the CTS required actions result in non compliance with the Technical Specifications and an Licensee Event Report will be required. ITS rore appropriately establishes the required actions as " Initiate action" immediately to establish the desired plant conditions. This change eliminates an CTS allowance to delay establishing the condition for up to the specified action time and replaces it with a requirement to establish the desired condition as quickly as is reasonably achievable. However, by eliminating the CTS completion times, an LER is not required if best efforts to establish the condition take longer than the time specified in the CTS. This is a more restrictive change with no negative impact on safety. r I TECHNICAL CHANGES LESS RESTRICTIVE l
" Generic" LA.1 CTS LC0 3.5.2 and 3.5.3 include details relating to system design. '
function, and Operability for the core spray system and the LPCI System while shutdown. ITS 3.5.2 includes only a requirement for ! Operability and moves details of Operability and system design d ! requirements to the Bases. This is acceptable because these bE/ details do not impact the ITS requirement to maintain the systems l Operable. Therefore, these details can be adequately defined and I controlled in the Bases which require change control in accordance ~
, with ITS 5.5.10. Bases Control Program. These details are not required to be in the ITS to provide adequate protection of the FERMI UNIT 2 5 REVISION 7 06/18/99l l i
l l 4 DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown public health and safety acceptable because relocating these details does not impact the requirement to maintain the equipment Operable. )
)
LA.2' CTS 4.5.2.1 refers to the ECCS Operating surveillances that also apply to ECCS Shutdown, and also provides an exception for the position of the LPCI cross tie valves. This exception is a detail of the " correct position" of the system's valves and is relocated to the ITS LC0 3.5.2 Bases. ITS SR 3.5.2.5 includes only a l requirement for valves to be aligned to their correct position and moves details of the position needed to support Operability and system design requirements to the Bases. This is acceptable because the these details do not impact the ITS requirement to maintain the valves properly aligned and the system Operable. Therefore, these details can be adequately defined and controlled in the Bases which require change control in accordance with ITS l 5.5.10. Bases Control Program. These details are not required to be in the ITS to provide adequate protection of the public health and safety acceptable because relocating these details does not impact the requirement to maintain the equipment Operable. LA.3 CTS 3.5.3.b and CTS 4.5.3.1.b include details that relate required suppression pool volume to its respective indicated level. ITS (T T/ l i 3.5.2 includes only the required level and moves details of system design to the B9ses. The Bases require change control in accordance with ITS 5.5.10. Bases Control Program. These details ! are not required to be in the ITS to provide adequate protection l of the public health and safety acceptable because relocating ' these details does not impact the requirement to maintain the equipment Operable. LA.4 The following CTS details for performing Surveillances are not j included in the ITS. These detailed methods for performing l Surve111ances are moved to the Bases l:
- a. CTS 4.5.1.a.1.a details a requirement for verifying that '
the system is filled with water. "by venting at the high point vents":
- b. CTS 4.5.1.a.2 contains a footnote "*" which details a requirement for the correct position of ECCS valves:
- c. CTS 4.5.1.b.1 and 4.5.1.b.2 details test line pressure requirements for the CSS and LPCI pumps: and !
FERMI UNIT 2 6 REVISION 7 06/18/99l l
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown These details can be adequately defined and controlled in the Bases, which require change control in accordance with Chapter 5 of the ITS. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the details in the ITS are adequate for performing the required Surveillances. LR.1 CTS 3.5.3.b.2 and CTS 3.5.3. Action b. requires locking the mode switch in Shutdown or Refuel when ECCS is not available because of l insufficient water inventory in the Suppression Pool in Modes 4 or 5. Under the same conditions. ITS 3.5.2. Action B takes appropriate actions which do not include locking the mode switch in shutdown or refuel. This change is acceptable because the action to place the mode switch in the proper position remains a Technical Specification requirement, while the requirement to lock i the mode switch in shutdown or refuel to prevent reactor startup I when the suppression pool is drained is an administrative control intended to prevent violation of other Technical Specifications. Therefore, the requirement to lock the mode switch to prevent violating requirements is an administrative control that is not necessary to be controlled by license amendment or 10 CFR 50.59. ; This detail is not required to be in the ITS to provide adequate l protection of the public health and safety and is acceptable because the action to place the mode switch in the proper position l remains a Technical Specification requirement. ! TECHNICAL _ CHANGES LESS RESTRICTIVE
Speci fi c"
~
L.1 CTS 3.5.2. Action b and CTS 3.5.3. Action b. require the suspension of Core Alterations when no ECCS is available. ITS 3.5.2 does not retain this requirement because ITS refueling LCOs provide requirements to ensure safe operation during Core Alterations including required water level above the RPV flange ' and the position of the mode switch. The ECCS function enforced by ITS 3.5.2 is intended to provide protection for loss of vessel inventory events. However, a loss of vessel water inventory is ' not initiated by Core Alterations and the response to a loss of vessel water inventory is not hampered by Core Alteration operations. Therefore, this change has no impact on safety. , FERMI UNIT 2 7 REVISION 7 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.5.2 ECCS-Shutdown L.2 Not used. lh L.3 CTS 3.5.2 requires two low pressure emergency core cooling subsystems to be operable. If one of the required systems is inoperable. Action a. allows 4 hours to get back to two operable subsystems. Otherwise. it requires the licensee to suspend operations with a potential for draining the reactor vessel (0PDRVs). CTS 3.5.3 requires the suppression pool to be operable but allows the level to be below the limit (including completely drained) in Modes 4 and 5 provided certain conditions are met. One of these conditions is that no OPOWs are performed. The two TS are related because the suppression pool is.the suction source for the LPCI subsystems and one of the possible suction sources for the CSS subsystems. If the suppression pool level is below l the limit in CTS 3.5.3.b. the LPCI subsystems would be inoperable l and the CSS subsystems would be operable only if there was adequate water in the condensate storage tank (CST) and the CSS subsystems were aligned to take suction from the CST. With both CSS subsystems operable with suction from the CST CTS 3.5.2 would i not prohibit performing OPDRVs. However. CTS 3.5.3.b would prohibit OPDRVs because the suppression pool level is below the limit. In ITS 3.5.2. the aspects of CTS 3.5.2 and 3.5.3 related to the operability of ECCS are combined. . SR 3.5.2.2 requires the i licensee to verify that the suppression pool level is within g limits or that adequate volume is available in the CST. However, k a note to this SR indicates that only one CSS subsystem can take credit for the CST as a suction source during OPDRVs. Under these circumst'ances (performing OPDRVs). Action A is entered for one of the two required subsystems inoperable. This would allow 4 hours to restore a second subsystem. If this time is not met (which would happen if the suppression pool is intentionally drained). Action B. requires actions to suspend OPDRVs. This 4 hour extension to the requirements of CTS 3.5.3 when the operability of only one ECCS subsystem is impacted. does not result in a significant impact on safety due to the following:
- 1) the allowance is consistent with that approved in CTS 3.5.2 Actions: 2) the availability of the remaining operable subsystem:
- and 3) the low probability of an event during this limited time.
I FERMI UNIT 2 8 REVISION 7 06/18/99l
e DISCUSSION OF CHANGES ITS: SECTION 3.5.2 - ECCS-Shutdown i I l (. RELOCATED SPECIFICATIONS-None-
+
TECHNICAL SPECIFICATION BASES The CTS Bases for this Specification have been replaced by Bases that reflect the. format.and applicable content of ITS 3.5.2 consistent with the BWR STS. NUREG 1433. Rev. 1. i l 'i l l 1 3 l
. FERMI'-' UNIT 2 9 REVISION 7 06/18/99l
)
ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY (C T$ ) SR 3.5.2.2 Verify, f or each required core spray (CS) 12 hours i subsystem, the: 4. '/, p , 2 , Q (35.3,b) l i a. Suppression pool water level is P.I (3.5,5.6.l) i - -- TE---- - l Only one required CS subsystem may {j g g a edit for this option during 7,g,3, f 4 ) l 3* i i Condensate storage tank water level is [ 3.6.3. 6 3) f 2 f4 M +]. M'- l m h3..s5.. 2,,6 n >, f ') @)' i SR 3.5.2. Verify, for each required ECCS injection / l spray subsystem, the piping is filled with 31 days N /g* g,7,/ l\ 'b Y water from the pump discharge valve to the I injection valve. d4.5./.a..LQ
- A SR 3.5.2.4'
--9;w LPCI subsysteg may be considered
<45J,fh L h,l O6 OPERABLEduringaTIgnmentandoperationfor decay heat removal if capable of being Q.T.2 b 4Y) manually realigned and not otherwise inoperable.
Verify each required ECCS injection / spray 31 days ,3, p. / j subsystem manual, power operated, and l automatic valve in the flow path, that is 1
- not locked, sealed, or otherwise secured in ,[/. d . /. b) position, is in the correct position.
(continued)
-:ra/4 STS- 3.5-9 -P= 1 ^'/^7/05
_.s i i
--,yc ECCS-Shutdown 3.5.2 l
l J_NSERT 3.5.2-1 i \ l 1 SR.3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. 6 l l 1 i e FERMI UNIT 2 Page 3.5 9 (Insert) REVISION 7. 06/18/99l
o ECCS-Shutdown 3.5.2 SURVEILLANCE REOUIREMENTS (continued) SURVEILLANCE FREQUENCY ( C TS ) SR 3.5.2.f Verify each required ECCS pump develops the 5accordanc specified flow rate [against a system head with the , (7 corresponding to the specified reactor ;cInservice M I pressure). Testing Program ee-b [ SYSTEM HEAD NO. CORRESPONDING "2 2.,;- P.i Or TO 4 REACTOR - - SYSTEM FLOW RATE Bt!PJ PRESSURE OF1
, g, 7, j CS 2 gpu 2 psig LPCI 2-J300, gpa 1:1) 2 ( # =psig h'8e/*d/ i g @ { 4 5. l.f. 2 }
SR 3.5.2.f NOTE ------- Vessel injection / spray may be excluded.
/g,5,f./)
\
/
(4.5. l. C.I} Verify each required ECCS injection / spray ;{18} months subsystem actuates on an actual or j simulated automatic initiation signal. ~ l
- WR/, aTS-~ 3.5-10 au 1, W /; /S; ---
@v7
i ECCS-Shutdown B 3.5.2 BASES ACTIONS C.1. C.2. D.1. D.2. and D.3 (continued) { necessary to perfom the Surveillances needed to demonstrate the OPERABILITY of the components. If, however, any required component is inoperable, then it must be restored i to OPERABLE status. In this case, the Surveillance may need ! to be performed to restore the component to OPERABLE status. Actions must continue until all required components are OPERABLE. l The 4 hour Completion Time to restore at least one low pressure ECCS injection / spray subsystem to OPERABLE status ensures that prompt action will be taken to provide the required cooling capacity or to initiate actions to place the plant in a condition that minimizes any potential fission product release to the environment.
^
l
~
)
SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 id:ca+im of -4 inckes ( ! REQUIREME S O 9 dchaA hve O) l p't The minimum water level )Dt ft 1 inches equired for The suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for the CS System and LPCI subsystem pumps, recirculation volume, and vortex prevention. With the suppression pool water level less than the required limit, all ECCS injection / spray subsystems are inoperable unless they are aligned to an OPERABLE CST.
- 4G in l When suppression pool level is < .. ._ _ -.,, e CS !
System is considered OPERABLE only if it can take suction l from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a
-(4 verification that either the suppression pool water level 2 6 .i r inchesF or that CS is ali ged to take suction 'po ce from the esT mad ths. CST contains 2 "",-::L ailons of wate equivalent to N ft_. ensures that the CS System can upplyatleast{!!,^^^7gallonsofmakeupwa,terTtotheRPV !
The CS suction is uncovered at the i 00,000Nallon leve o 3^
- may ta %.
However, as noted, only one required CS subsystem f N gin fo ke I credit for the CST option during OPDRVs. During OPDRVs, the precb4M N volume in the CST may not provide adequate makeup if the RPV )4 7.;,m Men were completely drained. Therefore, only one CS subsystem i , l is allowed to use the CST. This ensures the other required i ECCS subsystem has adequate makeup volume. (continued)
- Mi ' E - B 3.5-20 L,1, ;;;;rja; w'
I
i ECCS-Shutdown B 3.5.2 ! BASES SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 (continued) REQUIREMENTS The 12 hour Frequency of these SRs was developed considering operating experience related to suppression pool water level and CST water level variations and instrument drift during ; the applicable MODES. Furthermore, the 12 hour Frequency is considered adequate in view of other indications available in the control room, including alarms, to alert the operator i to an abnormal suppression pool or CST water level !
.j g g rCT- condition.
l 7 Y g,g O j p . I SR 3.5.2. . SR 3.5.2.$.andSR 3.5.2.4 ' W The laseg provided for SR 3.5.1 SR 3.5.1. and i
// R 3.5.I3tr are applicable to SR 3.5.2 SR 3.5.2 A and SR 3.5.2 respectively. y gG, ;
SR 3.5.2] Verifying the correct alignment for manual, power operated, I' ! and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves were verified to be in the correct position < prior to locking, sealing, or securing. A valve that i receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it
' involves verification that thase valves capable of potentially being mispositioned are in the correct position. l This SR does not apply to valves that cannot be
{ inadvertently misaligned, such as check valves. The 31 day , Frequency is appropriate because the valves are operated under procedural control and the probability of their being '
- mispositioned during this time period is low.
In MODES 4 and 5, the RHR System may operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore, RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal Therefore, this SR LPCI subsystengof is modified the RHR bybeaconsidered System to Note thatOPERABL allows one or dofh g'j (continued) : BWR/ M T P B 3.5-21 ";. ;, ^'l0?/00
' mes8
l 1 ECCS Shutdc,wn B 3.5.2 INSERT B 3.5.2 1 l SR 3.5.2.3 i The LPCI System injection valves, recirculation pump discharge valves, and'LPCI cross tie valve are powered from the LPCI swing bus, which I must remain energized to support OPERABILITY of any required LPCI l subsystem. Therefore, verification of proper voltage and correct i breaker alignment to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate electrical power sources are j available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability j ensures that the required voltage is readily available for critical i system loads connecte'd to this bus. The 7 day Frequency takes into account the redundant capability of the AC, DC, and AC swing bus ' electrical power sources, and other indications available in the control room that alert the operator to subsystem malfunctions. i FERMI UNIT 2 Page B 3.5 21 (Insert) REVISION 7 06/18/99l
.__ e. . .-...c.. .d . . . .. e ,,
1
.. ......x....,..,. . ;...._.__.a _ __
l ECCS-Shutdown B 3.5.2 BASES
- /
SURVEILLANCE SR 3.5.2.4 (continued) b'3 REQUIREMENTS for the ECCS function if all the required valves in the LPCI ' flow path can be manually realigned (remote or local) to , allow injection into the RPV, and the system is not otherwise inoperable. This will ensure adequate core
. cooling if an inadvertent RPV draindown should occur.
REFERENCES
- 1. (AFSAR, Section 16.3.2J. !
l I l 9 9
-BWR/41W B 3.5-22 Re@4lc7jo3-L l
Aev 7
. t *
< l%
p: l JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.5.2 ECCS Shutdown
'NON BRACKETED' PLANT SPECIFIC CHANGES
, P.1 These changes are made to NUREG-1433 to reflect Fermi 2 current licensing basis:' including design features, existing license l r'equirements and comitments. Additional rewording, reformatting, l 'and revised numbering is made to incorporate these changes consistent j with Writer's Guide conventions.
- P.2 Bases' changes are made to reflect plant specific oesign details.
! . equipment terminology, and analyses. Some of these changes are specifically discussed below:
- a. LCQ
- In the NUREG (based on non LPCI loop select logic plants).
l- the cross tie valves would be required to be closed during Modes l 1, 2. and 3 and 3.5.2 Bases discuss how this is not required in ! shutdown Modes. However, with the Fermi-2 LPCI loop select logic, the cross-tie valves are required to be open in Modes 1
- 2. and 3. Therefore the Bases for the shutdown Modes is revised to reflect the exception for the Fermi-specific design.
1 FERMI - UNIT'2 1 REVISION 7. 06/18/99 l u
]
i NO SIGNIFICANT HAZARDS EVALUATION ITS:.SECTION 3.5.2.- ECCS - Shutdown l TECHNICAL CHANGES LESS RESTRICTIVE (Soccification 3.5.2 "L.2" Labeled Coments/ Discussions)
/
Not used. l
- s :
d g I w FERMI UNIT 2 3 REVISION 7 06/18/99l
NO SIGNIFICANT HAZARDS EVALVATION ITS: SECTION 3.5.2 - ECCS - Shutdown l TECHNICAL CHANGES - LESS RESTRICTIVE i (Scecification 3.5.2 "L.2" Labeled Comments / Discussions) ! l i
+
Not used. l FERMI UNIT 2 4 REVISION 7, 06/18/99l
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.5.2 ECCS - Shutdown TECHNICAL CHANGES - LESS RESTRICTIVE ISoecification 3.5.1 "L.3" Labeled Comments / Discussions) Detroit Edison has evaluated the proposed Technical Specification change identified is "Less Restrictive" in accordance with the criteria specified by 10 CFR 50.92 and has determined that the proposed change does not involve a significant hazards consideration. The bases for the determination that the proposed change does not involve a significant hazards consideration is an ovaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below.
- 1. Does the change involve a significant increase in the probability or consequencc: of an accident previously evaluated?
The proposed change allows 4 hours to restore two ECCS subsystems to operable status with at least one aligned to the suppression pool, prior to requiring suspension of OPDRVs. . This change will not significantly increase the probability of an accident previously evaluated because the amount of time allowed to restore equipment to 4 l s operable does not affect the initiators of any analyzed accident. This ' j change will not significantly increase the consequences of any accident previously evaluated because the remaining operable ECCS subsystem would k j be available to perform the core flooding function.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
This proposed' change will not involve any physical changes to plant systems, structures or components (SSC). The changes in normal plant operation are not in conflict with any current safety analysis assumptions. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. FERMI - UNIT 2 5 REVISION 7 06/18/99l
INSERT THIS PAGE IN FRONT OF VOLUME 6 , l Volume 6 SECT 1.ON 3.5. Remove Replace 3.5.1 ITS pg 3.5-3 Rev 0 3.5.1 ITS pg 3.5-3 Rev 7 3.5.1 ITS pg 3.5-4 Rev 0 3.5.1 ITS pg 3.5-4 Rev 7 3.5.1 ITS pg 3.5-5 Rev 0 - 3.5.1 ITS pg 3.5-5 Rev 7 3.5.1 ITS pg 3.5-6 Rev 0 3.5.1 ITS pg 3.5-6 Rev 7 3.5.1 ITS pg 3.5-7 Rev 0 3.5.1 ITS pg 3.5-7 Rev 7 3.5.1 ITS pg 3.5-8 Rev 0 -- B3.5.1 ITS pg B 3.5.1-3 Rev 0 B3.5.1 ITS pg B 3.5.1-3 Rev 7 B3.5.1 ITS pg B 3.5.1-9 Rev 0 B3.5.1 ITS pg B 3.5.1-9 Rev 7 B3.5.1 ITS pg B 3.5.1-11 Rev 0 B3.5.1 ITS pg B 3.5.1-1I Rev 7 B3.5.1 ITS pg B 3.5.1-13 Rev 0 B3.5.1 ITS pg B 3.5.1-13 Rev 7 B3.5.1 ITS pg B 3.5.1-17 Rev 0 B3.5.1 ITS pg B 3.5.1-17 Rev 7 3.5.1 CTS M/U (3/4 3-23) pg 1 of 10 3.5.1 CS M/U (3/4 3-23) pg 1 of 10 Rev 7 3.5.1 CS M/U (3/4 4-2) pg 2 of 10 3.5.1 GS M/U (3/4 4-2) pg 2 of 10 Rev 7 3.5.1 GS M/U (3/4 5-3) pg 5 of 10 3.5.1 CTS M/U (3/4 5-3) pg 5 of 10 Rev 7 3.5.1 CS M/U (3/4.7-3) pg 8 of 10 3.5.1 CS M/U (3/4 7-3) pg 8 of 10 Rev 7 3.5.1 DOCS pg 6 Rev 0 3.5.1 DOCS pg 6 R, 7 . 3.5.1 DOCS pg 7 Rev .0 3.5.1 DOCS pg 7 Rev 7 3.5.1 DOCS pg 8 Rev 0 3.5.1 DOCS pg 8 Rev 7 3.5.1 DOCS pg 9 Rev 0 3.5.1 DOCS pg 9 Rev 7 3.5.1 DOCS pg 10 Rev 0 3.5.1 DOCS pg 10 Rev 7 3.5.1 DOCS pg 1I Rev 0 3.5.1 DOCS pg i1 Rev 7 3.5.1 DOCS pg 12 Rev 0 3.5.1 DOCS pg 12 Rev 7 3.5.1 NUREG M/U pg 3.5-2 3.5.1 NUREG M/U pg 3.5-2 Rev 7 ! 3.5.1 NUREG M/U pg 3.5-3 3.5.1 NUREG M/U pg 3.5-3 Rev 7 3.5.1 NUREG M/U pg 3.5-4 (insen) Rev 0 3.5.1 NUREG M/U pg 3.5-4 (insen) Rev 7 3.5.1 NUREG M/U pg 3.5 5 3.5.1 NUREG M/U pg 3.5 5 Rev 7 B3.5.1 NUREG M/U pg B3.5-3 B3.5.1 NUREG M/U pg B3.5-3 Rev 7 B3.5.1 NUREG M/U pg B3.5-8 B3.5.1 NUREG M/U pg B3.5 8 Rev 7 B3.5.1 NUREG M/U pg B3.5-9 (insen) Rev 0 B3.5.1 NUREG M/U pg B3.5-9 (insen) Rev 7 B3.5.1 NUREG M/U pg B3.5-11 B3.5.1 NUREG M/U pg B3.5-11 Rev 7 I B3.5.1 NUREG M/U pg B3.5-12 B3.5.1 NUREG M/U pg B3.5-12 rev 7 B3.5.1 NUREG M/U pg B3.5-15 B3.5.1 NUREG M/U pg B3.5-15 Rev 7 Rev 7 06/18/99
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.5.2 ECCS - Shutdown TECHNICAL CHANGES - LESS RESTRICTIVE (Soecification 3.5.3 "L.3" Labeled Comments / Discussions) ;
- 3. Does this change involve a significant reduction in a margin of safety? !
,The proposed change does not involve'a significant reduction in a margin of safety because: 1)<the allowance is consistent with that approved in CTS 3.5'2 Actions: 2) the availability of the remaining operable f
subsystem; and 3) the low probability of an event during this limited time. 6 k i
' m#
FERMI UNIT 2- 6 REVISION 7 06/18/99l
L L RCIC System l 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LC0 3.5.3 The RCIC System shall be OPERABLE.
' APPLICABILITY: MODE 1 MODES 2 and 3 with reactor steam done pressure > 150 psig.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant Injection System is OPERABLE. M A.2 Restore RCIC System 14 days to OPERABLE status. B. Required Action'and B.1 Be in MODE 3. 12 hours associated Completion Time not met. ' E B.2 Reduce reactor steam 36 hours dome pressure to s 150 psig. J kl' FERMI-UNIT 2 3.5 12 Revision 7 06/18/99 I
l RCIC System i 3.5.3 l SURVEILLANCE REQUIREMENTS I SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to
~
the injection valve. ! i i SR 3.5 3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or l otherwise secured in position is in the correct position. SR 3.5.3.3 - ------
--- --NOTE- ---- ---- ---
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify. with reactor pressure s 1045 psig 92 days and a 945 psig, the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure. SR 3.5.3.4 -- - -
- ---- NOTE-- - - -- - -
Not.' required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. j Verify. with reactor pressure s 200 psig. 18 months the RCIC pump can develop a flow rate a 600 gpm against a system head l corresponding to reactor pressure. ' (continued) I gl FERMI-UNIT 2 3.5 13 Revision 7 06/18/99 ] L t _ I
RCIC System 3.5.3
. SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.3.5 --- --- -
---- --NOTE- -- -- - - - --
Vessel injection may be excluded. Verify the RCIC System actuates on an 18 months actual or simulated automatic initiation signal.
. g
i l 1 INSERT THIS PAGE IN FRONT OF VOLUME 9 Volume 9: SECTION 3.8 l Remove Replace 3.8.1 ITS pg 3.8-1 Rev 0 3.8.1 ITS pg 3.8-1 Rev 7 3.8.1 ITS pg 3.8-2 Rev 0 3.8.1 ITS pg 3.8-2 Rev 7 I 3.8.1 ITS pg 3.8-3 Rev 0 3.8.1 ITS pg 3.8-3 Rev 7 i 3.8.1 ITS pg 3.8-4 Rev 0 3.8.1 ITS pg 3.8-4 Rev 7 3.8.1 ITS pg 3.8-6 Rev 0 3.8.1 ITS pg 3.8-6 Rev 7 i B 3.8.1 ITS pg B 3.8.1-6 Rev 0 B 3.8.1 ITS pg B 3.8.1-6 Rev 7 l B 3.8.1 ITS pg B 3.8.1-7 Rev 0 B 3.8.1 ITS pg B 3.8.1-7 Rev 7 i B 3.8.1 ITS pg B 3.8.1-8 Rev 0 B 3.8.1 ITS pg B 3.8.1-8 Rev 7 B 3.8.1 ITS pg B 3.8.1-9 Rev 0 B 3.8.1 ITS pg B 3.8.1-9 Rev 7 B 3.8.1 ITS pg B 3.8.1-10 Rev 0 B 3.8.1 ITS pg B 3.8.1 10 Rev 7 l B 3.8.1 ITS pg B 3.8.1-11 Rev 0 B 3.8.1 ITS pg B 3.8.1 11 Rev 7 l B 3.8.1 ITS pg B 3.8.1-12 Rev 0 B 3.8.1 ITS pg B 3.8.1 12 Rev 7 j B 3.8.1 ITS pg B 3.8.1-13 Rev 0 B 3.8.1 ITS pg B 3.8.1-13 Rev 7 B 3.8.1 ITS pg B 3.8.1-14 Rev 0 B 3.8.1 ITS pg B 3.8.1-14 Rev 7 B 3.8.1 ITS pg B 3.8.1-15 Rev 0 B 3.8.1 ITS pg B 3.8.1-15 Rev 7 i B 3.8.1 ITS pg B 3.8.1-16 Rev 0 B 3.8.1 ITS pg B 3.8.1 16 Rev 7 B 3.8.1 ITS pg B 3.8.1-17 Rev 0 B 3.8.1 ITS pg B 3.8.1-17 Rev 7 B 3.8.1 ITS pg B 3.8.1-18 Rev 0 B 3.8.1 ITS pg B 3.8.1-18 Rev 7 B 3.8.1 ITS pg B 3.8.1 19 Rev 0 B 3.8.1 ITS pg B 3.8.1-19 Rev 7 B 3.8.1 ITS pg B 3.8.1-20 Rev 0 B 3.8.1 ITS pg B 3.8.1-20 Rev 7 l 3.8.1 CTS M/U (3/4 7-5) pg 1 of 8 3.8.1 CTS M/U pg 1 of 8 Rev. 7 3.8.1 CTS M/U (3/4 8-1) pg 2 of 8 Rev 2 3.8.1 CTS M/U (3/4 8-1) pg 2 of 8 Rev 7 3.8.1 CTS M/U (3/4 8-2) pg 3 of 8 Rev 2 3.8.1 CTS M/U (3/4 8-2) pg 3 of 8 Rev 7 3.8.1 CTS M/U (3/4 8-3) pg 4 of 8 3.8.1 CTS M/U (3/4 8-3) pg 4 of 8 Rev 7 3.8.1 DOCS pg 2 Rev 0 3.8.1 DOCS pg 2 Rev 7 3.8.1 DOCS pg 4 Rev 0 3.8.1 DOCS pg 4 Rev 7 3.8.1 DOCS pg 8 Rev 0 3.8.1 DOCS pg 8 Rev 7 3.8.1 DOCS pg 9 Rev 0 3.8.1 DOCS pg 9 Rev 7 3.8.1 DOCS pg 10 Rev 0 3.8.1 DOCS pg 10 Rev 7 3.8.1 NUREG M/U pg 3.8-2 3.8.I NUREG M/U pg 3.8-2 Rev 7 3.8.1 NUREG M/U pg 3.8-3 3.8.1 NUREG M/U pg 3.8-3 Rev 7 3.8.1 NUREG M/U pg 3.8-6 3.8.1 NUREG M/U pg 3.8-6 Rev 7 Rev 7 06/18/99
Volume 9: SECTION 3.8 (cont'd) Remove Replace 3.8.1 NUREG M/U pg 3.8-8 3.8.1 NUREG M/U pg 3.8-8 Rev 7 3.8.1 NUREG M/U pg 3.8-11 3.8.1 NUREG M/U pg 3.8-11 Rev 7 3.8.1 NUREG M/U pg 3.8-13 3.8.1 NUREG M/U pg 3.8-13 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-9 B 3.8.1 NUREG M/U pg B 3.8-9 Rev 7
. B 3.8.1 NUREG M/U pg B 3.8-9 (Insen) Rev 7 '
B 3.8.1 NUREG M/U pg B 3.8-10 B 3.8.1 NUREG M/U pg B 3.8-10 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-10 (Insen) Rev 0 B 3.8.1 NUREG M/U pg B 3.8-10 (Insen) Rev 7 B 3.8.1 NUREG M/U pg B 3.8-16 B 3.8.1 NUREG M/U pg B 3.8-16 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-16 (Insen) Rev 0 B 3.8.1 NUREG M/U pg B 3.8-16 (Insen) Rev 7 B 3.8.1 NUREG M/U pg B 3.8-17 B 3.8.1 NUREG M/U pg B 3.8-17 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-17 (Insen) Rev 0 B 3.8.1 NUREG M/U pg B 3.8-17 (Insen) Rev 7 B 3.8.1 NUREG M/U pg B 3.8-18 B 3.8.1 NUREG M/U pg B 3.8-18 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-27 B 3.8.1 NUREG M/U pg B 3.8-27 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-27 (Insen) Rev 7 _B 3.8.1 NUREG M/U pg B 3.8-28 B 3.8.1 NUREG M/U pg B 3.8-28 Rev 7 B 3.8.1 NUREG M/U pg B 3.8-34 B 3.8.1 NUREG M/U pg B 3.8-34 Rev 7 3.8.1 JFD's pg 2 Rev 0 3.8.1 JFD's pg 2 Rev 7 3.8.1 JFD's pg 3 Rev 0 3.8.1 JFD's pg 3 Rev 7 3.8.2 CTS M/U (3/4 7-5) pg i of 2 3.8.2 CTS M/U pg 1 of 2 Rev. 7 3.8.2 DOCS pg 3 Rev 0 3.8.2 DOCS pg 3 Rev 7 3.8.2 DOCS pg 4 Rev 0 3.8.2 DOCS pg 4 Rev 7 3.8.2 DOCS pg 5 Rev 0 3.8.2 DOCS pg 5 Rev 7 3.8.3 ITS pg 3.8-13 Rev 0 3.8.3 ITS pg 3.8-13 Rev 7 3.8.3 ITS pg 3.8-14 Rev 0 3.8.3 ITS pg 3.8-14 Rev 7 3.8.3 ITS pg 3.8-15 Rev 0 3.8.3 ITS pg 3.8-15 Rev 7 B 3.8.3 I. > pg B3.83-1 Rev 0 B 3.8.3 ITS pg B 3.8.3-1 Rev 7 B 3.8.3 ITS pg B3.8.3-2 Rev 0 B 3.8.3 ITS pg B 3.8.3-2 Rev 7 B 3.8.3 ITS pg B3.8.3-3 Rev 0 B 3.8.3 ITS pg B 3.8.3-3 Rev 7 i B 3.8.3 ITS pg B3.8.3-4 Rev 0 B 3.8.3 ITS pg B 3.8.3-4 Rev 7 B 3.8.3 ITS pg B3.8.3-5 Rev 0 B 3.8.3 ITS pg B 3.8.3-5 Rev 7 B 3.8.3 ITS pg B3.8.3-6 Rev 0 B 3.8.3 ITS pg B 3.8.3-6 Rev 7 B 3.8.3 ITS pg B3.8.3-7 Rev 0 B 3.8.3 ITS pg B 3.8.3-7 Rev 7 3.8.3 CTS M/U (3/4 8-1) pg 1 of 5 Rev 2 3.8.3 CTS M/U (3/4 8-1) pg 1 of 5 Rev 7 3.83 CTS M/U (3/4 8-3) pg 2 of 5 3.8.3 CTS M/U (3/4 8-3) pg 2 of 5 Rev 7 I Rev7 06/18/99 ! 1
{ 1 I Volume 9: SECTION 3.8 (cont'd) l Remove Replace 3.83 CTS M/U (3/4 8-4) pg 3 of 5 3.8.3 CTS M/U (3/4 8-4) pg 3 of 5 Rev 7 ) 3.8.3 CTS M/U (3/4 8-7) pg 4 of 5 3.8.3 CTS M/U (3/4 8-7) pg 4 of 5 Rev 7 I 3.8.3 DOCS pg 1 Rev 0 3.8.3 DOCS pg 1 Rev 7 I 3.8.3 DOCS pg 2 Rev 0 3.8.3 DOCS pg 2 Rev 7 3.8.3 DOCS pg 3 Rev 0 3.8.3 DOCS pg 3 Rev 7 3.8.3 NUREG M/U pg 3.8-21 3.8.3 NUREG M/U pg 3.8-21 Rev 7 3.8.3 NUREG M/U pg 3.8-22 3.8.3 NUREG M/U pg 3.8-22 Rev 7 l 1 3.8.3 NUREG M/U pg 3.8-23 3.8.3 NUREG M/U pg 3.8-23 Rev 7 l l' B 3.8.3 NUREG M/U pg B 3.8-41 B 3.8.3 NUREG M/U pg B 3.8-41 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-42 B 3.8.3 NUREG M/U pg B 3.8-42 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-43 B 3.8.3 NUREG M/U pg B 3.8-43 Rev 7 B 3.8.3 NUREG M/Upg B 3.8-44 B 3.8.3 NUREG M/U pg B 3.8-44 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-45 B 3.8.3 NUREG M/U pg B 3.8-45 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-46 B 3.8.3 NUREG M/U pg B 3.8-46 Rev 7 l
-B 3.8.3 NUREG M/U pg B 3.8-46 (Insen) Rev 0 B 3.8.3 NUREG M/U pg B 3.8-46 (Insen) Rev 7 l B 3.8.3 NUREG M/U pg B 3.8-47 B 3.8.3 NUREG M/U pg B 3.8-47 Rev 7 !
B 3.8.3 NUREG M/U pg B 3.8-47 (Insen) Rev 0 B 3.8.3 NUREG M/U pg B 3.8-47 (Insen) Rev 7 B 3.8.3 NUREG M/U pg B 3.8-48 B 3.8.3 NUREG M/U pg B 3.8-48 Rev 7 B 3.8.3 NUREG M/U pg B 3.8-49 B 3.8.3 NUREG M/U pg B 3.8-49 Rev 7 I 3.8.3 JFD's pg 1 Rev 0 3.8.3 JFD's pg i Rev 7 3.8.3 JFD's pg 2 Rev 7 3.8.3 NSHC pg i Rev 0 3.8.3 NSHC pg i Rev 7 3.8.3 NSHC pg 2 Rev 0 3.8.3 NSHC pg 2 Rev 7 3.8.3 NSHC pg 3 Rev 7 3.8.3 NSHC pg 4 Rev 7 3.8.4 ITS pg 3.8-17 Rev i 3.8.4 ITS pg 3.8-17 Rev 7 B 3.8.4 ITS pg B 3.8.4-2 Rev 1 B 3.8.4 ITS pg B 3.8.4 2 Rev 7 B 3.8.4 ITS pg B 3.8.4-3 Rev i B 3.8.4 ITS pg B 3.8.4 3 Rev 7 B 3.8.4 ITS pg B 3.8.4-4 Rev i B 3.8.4 ITS pg B 3.8.4-4 Rev 7 B 3.8.4 ITS pg B 3.8.4-5 Rev 1 B 3.8.4 ITS pg B 3.8.4-5 Rev 7 3.8.4 DOCS pg i Rev 0 3.8.4 DOCS pg i Rev 7 3.8.4 DOCS pg 2 Rev 0 3.8.4 DOCS pg 2 Rev 7 3.8.4 NUREG M/U pg 3.8-25 Rev 1 3.8.4 NUREG M/U pg 3.8-25 Rev 7 B 3.8.4 NUREG M/U pg B 3.8-51 B 3.8.4 NUREG M/U pg B 3.8-51 Rev 7 Rev7 06/18/99
l l Volume 9:' SECTION 3.8 (cont'd) Remove Replace B 3.8.4 NUREG M/U pg B 3.8-51 (Insen) Rev i -- B 3.8.4 NUREG M/U pg B 3.8-55 B 3.8.4 NUREG M/U pg B 3.8-55 Rev 7 B 3.8.4 NUREG M/U pg B 3.8-55 (Insen) Rev 0 B 3.8.4 NUREG M/U pg B 3.8-55 (Insen) Rev 7 3.8.5 DOCS pg 2 Rev 0 3.8.5 DOCS pg 2 Rev 7 3.8.5 JFD's pg 1 Rev 0 3.8.5 JFD's pg 1 Rev 7 l 3.8.6 ITS pg 3.8-22 Rev 0 3.8.6 ITS pg 3.8-22 Rev 7 3.8.6 ITS pg 3.8-23 Rev 0 3.8.6 ITS pg 3.8-23 Rev 7 B 3.8.6 ITS pg B 3.8.6-6 Rev 0 B 3.8.6 ITS pg B 3.8.6-6 Rev 7 l 3.8.6 CTS M/U (3/4 8-10) pg 1 of 3 Rev i 3.8.6 CTS M/U (3/4 8-10) pg I of 3 Rev 7 3.8.6 DOCS pg 3 Rev 0 3.8.6 DOCS pg 3 Rev 7 3.8.6 NUREG M/U pg 3.8-30 3.8.6 NUREG M/U pg 3.8-30 Rev 7 3.8.6 NUREG M/U pg 3.8-31 3.8.6 NUREG M/U pg 3.8-31 Rev 7 3.8.6 NUREG M/U pg 3.8-69 3.8.6 NUREG M/U pg 3.8-69 Rev 7 3.8.6 JFD's pg i Rev 0 3.8.6 JFD's pg i Rev 7 3.8.6 NSHC pg 5 Rev 7 3.8.6 NSHC pg 6 Rev 7 3.8.7 ITS pg 3.8-26 Rev 0 3.8.7 ITS pg 3.8-26 Rev 7 1 3.8.7 CTS M/U (3/4 8-14) pg 1 of 2 3.8.7 CTS M/U (3/4 8-14) pg i of 2 Rev 7 3.8.7 DOCS pg 1 Rev 0 3.8.7 DOCS pg 1 Rev 7 3.8.7 DOCS pg 2 Rev 0 3.8.7 DOCS pg 2 Rev 7 3.8.7 NUREG M/U pg 3.8-38 3.8.7 NUREG M/U pg 3.8-38 Rev 7 3.8.7 JFD's pg i Rev 0 3.8.7 JFD's pg i Rev 7 3.8.8 JFD's pg i Rev 0 3.8.8 JFD's pg i Rev 7 l Rev 7 06/18/99 l L
AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-0perating
)
LC0 3.8.1 , The following AC electrical power sources shall be OPERABLE:
- a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and i
- b. Two emergency diesel generators (EDGs) per division. j APPLICABILITY: MODES 1, 2. and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both EDGs in A.1 Perform SR 3.8.1.1 1 hour I one division for OPERABLE offsite inoperable. circuit (s). @ Once per 8 hours thereafter M-A.2 Declare required 4 hours from feature (s). supported discovery of an by the inoperable inoperable EDG EDGs inoperable when concurrent with the redundant . inoperability of required feature (s) redundant are inoperable. required feature (s) M A.3 Verify the status of Once per 8 hours CTG 11 1.
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k M (continued) l FERMI UNIT 2 3.8 1 Revision 7 06/18/99
AC Sources-0perating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLET10N TIME A. (continued) A.4.1 Determine OPERABLE 24 hours Al EDG(s) are not inoperable due to I common cause failure. E l A.4.2 Perform SR 3.8.1.2 24 hours ! for OPERABLE EDG(s). 7 E $ A.5 Restore availability of CTG 11-1. 72 hours from discovery of Condition A concurrent with CTG 11 1 not available V l
! A.'6 Restore both EDGs in 7 days the division to OPERABLE status.
B. One or both EDGs in B.1 Restore both EDGs in 2 hours both divisions one division to inoperable. OPERABLE status. C. Dr.e or two offsite C.1 Be in H0DE 3. 12 hours circuits inoperable. E @ Required Action and C.2 Be in H0DE 4. 36 hours Associated Completion Time of Condition A or B not met. l FERMI UNIT 2 3.82 Revision 7 06/18/99
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1 AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS ; i SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify-correct breaker alignment and 7 days ) indicated power availability for each ; offsite circuit. 1 SR' 3.8.1.2 ----- - --- ------NOTES- - - ---- - - ---
- 1. All EDG starts may be preceded by an 06 l engine prelube period and followed by a warmup period prior to loading.
- 2. A modified DG start involving idling
.d and gradual acceleration to 1 synchronous speed may be used for this 6 SR as recommended by the manufacturer.
l Verify each EDG starts and achieves steady 31 days state voltage = 3740 V and s 4580 V and l frequency = 58.8 Hz and s 61.2 Hz. SR 3.8.1~.3 --
- --- ---- - NOTES.- -- ---- -- -
- 1. EDG loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not invalidate this test.
- 3. This Surveillance shall'be conducted on only one EDG at a time.
Verify each EDG is synchronized and loaded 31 days l and operates for a 60 minutes at a load a 2500 kW. j (continued) l i l 1 l l FERMI UNIT 2 3.8 3 Revision 7, 06/18/99 J
1 4 I J AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FRE0VENCY SR 3.8.1.4 Verify each day tank contains a 210 gal of 31 days fuel oil. ~ SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank. I i 1 SR 3.8.1.6 Verify each fuel oil transfer system 31 days i operates to automatically transfer fuel oil from storage tanks to the day tanks. l SR 3.8.1.7 - --
- - -- - NOTE- - - -- --- --- - All EDG starts may be preceded by an engine 't prelube period and followed by a warmup EE period prior to loading. l nc ........................................... '
Verify each EDG starts from standby 184 days condition and achieves:
- a. In s 10 seconds. voltage a 3740 V and frequency a 58.8 Hz: and
- b. Steady state voltage a 3740 V and s 4580 V and frequency a 58.8 Hz and s 61.2 Hz.
SR 3.8.1.8 Verify each EDG rejects a load greater than 18 months j or equal to its associated single largest i post accident load, and following load l rejection the frequency is s 66.75 Hz. ! 1 1 (continued) j FERMI UNIT 2 3.8-4 Revision 7, 06/18/99
AC Sources-0perating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.8.1.11 - -- -- - ---
- NOTE --- -- ------ ---
All.EDG starts may be preceded by an engine prelube period. Verify on.an actual or simulated Emergency 18 months Core Cooling System (ECCS) nitiation signal each EDG auto starts and:
- a. In s 10 seconds after auto start and during tests, achieves voltage 3 jl = 3740 V and frequency = 58.8 Hz:
'O b. Achieves steady state frcluency I4 an s48dV an jl c. Operates for = 5 minutes.
SR 3.8.1.12 Verify each EDG's automatic trips are 18 months bypassed on an actual or simulated ECCS initiation signal except:
- a. Engine overspeed:
- b. Generator differential current:
- c. Low lube oil pressure;
- d. Crankcase overpressure: and
- e. Failure to start.
(continued) l FERMI - UNIT 2 3.8-6 Revision 7 06/18/99
l l l ! AC Sources-Operating B 3.8.1 BASES ACT!0NS (continued) I events existing concurrently is acceptable because it
. minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown.
The remaining OPERABLE EDGs and offsite circuits are l adequate to supply electrical power to the onsite Class 1E Distribution System. Thus, on a component basis, single failure protection for the required feature's function may have been lost: however, function has not been lost. The 4 hour Completion Time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required feature. Additionally, the 4 hour Completion Time takes into account the capacity and capability of the remaining AC sources, reasonable time for repairs, and low j probability of a DBA occurring during this period.
/L3 To minimize the impact of operation with an inoperable EDG, it is necessary to periodically ensure the availability of CTG 11 1. The verification of the status of CTG 111 is performed by an administrative check of breaker and line availability, and the CTG 111 ability to supply Division I :
loads. Since this Required Action only specifies " verify 1 6 the status." even when CTG 11 1 is not available it does not j result in this Required Actions being not met. However. l upon discovery that CTG 11 1 is unavailable, the limitations ! of Required Action A.5 are imposed. l A.4.1 and A.4.2 l 3l Required Action A.4.1 provides an allowance to avoid W W unnecessary testing of OPERABLE EDGs. If it can be determined that the cause of the inoperable EDG(s) does not exist on the OPERABLE EDGs, 9 3.8.1.2 does not have to be I performed. If the cause of inoperability exists on other ! EDG(s), they are declared ino>erable upon discovery, and ; Condition B of LC0 3.8.1 may />e entered. Once the failure < is repaired and the common cause failure no longer exists, i Required Action A.4.1 is satisfied. If the cause of the initial inoperable EDG cannot be confirmed not to exist on l the remaining EDG(s), performance of SR 3.8.1.2 suffices to provide assurance of continued OPERABILITY of those EDGs. y In the event the inoperable EDG(s) are restored to OPERABLE ; I status prior to completing either A.4.1 or A.4.2, the plant j l FERMI UNIT 2 B 3.8.1- 6 Revision 7 06/18/99 I
r i L AC Sources-Operating B 3.8.1 BASES ACTIONS (continued) corrective action program will continue to evaluate the
, common cause possibility. This continued evaluation, however, is no longer under the 24 hour constraint imposed while in Condition A.
According to Generic Letter 84 15 (Ref. 7). 24 hours is a reasonable time to confirm that the OPERABLE EDGs are not affected by the same problem as the inoperable EDG. 4l A.5 and A.6 According to Regulatory Guide 1.93 (Ref. 6), operation may continue with no OPERABLE EDGs to one division for a period that should not exceed 72 hours. With one or both EDGs in one division inoperable, the remaining OPERABLE EDGs and offsite circuits are adequate to supply electrical power to
- the onsite Class 1E Distribution System. Required Action 1 A.5 imposes this 72 hour Completion Time from the discovery
( of the non availability CTG 11 1. However, if CTG 111 is available to sup)1y Division I loads-(determined by administrative c1eck of breaker, line availability, and CTG 111 status) Required Action A.5 would be met and Required Action A.6 would allow the restoration time of 7 days. The 72 hour Completion Time to restore to at least one EDG in the division in OPERABLE status takes into account the capacity and capability of the remaining AC sources, reasonable time for repairs, and low probability of a DBA yl occurring during this period. The 7 day Completion Time to restore all EDGs to OPERABLE status takes into account the capacity and capability of the remaining AC Sources, as well as the additional reliability afforded by the availability of CTG 11-1. IL1 With one or both EDGs on both divisions inoperable, there may be no remaining standby AC source. Thus, with an assumed loss of offsite electrical power, insufficient standby AC sources are available to power the minimum required ESF functions. Since the offsite electrical power system is the only source of AC )ower for a significant percentage of ESF equipment at t11s level of degradation, the risk associated with continued operation for a very short time could be less than that associated with an immediate controlled shutdown. (The immediate shutdown s_ l FERMI - UNIT 2 B 3.8.1 - 7 Revision 7 06/18/99 ) l I
I AC Sources-Operating B 3.8.1 BASES ACTIONS (continued) could cause grid instability, which could result in a total loss of AC power.) Since any inadvertent unit generator trip could also result in a total loss of offsite AC power, however, the time allowed for continued operation is severely restricted. The intent here is to avoid the risk associated with an immediate controlled shutdown and to minimize the risk associated with this level of degradation. According to Regulatory Guide 1.93 (Ref. 6), with both divisions with EDGs inoperable, operation may continue for a period that should not exceed 2 hours. C.1 and C.2 If the inoperable AC electrical power sources cannot be restored to OPERABLE status within the associated Completion Time, the unit must be brought to a MODE in which the LC0 1 does not apply. Furthermore, with one or both offsite ; circuits inoperable, the Fermi design and subsequent plant i response is such that power operation is not justified, and a plant shutdown is required. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are ! reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. SURVEILLANCE The AC sources are designed-to permit inspection and REQUIREMENTS testing of all important areas and features, especially those that have a standby function, in accordance with 10 CFR 50. GDC 18 (Ref. 8). Periodic component tests are supplemented by extensive functional tests during refueling outages (under simulated accident conditions). The SRs for demonstrating the OPERABILITY of the EDGs are based on the recommendations of Regulatory Guide 1.9 (Ref. 3), Regulatory Guide 1.108 (Ref. 9), and Regulatory Guide 1.137 (Ref.10), as addressed in the UFSAR. Where the SRs discussed herein specify voltage and frequency tolerances, the following summary is applicable. The minimum steady state output voltage of 3740 V is 90% of the nominal 4160 V output voltage. This value, which is k l FERMI - UNIT 2 B 3.8.1 - 8 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) specified in ANSI C84.1 (Ref.11), allows for voltage drop to the terminals of 4000 V motors whose minimum operating voltage is specified as 90% or 3600 V. It also allows for voltage drops to motors and other equipment down through the 120 V level where minimum operating voltage is also usually specified as 90% of name plate rating. The specified maximum steady state output voltage of 4580 V is equal to the maximum operating voltage specified for 4000 V motors. It ensures that for a lightly loaded distribution system, the voltage at the terminals of 4000 V motors is no more than the maximum rated operating voltages. The specified minimum and maximum frequencies of the EDG are 58.8 Hz and 61.2 Hz. respectively. These values are ecual to i 2% of the 60 Hz nominal frequency and are derivec from the recommendations found in Regulatory Guide 1.9 (Ref. 3). SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are connected to their preferred power source and that appropriate independence of offsite circuits is maintained. The 7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room. SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the, standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown condition. To minimize the mechanical stress and wear on moving parts that do not get lubricated when the engine is not running. l tr.ase SRs have been modified by a Note (Note 1 for SR 3.8.1.2 and Note 1 for SR 3.8.1.7) to indicate that all EDG starts for these Surveillances may be preceded by an g engine prelube period and followed by a warmup prior to
, loading.
Y l l
' FERMI
. UNIT 2 B 3.8.1- 9 Revision 7 06/18/99 l
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i l l AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) For the purposes of SR 3.8.1.2 testing, the EDGs are started
+
anywhere from standby to hot conditions by using one of the following signals: Manual. l Simulated loss-of offsite power by itself. l Simulated loss of offsite power in conjunction with an ESF actuation test signal, or An ESF actuation test signal by itself. In order to reduce stress and wear on diesel engines, the ! EDG manufacturer recommends a modified start in which the i starting speed of EDGs is limited, warmup is limited to this lower speed, and the EDGs are gradually accelerated to synchronous speed prior to loading. These start procedures yl 2 are the intent of Note 2, which is only allowed to satisfy q SR 3.8.1.2 but are not applicable when performing SR 3.8.1.7. i SR 3.8.1.7 requires that, at a 184 day Frequency, the EDG , starts from standby conditions and achieves required voltage ' and frequency within 10 seconds. Standby conditions for an EDG mean that the diesel engine coolant and oil are being continuously circulated and temperature is being maintained consistent with manufacturer recommendations. The 10 second start requirement supports the assumptions in the design basis LOCA analysis of UFSAR. Section 6.3 (Ref.12). The 10 second start requirement is not applicable to SR 3.8.1.2. Since SR 3.8.1.7 does require a 10 second start it is more restrictive than SR 3.8.1.2 and it may be performed in lieu of SR 3.8.1.2. In addition to the SR requirements, the time for the EDG to reach steady state operation, unless the 9 modified EDG start method is employed, is periodically monitored and the trend evaluated to identify degradation of E governor and voltage regulator performance. If The normal 31 day Frequency for SR 3.8.1.2 is consistent with Regulatory Guide 1.9 (Ref. 3). The 184 day Frequency E for SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7). These Frequencies provide adecuate assurance of EDG OPERABILITY, while minimizing cegradation resulting from testing. l FERMI - UNIT 2 B 3.8.1 - 10 Revision 7. 06/18/99
AC Sources-Operating B 3.8.1 BASES
-SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.3 This Surveillance provides assurance that the EDGs are ' capable of synchronizing and accepting greater than or equal to the equivalent of the maximum expected accident loads al T y without the risk of overloading the EDG. The EDG is tested at approximately 90% of its continuous load rating which R provides margin to excessive EDG loading, while demonstrating the EDG capability to carry loads near the maximum expected accident loads. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the EDG is connected to the offsite source. Although no power factor requirements are established by this SR, the EDG is normally operated at a power factor between 0.8 lagging and 1.0. The 0.8 value is the design b rating of the machine, while 1.0 is an operational limitation to ensure circulating currents are minimized. D Routine overloading may result in more frequent teardown
.1 inspections in accordance with vendor recommendations in
( order to maintain EDG OPERABILITY. l The normal 31 day Frequency for this Surveillance is kll consistent with Regulatory Guide 1.9 (Ref. 3). Note 1 modifies this Surveillance to indicate that diesel engine runs for this Surveillance may include gradual loading, as recommended by the manufacturer, so that mechanical stress and wear on the diesel engine are minimized. Note 2 modifies this Surveillance by stating that momentary transients (e.g., because of changing bus loads) do not invalidate this test. Similarly, momentary power factor transients outside the normal range do not invalidate the test. Note 3 indicates that this Surveillance should be conducted on only one EDG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations. l FERMI. UNIT 2 B 3.8.1- 11 Revision 7 06/18/99
m AC Sources-Operating B 3.8.1 BASES-1 SURVEILLANCE REQUIREMENTS (continued) 1
- SR 3.8.1.4 This SR provides verification that the level of fuel oil'in the day tank is'at or above the level at which fuel oil is automatically added. The level.is expressed as an ecuivalent volume in gallons, and is selected to ensure acequate -fuel oil for a minimum of 1 hour of EDG operation at full load.
The 31 day Frequency is adequate to ensure that a susficient supply of fuel oil is available, since low level alrrms are provided and facility operators would be aware of ray large uses of fuel oil during this period. SR 3.8.1.5 i Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive. Removal of water from the fuel oil day tanks once every 31 days eliminates the l necessary environment' for bacterial survival. This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water i entrainment in the fuel oil during EDG operation. Water may come from any of several sources. including condensation, ground water, rain water, contaminated fuel oil, and breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref.10). This SR is for preventive maintenance. The presence of water does not necessarily represent a failure of.this SR provided that accumulated water is removed during performance of this Surveillance. SR 3.8.1.6 This Surveillance demonstrates that each required fuel oil I transfer pump operates and transfers fuel oil from its ) associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This Surveillance provides assurance that the fuel oil transfer pump is OPERABLE. the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the h l FERMI. UNIT 2 B 3'.8.1 - 12 Revision 7. 06/18/99 I y ! m_ .]
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) controls and control systems for automatic fuel transfer 3 systems are OPERABLE. The design of fuel transfer systems is such' that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG l testing. As such, a 31 day Frequency is appropriate, since ' proper operation of fuel transfer systems is an inherent part of EDG OPERABILITY. j SR 3.8.1.7 : 1 See SR 3.8.1.2. SR 3.8.1.8 1 Each EDG is provided with an engine overspeed trip to ' prevent damage to the engine. Recovery from the transient ! caused by the loss of a large load could cause diesel engine i overspeed. which, if excessive, might result in a trip of the engine. This Surveillance demonstrates the EDG load response characteristics and capability to reject the i largest single load while maintaining a specified margin to ! the overspeed trip. The largest single load for each EDG is a residual heat removal pump (1684 kW). This Surveillance may be accomplished by: j
- a. Tripping the EDG output breaker with the EDG carrying greater than or ecual to its associated single largest post accident loac while paralleled to offsite power, or while solely supplying the bus; or
- b. Tripping its associated single largest post accident load with the EDG solely supplying the bus.
As required by IEEE.308 (Ref.14), the load rejection test is acceptable if the increase in diesel s)eed does not ' exceed 75% of the difference between sync 1ronous speed and the overspeed trip set)oint. or 15% above synchronous speed, i whichever is lower. T1is represents 66.75 Hz, equivalent to 75% of the difference between nominal speed and the overspeed trip setpoint. 8gi~ j ; FERMI UNIT 2 B 3.8.1- 13 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) The frequency tolerances specified in this SR are derived from Regulatory Guide 1.9 (Ref. 3) recommendations for response during load sequence intervals. The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9). SR 3.8.1.9 This Surveillance demonstrates the EDG capability to reject a full load without overspeed tripping or exceeding the predetermined voltage limits. The EDG full load rejection may occur because of a system fault or inadvertent breaker tripping. This Surveillance ensures proper engine generator load response under the simulated test conditions. This test simulates the loss of the total connected load that the EDG ex>eriences following a full load rejection and verifies that t1e EDG does not trip upon loss of the load. These acceptance criteria provide EDG damage ;rotection. While the EDG is not expected to experience t1is transient during an event, and continues to be available. this response ensures that the EDG is not degraded for future application, including reconnection to the bus if the trip initiator can be corrected or isolated. The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.100 (Ref. 9) and is intended to be consistent with expected fuel cycle lengths. 4 i SR 3.8.1.10
)
As required by Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(1) this Surveillance demonstrates the as designed operation of the standby power sources during loss ; of the offsite source. This test verifies all actions I encountered from the loss of offsite power, including 1 shedding of the nonessential loads and energization of the i emergency buses and respective loads from the EDG, including - automatic start of the EDG cooling water pump. It further } demonstrates the capability of the EDG to automatically j achieve the required voltage and frequency within the a specified time. The EDG auto start time of 10 seconds is derived from requirements of the accident analysis for responding to a ! design basis large break LOCA. The Surveillance should be ! continued for a minimum of 5 minutes in order to demonstrate ! l FERMI - UNIT 2 B 3.8.1 - 14 Revision 7 06/18/99
n e l
)
AC Sources-0perating i B 3.8.1
)
BASES l SURVEILLANCE REQUIREMENTS (continued) I that all starting transients have decayed and stability has been achieved. The requirement to verify the connection and power supply of permanent and auto connected loads is intended to satisfactorily show the rel3tionship of these loads to the EDG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For
. instance. Emergency Core Cooling Systems (ECCS) injection valves are not desired to be stroked open, or systems are not capable of being operated at full flow, or RHR systems
)erforming a decay heat removal function are not desired to
)e realigned to the ECCS mode of operation. In lieu of !
actual demonstration of the connection and loading of these ' loads, testing that adequately shows the capability of the EDG system to perform these functions is acceptable. This testing may include any series of sequential. overlapping, or total steps so that the entire connection and loading sequence is verified. The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). l paragraph 2.a.(1), takes into consideration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the Note is to minimize wear and tear on the EDGs during testing. SR 3.8.1.11 ' This Surveillance demonstrates that the EDG (including its associated cooling water pump) automatically starts and achieves the required minimum voltare end frequency within the specified time (10 seconds) from the design basis actuation signal (LOCA signal) and operates for a 5 minutes. The 5 minute period provides sufficient time to demonstrate stability. The Frequency of 18 months takes into consideration plant conditions required to perform the Surveillance and is intended to be consistent with the expected fuel cycle lengths. Operating experience has shown that these l FERMI UNIT 2 B 3.8.1 - 15 Revision 7 06/18/99 1 e
l- AC Sources-Operating p B 3.8.1 BA ES SURVEILLANCE REQUIREMENTS (continued) components usually pass the SR when performed at the 18 month Frequency. Therefore. the Frequency is acceptable from a reliability standpoint. l This SR is modified by a Note allowing EDG starts to be l *
) receded by an engine prelube period. The reason for the t)te is'to minimize wear and tear on the EDGs during testing.
SR 3.8.1.12 This Surveillance demonstrates that EDG non critical l protective functions (e.g., high jacket water temperature)
- are bypassed on an actual or simulated ECCS initiation l signal and critical protective functions (engine overspeed.
l I generator differential current. low lubricating oil )ressure crankcase overpressure, and failure to start) trip t1e EDG to avert substantial damage to the EDG unit. The non-critical trips are bypassed during DBAs and provide an alarm on an. abnormal engine condition. This alarm provides the operator with sufficient time to react appropriately. 'The EDG availability to mitigate the DBA is more critical than protecting the engine against minor problems that are not 3 immediately detrimental to emergency operation of the EDG. j The 18 month Frecuency is based on engineering judgment. takes into consiceration l perform the Surveillance,and plant is conditions intended t) required to be consistent with ex>ected fuel cycle lengths. Operating experience has l J l , shown tlat these components usually pass the SR when
)erformed at the 18 month Frequency. Therefore, the treguency was concluded to be acceptable from a reliability
- standpoint.
SR 3.8.1.13 Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(3). requires . ! l. demonstration once per 18 months that the EDGs can start and j run continuously at full load capability for an interval of ; not less than 24 hours-22 hours of which is at a load 4 equivalent to the continuous rating of the EDG, and 2 hours l of which is at a load equivalent to 110% of the continuous ! duty rating of the EDG. Fermi 2 has taken.an exception to ; this requirement and performs the 22 hour run at 1 approximately 90% of the continuous rating (2500 kW- ; 2600 kW) ~ and performs the 2 hour run at approximately the j l FERMI UNIT-2 B 3.8.1 - 16 Revision 7 06/18/99 j
c AC Sources-Operating B 3.8.1
' BASES SURVEILLANCE REQUIREMENTS (continued) continuous rating (2800 kW 2900 kW). The EDG starts for
, this Surveillance can be performed either from standby or hot conditions. The provisions for prelube and warmup, discussed in SR 3.8.1.2, and for gradual loading, discussed
'in SR 3.8.1.3, are applicable to this SR.
Although no power factor requirements are established by l m this SR, the EDG is normally operated at a power factor i between 0.8 -lagging and 1.0.- The 0.8 value is the design R rating of the machine, while the 1.0.is an operational V limitation to ensure circulating currents are minimized. A load' band is provided to avoid routine overloading of the EDG. Routine overloading may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY. The 18 month Frequency is' consistent'with the recommendations of Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(3): takes'into consideration plant conditions required to perform the Surveillance: and is inPnded to be consistent with expected fuel cycle lengths. This Surveillance has been modified by a Note. The Note states that momentary transients due to changing bus loads do not invalidate this test. SR 3.8.1.14 This Surveillance demonstrates that the diesel engine can restart from a hot condition, such as subsequent to shutdown from normal Surveillances, and achieve the minimum required voltage and frequency within 10 seconds and maintain a steady state voltage and frequency range. The 10 second time is derived from the requirements of the accident
-analysis-to respond to a design basis large break LOCA. The 18 month Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(5).
This SR is modified by two Notes. Note 1 ensures that the
. test is performed with the diesel sufficiently hot. The Y. requirement that the diesel has operated for at least i 2 hours near full load conditions prior to performance of 1 this Surveillance is based on manufacturer recommendations iTl -for achieving hot conditions. Routine overloads may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY.
r
-l FERMI . UNIT 2 8 3.8.1 - 17 Revision 7, 06/18/99
]
L AC Sources-Operating B 3.8.1 L BASES- I SURVEILLANCE REQUIREMENTS (continued) Mcmentary transients due to changing bus loads do not
. invalidate this test. Note 2 allows all EDG starts to be-l< preceded by an engine prelube period to minimize wear and L
1 tear on the diesel during testing. SR 3.8.1.15 As required by Regulatory Guide 1.108 (Ref. 9). ) paragraph 2.a.(6). this Surveillance ensures that the manual ' synchronization and load transfer from the EDG to the offsite source can be made and that the EDG can be returned to standby status when offsite power is' restored. It also ; ensures that the. auto start logic is reset to allow the EDG ; to restart and reload if a subsequent loss of offsite power j occurs. The EDG is considered to be in standby status when the EDG is shutdown with the output breaker open, the load sequence timers are reset. and is able to restart and reload on a subsequent bus under voltage.. I L -The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9).
- paragraph 2.a.(6), and takes into consideration plant conditions desired to perform the Surveillance.
SR 3.8.1.16 Under accident conditions with loss of offsite power loads I are sequentially-connected to the bus by the automatic load ' sequencer. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading of the EDGs due'to high motor starting currents. The 10% load sequence time interval tolerance' ensures that sufficient time exists for the EDG to restore frequency and voltage
- i. . prior to^ applying the next load and that safety analysis L assumptions regarding ESF equipment time delays are not i violated. Reference 2 provides a summary of the automatic loading of ESF buses.
The~ Frequency of 18 months is consistent with the . reconnendations of Regulatory Guide 1.108 (Ref. 9). ' paragraph 2.a.(2): takes into consideration plant conditions required to perform the Surveillance: and is intended to be consistent with expected fuel cycle' lengths. j q B 3.8.1 - 18 hiFERMIIUNIT'2- Revision 7. 06/18/99 k k L .
= -
i AC Sources-Operating . B 3.8.1 l i BASES SURVEILLANCE REQUIREMENTS (continued) SR 3.8.1.17 In the event of a DBA coincident with a loss of offsite . power, the EDGs are required to supply the'necessary power l to ESF systems so that the fuel. RCS, and containment design ! limits are not exceeded. ' This Surveillance demonstrates EDG operation, as discussed l in the Bases for SR 3.8.1.10, during a loss of offsite power actuation test signal in conjunction with an ECCS initiation i signal. In lieu of actual demonstration of connection and ; loading of loads, testing that adequately shows the ; capability of the EDG system to perform these functions is ; acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified. The Frequency of 18 months takes into consideration plant conditions required to perform the Surveillance and is ! intended to be consistent with an expected fuel cycle length ! of 18 months. 4 This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the Note is to minimize wear and tear on the EDGs during testing. SR 3.8.1.18 This Surveillance demonstrates that the EDG starting independence has not been compromised. Also, this Surveillance demonstrates that each engine can achieve proper speed within the specified time when the EDGs are started simultaneously. j The 10 year Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the i Note is to minimize wear on the EDG during testing. l ( FERMI : UNIT 2 B 3.8.1 - 19 Revision 7 06/18/99 L
7-- AC Sources-Operating B 3.8.1 BASES REFERENCES 1. 10 CFR 50. Appendix A. GDC 17.
)
- 2. UFSAR. Sections 8.2 and 8.3.
- 3. Regulatory Guide 1.9.
- 4. UFSAR. Chapter 6.
- 5. UFSAR, Chapter 15.
- 6. Regulatory Guide 1.93. !
- 7. Generic Letter 84 15.
i
- 8. 10 CFR 50, Appendix A. GDC 18.
l
- 9. Regulatory Guide 1.108.
- 10. Regulatory Guide 1.137.
- 11. ANSI C84.1, 1982.
1
- 12. UFSAR. Section 6.3.
- 13. ASME Boiler and Pressure Vessel Code. Section XI.
- 14. IEEE Standard 308.
4
'T 4
l l FERMI -' UNIT 2 B 3.8.1-20 Revision 7 06/18/99 4
1 6PECtFtcNrto^) 5 f. / 4 l ff C)6 0WOYA
/rd K6V 7 i
1 1 1
. i l
l
, PAGE / OF 08 gg 7 ;
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&fCIFlMTioh).3.8I \
.3/4.8 ELECTRICAL POWER SYSTEMS
[ Al50 54 h C b #'I 3 ) 3/4.8.1 A.C. SOURCES A.C. SOURCES - OPERATING d,f i llMITING CONDITION FOR OPERATION LLO 3.8.1 As a minimum, the following A.C. electrical power sources shall be ' OPERA :
., p
- a. Two My .cr.5 ir2;;cannt circuits between the offsite l transmission network and the onsite Class IE distribution system, '
and 0.l
- b. Twolse ate and A depende onsite A.F. electrical power /sourgp, Div1ston I and Eivision ,[each consisting of two emergency dieselgeneratorsleac diesel generator wi @j 643,8,lM 1. A separate day fuel tank containing a minimum of 210 gallons of fuel,
/I jS ) 2. A separate fuel storage system containing a minimum of
\ P "y g.y
, 3 g [ 35,280 gallons of fuel, and
- 3. A n;.:r;te f;;l tr=:f:r p=;. _ (p APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION: a With one or both offsite circuits of the above required A.C. 4c.w (. electrical power sources inoperable, be in at least HOT SHUTOOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; .
'demonst te the OPERABI Y of the remain A . t. , sources perfo ing Surveillan Requirement 4.8 .l.1. within one ur and mat ast once per 8 ours thereafter dg A
MbM kb. With one or both diesel generators in one of the above required onsite A.C. electrical power divisions inoperable; b kt A,) 1. ' Demonstrate the OPERABil.ITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1 within one 6 1 , _ hour and at least once per 8 hours thereafterf ana if he (dieyan generator (s) ecame inoperaos aue to any ca eot]er h that an inoperabl support system, independenti testablel gdmponent, or or planned preventi e maintenance testina.1 l kejbcb 4.47 --l)iy/ dieselperforming generator atSurveillance a time within 24Requirement hours, unless the 4.8.1.1.2.a.4 for one ACE 4 I absence of any potential common mode failure for the f 4.2 ! 8 remaining diesel generators is determined, and lg .s FERMI UNIT 2 3/4 8-1 Amendrient No. Pf,119 PAGE L OF 08 hv 7
FLECTRICAL POWER SYSTEMS LIMITING CON 01 TION FOR OPERATION (Continued) 32,3 3 (Continued) R Y AcA A 3 2. verify within 8 hours and at least once >er a hours 4 thereafter. that CTG 11-1 is OPERABLE. Restore the get Act AD inoperable division to OPERABLE status within 7 days or be lg V in at least HOT SHUTDOWN within the next 12 hours and in AcT7oN C- COLD SHUTDOWN within the following 24 hours. -
- 3. Of t requirements f ACTION b.2. abdve for CTG 11-1 '
be . either re re the inocerabW division k' tEj to OPhmno l<sta within 72 msRnot to exceto 1 Days uw we ume Ref Ad 4 6 the' division beca'me ino>erable): or satisfy the
, !l! requirements of ACTION .).2 above within 72 hours and restore L ReIAck AS ', f the inoperable division to OPERABLE status within 7 daysfrom th k least HOT SHUTDOWN within the next 12 hours and in COLD A'W g f)l SHUTDOWN within the following 24 h , - - . - . -.
- c. With one or both diesel generators i one f the above required onsite A.C. electrical power divisions inoperable. in addition to \ i b Ar t A7. ACTION b. above verify within @ hours that all required systems
/
subsystems, trains. components and devices
- that depend on the g remaining onsite A.C. electrical power division as a source of emeroency power are also OPERABLE: o ~ . wise. De ut at least wi ,
n ap nours o inCOLDSyV0WNwithifth5 wgn n 7 ( ordeclare rekk4- k%re. ine) d With both of the above recuired onsite A.C. electrical power AtTio d 6 divisions inoperable:
- 1. Demonstrate the OPERABILITY of the remaining A.C. Sources by M bl performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours thereafter: and g m Ac4 6,/ 2.
Restore at least one of the above required inoperable 7 s divisions to OPERABLE status within 2 hours or be in at least HOT SHUTDOWN within the next 12 hours ar' in COLD MTloMC. SHUTDOWN within the following 24 hours; and 3 Restore the second of the above required divisions to drN A'6 OPERABLE status within tne time required by Action b above from the time of initial bss or be in at least HOT SHUTDOWN Ac.T20pj C. within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
*Except for an inoperable primary containment oxygen monitoring hN instrumentation channel, required by Specification 3.3.7.5. that depends on A,%-- the remaining OPERABLE onsite A.C. electrical power division. In this case. r take the ACTION required by Specification 3.3.7.5 for the inoperability of both required primary containment oxygen monitoring instrumentation channels.
FERMI . UNIT 2 3/4 8 2 Amendment No. 119. 132 PAGE S OF 08 g,97
l 1 l 5PectFiorniva 3 5? I ELECTRftat p0WER SYSTEMS
# 64 h##IOC4b 'E'bI'3 SURVEfttANCE REOUTREMENTS gg 3,9,;, ; 4.E.i.i. c Each of the above required independent circuits between the offsite l.
transmission network and the onsite Class IE distribution system shall be , J determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availat. ity.
-t.".I.I.2 Each of the above required diesel generators shall be demonstrated OPERABLE:
i
- a. At least once per 31 days [: ; =:== 15:T "aS.i By:
l 25.2.l.9 1. Verifying the fuel level in the day fuel tank. (su Spec.ficab3.r.3g2. Verifying the fuel level in the fuel storage tank. g y,g'f' g 3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank.
- 4. r T_
Verifying the diesel startsifr(om_E.t Hii = . T R S g'I. 7 ,19 sabient condition and accelerates to at least(900 rpalin less than or equal to g g*g*7 I 8
?0 seconds.* Thergenerator voltage and frequency shall be I 4160 e 4ZD volts and 60 e 1.2 Hz ef t"a M ccr-e Mte-tS Itirt c i- :'. . _fTh cieses geners6 snasi oc st tea to r Ini test my usi one of the fo owing signal :
a Manual. Simula d loss-of-offs e power by i El f. tgg c) Simul ed loss-of-off ite power in njunction ith an ESF tuation test gnal, d) An F actuation t t signal by i el f. sR 3.g .g.3 5. Verifying the diesel generator is synchronized, loaded to Lreater than or equal to an indicated 2500-2600 kW in
', l. . g,g 1, - fac.cordance with the manufacturer's recommendations, and i
operates i MDD No4c 2 fps go A:. 3 is load for at least 60 minutes. 3 t-MMNm;);;8m"re-h4%9"* ";" *
- 7. Verifying the pressure in all diesel generator air start
" ' M C b. 3* D receivers to be greater than or equal to 215 psig.
% y.RI7 SE 5.1.s.1 #8k Aok.t' --< uM s a,4Q,dowed bya wumuy f quiof riorlo I dinh lh 34 M*l l4 8'*k 1 may Am peceded by an engine prelube period.All diesel The diesel generatar start generator starts for the p 44 3.S.I . 7 (10 see) from ambient conditions shall be performed at least
~
onta .oer 184this the p;:rpose.cf days in thesetesting arveiriance surveillance may be tests. precededfall by other otherengine warmuostarts for { St3.T.t h { hjok. 3 Qear g the diesel enp(ne is minimized.( ,eroceduresfeconsnenoeo py the
- manufact Y
4 FERMI - UNIT 2 3/4 8-3 Amendment No. JJ,107 PAGE k 0F 08 ge,7
r 1 DISCUSSION OF CHANGES ITS: SECTION 3.8.1 AC SOURCES 0PERATING ;
.A.5 CTS 4.8.1.1.2.a.4 footnote *. is silent on limitations or allowances between starting and loading the EDG. ITS SR 3.8.1.2 Note'2. and SR 3.8.1.7 Note, explicitly acknowledges that the :=
monthly EDG start may be "followed by a warmup period prior to 2. loading." Additionally. CTS 4.8.1.1.2.a.4 footnote *. allows. for all EDG starts other than the 184 day 10 second start, that
" testing may be preceded by other warmup procedures." ITS does l@
not impose a pre condition on any EDG start other than the 184 day start to be "from standby condition." Therefore, performing the monthly EDG start after " warmup procedures" is not precluded. These changes do not reflect any revision in requirement, or change in intent. The changes are editorial presentation preferences only. A.6 Not used. lh A.7 CTS 4.8.1.1.2.e.5. 6..and 7 require the performance of an EDG functional test, which includes the requirement for: a " test i signal." " simulating" a signal, or "an emergency start signal." ITS SR 3.8.1.11, 17.-and 12 (respectively) permit the system functional to be initiated by an " actual or simulated" signal. This change allows satisfactory automatic EDG starts, as well as appropriately simulated EDG starts. to be used to fulfill the system functional Surveillance requirement. Operability is > adequately demonstrated because the EDGs can not discriminate between " actual" or " test" start signals. Since this is a reasonable interpretation of the existing requirement, this is an administrative change. FERMI UNIT 2 2 REVISION 7 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.8.1 AC SOURCES-0PERATING TECHNICAL CHANGES LESS RESTRICTIVE
" Generic" LA.1 CTS LC0 3.8.1.1 provides details defining the two offsite AC power s'ources. and design features of the EDGs (i.e. " separate and independent," " Division I and Division II. each consisting of two emergency diesel generators." and "A separate fuel transfer T pump"). The details relating to system design. function. and o Operability are not necessary in the ITS. These details are o relocated to the Bases, which maintains the consistency with -
NUREG 1433. The definition of Operability the Bases outline of k Operability details (which requires change contros in accordance with ITS 5.5.10. Bases Control Program), and the surveillance requirement for the fuel oil *cansfer pump (ITS SR 3.8.1.6). - provides sufficient control of these details. These details are l not required to be in the ITS. and ITS LCO. to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. LA.2 CTS SR 4.8.1.1.2.a.4 details the options for the start signals that can be used for the monthly EDG start. These details are relocated to the Bases. The relocation of this information maintains the consistency with NUREG-1433. This is acceptable because these details do not impact the requirement to start the EDG. These details can be adequately defined and controlled in the Bases, which require change control in accordance with ITS 5.5.10. Bases Control Program. These details are not required to i be in the ITS to provide adequate protection of the public health ! and safety since the requirement for EDG Operability remains in the Technical Specifications. LA.3 CTS 3.7.1.4 includes details relating to system design. function. and Operability for the EDG Cooling Water System. ITS 3.8.1 T includes only a requirement for EDG Operability and relocates the o details of subsystem design and specific Operability requirements O to the UFSAR. This is acceptable because thera details do not impact the requirement to maintain the EDG Operable and the ITS g definition for Operability ensures that all equipment required to maintain Operability is functioning. These details can be adequately defined and controlled in the UFSAR which require change control in accordance with 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of s~ . the public health and safety acceptable because these details do not impact the requirement to maintain the EDG Operable. FERMI UNIT 2 4 REVISION 7 06/18/99l
T I DISCUSSION OF CHANGES ITS: SECTION 3.8.1 - AC SOURCES 0PERATING LR.1 CTS SR 4.8.1.1.2.a.6 requires an explicit verification that the EDG is aligned to provide standby power to the associated emergency buses. This SR is not specifically detailed in the ITS. Procedural controls on EDG standby alignment, and the definition df Operability are sufficient to ensure the EDG remains aligned to provide standby power. The relocation of this information maintains the consistency with NUREG 1433. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do not impact the requirement to maintain the equipment Operable. LR.2 CTS SR 4.8.1.1.2.e.8 requires the 24 hour EDG run be associated with a 10 second start, and requires confirmation of steady state ! voltage and frequency. Since the 10 second start requirement, and l the required operating voltage and frequency are stated and ; verified in other Surveillances explicitly repeating those requirements in the 24 hour run Surveillance is not necessary. These details can be relocated from the Technical Specifications. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since the requirement for EDG Operability, verification of 10 second start capability. and verification of 24-hour run capability, remains in the Technical Specifications. LR.3 CTS SR 4.8.1.1.2.f requires a demonstration of EDG Operability "after modifications which could affect EDG interdependence." This requirement is relocated from the Technical Specifications. Verifying proper operability, including a simultaneous.EDG start, after maintenance on the EDG that could affect the simultaneous start is consistent with normal maintenance and operating practice for post-maintenance testing. Consequently. relocation of the requirement to verify Operability of the EDGs after maintenance is considered acceptable, and also maintains consistency with NUREG 1433. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do not impact the requirement to maintain the EDG independence and Operability. T LR.4 Not used. lg FERMI UNIT 2 8 REVISION 7. 06/18/99l
I 1 l DISCUSSION OF CHANGES ITS: SECTION 3.8.1 AC SOURCES 0PERATING l 1 LR.5 CTS 4.7.1.4 requires explicit verification of the proper positioning of the valves in the EDG cooling water flow path every l 31 days. ITS does not retain this explicit verification; however. ITS SR 3.8.1.2 and SR 3.8.1.3 does require EDG start and run (for a' minimum of 60 minutes). Since the EDG cooling water system provides the required cooling for all EDG operation the proper lineup is implicitly assured every 31 days by satisfactory operation of the required EDG load run. Regulatory control of changes to these requirements (e.g. Technical Specification j amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do not impact the requirement to maintain the EDG in an Operable status. l l FERMI - UNIT 2 9 REVISION 7, 06/18/99lh
DISCUSSION OF CHANGES ITS: SECTION 3.8.1 - AC SOURCES 0PERATING TECHNICAL CHANGES - LESS RESTRICTIVE 'Speci fic" L.1 CTS 3.8.1.1 Action a in addition to commencing an immediate plant shutdown with one or both offsite circuits inoperable, requires performance of CTS 4,8.1.1.1 (offsite circuit breaker alignment and power availability) within 1 hour and once per 8 hours thereafter. This verification of offsite circuit status is deleted. The verification is only required when one of two offsite circuits is inoperable, and even if the second circuit were to be discovered inoperable, no additional Actions or more restrictive time to complete the plant shutdown would be imposed. Since the plant is required to commence an immediate shutdown (be in MODE 3 in 12 hours) with one or both circuits _ inoperable, eliminating an increased frequency for verification of offsite circuit status will not adversely impact safety. L.2 With one EDG inoperable, CTS 3.8.1.1. Action c requires all features that depend on the remaining Operable EDG Division to be Operable. If this requirement can not be met, the CTS Action ! requires a shutdown be commenced within 2 hours. ITS 3.8.1 Required Action A.2 provides two relaxations: l@
- 1. Rather than a plant shutdown requirement, the ITS requires that the feature (s) supported by the inoperable EDG be declared inoperable if its redundant counterpart is inoperable. This provides for actions appropriate to the actual inoperabilities, which may avoid an immediate shutdown. For example, if one or both Division II EDGs are inoperable in conjunction with the Division I hydrogen recombiner, CTS Actions would require the immediate shutdown, while ITS would allow entering Actions for both hydrogen recombiners inoperable (a 7 day allowance is provided in the ITS Specification for hydrogen recombiners): thereby providing for the entire Completion Time to restore the EDG to Operable status. '
- 2. . ITS allows 4 hours (versus 2 hours) to restore inoperable features or inoperable EDG(s). This extension provides additional time, and is considered a reasonable time to effect repairs prior to requiring a forced shutdown of the unit.
FERMI - UNIT 2 10 REVISION 7 06/18/99l
AC Sources-Operating 3.8.1
, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME (A. ( % tinued) / A.3 R ore [ required) 42 hours fsite circuit to OPERABLE status. ANQ 6 days from discovery f failure meet LCO _ d Qr6of EOd'D One 3. ,....., -
1 Perform SR 3.8.1.1 1 hour f inoperable. for OPERABLE
- n _... ._n-offsite AND deMm b) in orie divial circuit (s). Ac han cl .1 Once per 8 hours thereafter 2 Declare required 4 hours from feature (s),supporte discovery of ANan C by the inoperable ,C=ditir "
inoperable when the concurrent'with redundant required inoperability of feature (s) are redundant inoperable. required feature (s)
* @W' (continued)
).3 WilYY CUS DM fw T of CTCr //~l . gpg Q t
WR/4-STS- 3.8-2 Rev 1, 04/07/05-4/7 1 l l
AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
- f. (continued) M.1 OPERABLE f24} hours e inoperable due to )
common cause failure. $tiloA) b. g E < E I y
.'[ @2 Perform SR 3 .l.2 J24yhours 0 5/
for OPERABLE (s).
% dae.vh-gg j %t-n1o nYok ^
h J-'in 1 F :- N'95- 72 hours h e b b.3 )
- ? ? "l-
{AchmbY) A. 6 Resfere bow EOGs in -( Adond.3) tk division fp DPdAftE s w .. . _ _-e w[ # 23 bn=2-
'. iwo tr rea] offsite L.a uud r. .wyuired 42 nuu. . . ' . - . . .
circui inoperable. feature (s) inop able discovery of when the redun nt Condition required fea re(s) concurren with are inopera e. inopera lity of redund t requ ed f,f fea re(s) en C.2 Re ore one 24 hou equired) offsite y ircuit to OPERABL ) tatus. s (continued) BHR/4-STS- 3.8-3 Re" 1, 01/07/05 1
\
Rw 7
)
l l AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS <CD # SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days l indicated power availability for each
--' __; offsite circuit.
h43*l l) l SR 3.8.1.2 -------,-- --NOTES 4.,_ _ _------------
- 4. . .. . .. .m ... .........
d
. Al starts may be preceded by an engine prelube period and followed by T *l L18 y 3i a wamup period prior to loading.
#. A modified DG start involving idling g and gradual acceleration to i synchronous speed may be used for this ,
P.6 "' > sR as reco end.d by the manufacturer.* When noatri start proced es are n { I used, the , voltage, d freque ey toleranc of SR 3.8.1.7 must be .t . Verify each starts ?. _ ;t r e; ; As ;;,;;i-d 4-k.l '"t n .fiti n; and achieves steady state Te n S.^.'-1 voltage 2 (3740E V and s 14580 V and frequency 2 p8.8gHz and s LS .2kHz. 34 16 l.ll,d.h' (continued) 17./4 MS- 3.8-6 Rev 1, 04/07/95 t
1 AC Sources-Operating
..u.1 l
SURVEILLANCE REQUIREMENTS (continued) [C75h w SURVEILLANCE FREQUENCY h t i SR 3.8.1.7 ---
---------NOTE------- ---------
All DG starts may be preceded by an engine e\
, and Q(ow b prelube period O warm q wiedp/,9 rf 4/,2. l. ).2 a N.Vs/
.tv ioa *nj ; a. ',
Verify each starts from st 184 days (48.l<\.2AY condition and achieves in s seconds,+ bb .'
= - - -
voltage 2 (3740kV and s J'45801 V and V0It* b' frequency 2M8.gHz and's QI'.2} Hz. Op%L 13700 V Oe4151 T (b S M Ns h j t SR 3.8. 8
- - - - - - - - - - - - / -----/-
Q+ This urveillan TE---- / shallnotbeperform[d' k' in DE 1 or P However redit may 6e en for u anned eve s that sa sfy /
.hir SR.
m /- Verif [ automatic and manua tran er month of nit power s ply))from e [no al y of ite circuit o the alte ate] j c fsite circui . / (continued) EWR/4-STS- 3.8-8 Re % -04/07/M-8ev 7
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) _ SURVEILLANCE TREQUENCY SR 3.8.1. --- g---- ----NOT EY---------------- - p h A11 DG Istarts may 'n preceded by an (DK 4.g) engine prelube period.
+
Thi Survei ance sh 1 not be f p formed n MODE or 2. H ever,
@ /2 edit events be tak for unp nned at sati y this S .
l i i gr @.a.zo) Verify on an actual or simulated Emergency /18monthsb Core Coolin System (ECCS) initiation signal each auto-starts f = - u.._f e%. an \} %- .I
- a. In 5 seconds after auto-start and during tests, achieves voltage fres"8 d/ ) 2 (374 g V a p T C ;] % [( {l
- b. In ; [! C : ent -'te rfte-ste-t , h rnd fr-'r; *er+ ;Jehieves frequency hJ58.81Hzandf$1.2[ lf ,
( i
- c. 'Operatesfor235} minute, i y
- d. Pe anently con cted loads r in ergized fr the offsite wer Y # >
fk "A 6 4M % system; and g e Emergency ends are en gized[or h auto-co ected throu the automa e load .quencer) fr the offdt nower y i syst (continued) WR/' STS 3.8-11 Rev-h-04/OU95-- Rev 7
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.8.1 ------------------NOT E S-------------------
- 1. Homentary transients outside the load 0g (,, L ,
, p,i wnrt TMENF-fEPN range [do not invalidate this test.
2 This urveill ce shall t be O91 per ormed in E I or . Howeve , dit may taken f unplann vents t t satisfy his SR. Verify each :;; ret h; it : ;: :7 n; 3 r hE18monthsA OP.I.. S " e! coerates for 1 24 hours:
@!i but the, kal t 2 novrs) 29,0
/
Nd I.I'2*8,3\ / a .- tot ^M nours loaded 2 kW and 5 - =
-kW;an[d-ft nal _t 2.)e
- b. Fo --- =: hours of the test loadedi kW and s kW.
24 SR 3.8.1. ----------------- NOTES ---------------- I4
- 1. This Surveillance shall be performed (g g.t.t.2.c. 9, h
@within5minutesofshuttingdownthe after the has operated kW e,r./ :
2L g oaded 2 ggi,gg E heakm h,x , Momentary transients outside of load stab:U.r.e d ) ran do not invalidate this test.
- 2. All starts may be preceded by an engine prelube period. / g g' g~
h.N' v. e.l.2.a 4 *-) rify each starts and achieves )R8monthsK
$ $Ji seconds, voltage 2 (3740F V and / \
M8t} V and frequency 2 JJ8.8) Hz and (LI I'I'I'7' d g,g/ sf61.2)Hz. q,g ,g ,g ,7,q, q) m - yo y_g 3.j. g y ,ng g (continued) hEs.sh ;a4 1(.l 9
- b. A dy s h tz, lg SWR /4-STS 3.8-13 h v 1, 04/07/95 s
sev7
AC Sources-Operating B 3.8.1 BASES ACTIONS M (continued) concurrently is acceptable because it minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown. The remaining OPERABLE DGs and offsite circuits are adequate to supply electrical power to the onsite Class 1E Distribution System. Thus, on a component basis, single failure protection for the required feature's function may have been lost; however, function has not been lost. The 4 hour Completion Time takes into account the component OPERASILITY of the redundant counterpart to the inoperable , required feature. Additionally, the 4 hour Completion Time i takes into account the capacity and capability of the
/NSE7ET remaining AC sources, reasonable time for repairs, and low probability of a DBA occurring during this period.
B 3 8.\ - 2 4
. 1 an .2 {
Required Action 1 provides an. allowance to avoid (5) '\ unnecessary testing of OPERABLE DGs. If it can be de3 mined that the cause of the inoperable DG oes not h exist on the OPERABLE perfomed. If the cavre of D6t SR 3.8.1.2 inoperability does exists h not have to be -i on other DG(s), therare declared inoperable upon discovery. and mo tion t1&of LC0 3.8.16& entered. Once the failure is k
'@~Cond<
C repa' red, and th onnon cTuse failure no longer exists, Required Actio 1 is satisfied. If the cause of the initial inoperable DG cannot be confimed not to exist on '% the remaining DG(s), performance of SR 3.8.1.2 suffices to provide assurance of continu LITY of those DGs. I
! f,I In the event the inoperable cred PERABLE A'
status prior to completing either 1 or 2,the(plant corrective action programF will con 31nue to evaluate tne common cause possibility. This continued evaluation, however, is no longer under the 24 hour constraint imposed while in Condition *
.A According to Generic etter84-15(Ref.7),[24[hoursisa reasonable time to confirm that the OPERABLE DGs are not affected by the same problem as the inoperable DG.
(continued) 8WR/4-STS- 8 3.8-9 ki 1, 04/07/05
#ev7 4
AC Sources Operating B 3.8.1 Insert B 3.8.1-8 Ad. _ i To minimize the impact of operation with an inoperable EDG, it is necessary to periodically ensure the availability of CTG 111. *R The verification of the status of CTG 11-1 is performed by an administrative check of breaker and line availability, and the ! CTG 111 ability to supply Division I loads. Since this Required Action only specifies " verify the status." even when CTG 111 is not available it does not result in this Required Actions being not met. However, upon discovery that CTG 11 1 is unavailable, the limitations of Required Action A.5 are imposed. FERMI UNIT 2 Page B 3.8 9 -(Insert) REVISION 7 06/18/99l
AC Sources-Operating B 3.8.1 BASES - i ACTIONS (continued) p. a=h ondh i v>ith no OPETEAoSLE EDGs % me divi jan S h j _ T According to Regulatory Guide 1.g3 (Ref 6), operation may Mg#*M gEDGs) continue is Cei. 73 hours.,:a tier. Cer. C for
- tier. a period O, the that remaining should not OPERABLE DGsexceed and in nit d
- Vi3* o fsite circuits are adequate to supply electrical power to d
looFoO the onsite Class IE Distribution System.fffhe 72 hour M~ l i.aspietion Time takes into account tne capacity and capability of the remaining AC sources, reasonable time for repairs, and low probability of a DBA occurring during this f gINS3 81-@T 3a Periody
/
mie second lation Time'for Requi Action 8.4 establishe a init on the maximum me allowed for any
- combinati n of required AC power urces to be inoperable g@{ during y single contiguous oc rrence of failing to meet the LC . If Condition B is e ered while, for instance, a I
8 s11-3b -l offs e circuit is inoPerabi and that circuit is sub quently restored OPE E, the LC0 may already hav be not met for up to 72 ours. This situation coul ead
, t a total of 144 hours since initial failure of th LCO, t restore the DG. At his time, an offsite circu could again become inopera e, the DG restored OPERABL and an additional 72 hours for a total of 9 days) all d prior to complete restorat n of the LCO. The 5 day C letion Time provides a limit n the time allowed in a sp ified condition after discovery of failure to me the LC0. This limit is cons ered reasonable for situat ns in which Conditions and B are entered concurre ly. The 'AM" connector etween the 72 ho::r and 6 d Completion Times means th both Completion Times ap y simultaneously, and the nor restrictive must be met.
1 As i Required Action B.2, the ompletion Time allows fo an exc tion to the normal 'ti zero" for beginning the ai owed outage time " clock This exception results tablishing the ' time zero' at the time that the LC was nitially not met, inst fid of the time that Conditi n B was entered. C.1 and C.2 . Required Act n C.I addresses actions to be aken in the event of i perability of redundant requir d features us V (continued) BWR/4-ST B 3.8-10 -Rev-17-04/07/9F , 1 l ~,
&v7
AC Sources-Operating B 3.8.1 I i Insert B 3.8.1-3a Required Action A.5 imposes this 72_ hour' Completion time i from the discovery of the non availability CTG 11-1. However, if CTG 11-1 is available to supply Division I loads (determined by administrative' check of breaker, line 7 availability, and CTG 111 status) Required Action A.5 would be met-and Required Action A.6 would allow the restoration k l time of 7 days. l Insert B 3.8.1 3b The_7 day Completion Time to restore all EDGs to OPERABLE l status takes into account the capacity and capability of the i remaining AC Sources as well as the additional reliability l afforded by the availability of CTG 11-1. !
)
i l I 1 FERMI - UNIT 2 Page B 3.810 (Insert) REVISION 7 06/18/99l
AC Sources-Operating B 3.8.1 BASES SURVEILtANCE minimum and maximum frequencies of the DG are 58.8 Hz and REQUIREMENTS 61.2 Hz, respectively. These values are equal to i 2% of (continued) the 60 Hz nominal frequency and are derived from the recommendations found in Regulatory Guide 1.9 (Ref. 3). SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are connected to their preferred power source and that appropriate independence of offsite circuits is maintained. The 7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room. SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the standby electrical power supply to mitigate DBAs and transients and maintain the unit in a cafe chutdown condition. cth6nttalS h n% M) OfI Tominimizethe&wearenmovingpartssnatnonotget lubricated when the engine is not running, these SRs have - been modified by a Note (Note forSR3.8.1.2andNote@ for SR 3.8.1.7) to indicate that 11 DG starts for these tI Surveillances may be preceded by n engine prelube period
.and followed by a warm to loading. A WQ hWOJ For the purposes of $ " I$EM w __ estina. t e DGs are startedefronF stanuu w.diti:.;. ]5tandby conditions for a DG mean that b 3 I'I d 'the diesel engine coolant and oil are being continuously j circulated and temperature is being maintained consistent y with manufacturer recommendations. z G2.
In order to reduce stre,s; and wear Tn diesel engines, y manufacturerkreconsnend,thmodifiedstartinwhichthe No
' starting speed of DGs is imited, warmup is limited to this i ,, lower speed, and the DG are gradually accelerated to synchronous speed prior o loading. These start procedures S- .q g6 W] are,tfjeintentofNote which is onlygapplicable when4veh- ,1,,
pg 7........p............,m._ . , u,. ..nu a cw. . g
.(g 3.d r anowel to sahsjue sR3.t.ia W no (continued)
SuRJ4-STS-fcMing Sg 3g,,;3, 8 3.bl6 R=1,MlWlW Rgv 7
1 AC Sources 0perating ) B 3.8.1 l i Insert B 3.8.1-6 __
<<Not used>> lT 1
l Insert B 3.8.1-7 to hot conditions by using one of the following signals: l Manual. l Simulated loss-of offsite power by itself, ; Simulated loss of-offsite power in conjunction with an l ESF actuation test signal. or An ESF actuation test signal by itself. l l i f FERMI UNIT 2 Page B 3.8-16 (Insert) REVISION 7 06/18/99l 4
-A
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 (continued) REQUIREMENTS SR 3.8.1.7 requires that, at a 184 day Frequency, the DG gSgty FRoy starts from standhv conditions and achieves required voltage gg
/ anc frequency within Qseconds.4 The GBqLecond start PA06 6 3d-4 requirement suppo ts the assumpuuns in the design basis LOCA analysis o uF , Section &6.3A (Ref. 12). The O' start requiremen is not appitcable to SR 3.8.1.2 ' :: Met- ?
second Og'g 4-f 2 ;.61.2), above 2[;a modified i used. If : ::fif t:dstart tart quirement/of SR 3.8.1.7 ap ies sterts not p.;;:d:/n us , the[ 124econd descriedJ) 3
,A
/ lNSERit-h Since SR 3.8.1.7 does require a cond rt, it is more restrictive than SR 3.8.1.2, and t may be performed in lieu e/
of SR 3.8.1.2. 'H : ;;::: t h th: t;te..t .T e^vi. i vi 6 { 6 315.)-k ; !" ? l l ?. l Og,j The nomal 31 day Frequency for SR 3.8.1.2 (;;e T;ble 0.0.1-1, i cl WM:: " ..eraivr 7.e Oc;..Joi.-) is consistent with T Regulatory Guide 1.g (Ref. 3). The 184 day Frequency for O SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7). These Frequencies provide J l adequate assurance of DG OPERABILITY, while minimizing ' degradation resulting from testing. l SR 3.8.1.3 1 f,I j . g] This Surveillance e rifie:J that the DGs are capable of 3 synchronizing and accepting greater than or equal to the g7 83S.bl/6 equivalent of the maximum expected accident loads # A minimem
'?
i' run time of 50 minutes is required to stabutze engine temperatures, while minimizing the time that the DG is Y connected to the offsite source. Although no power factor requirements are established by this SR, the DG is normally operated at a power factor between 20.8 laggingle and the machine,while f,1.0A1.0kisanoperationallimitation4to The f.p.8],value is the design rating of g i ensure circulating,{c,urrents are minimizedf Tl.. M d i;;d i;
).
'r: MM t: re:id r;;th; s...i.;dui,.T Oe M. Routine overloading may nsult in more frequent teardown inspections k<
in accordance with vendor recommendations in order to maintain DG OPERABILITY. (continued) BWR/4-STS- B 3.8-17 -Rev-1 704/07/95 Rev7
l i AC Sources-Operating B 3.8.1 1 Insert B 3.8.1-4a In addition to the SR requirements, the time for the EDG to O reach steady state operation, unless the modified EDG start d i method is employed, is periodically monitored and the trend 6 evaluated to identify degradation of governor and voltage j regulator performance. l I 3 1 Insert B 3.8.1-4b l4 I without the risk of overloading the EDG. The EDG is tested l f at approximately 90% of its continuous load rating, which provides margin to excessivo EDG loading, while demonstrating f the EDG capability to carry loads near the maximum expected accident loads. 1 ~ FERMI UNIT 2 Page B 3.8 17 (Insert) REVISION 7 06/18/99l
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS SR 3.8.1.3 (continued) y The normal 31 day Frequency for this Surveillance (::: - I i c h 0.0.1-1) is consistent with Regulatory Guide 1.9 5 (Ref. 3). M Note I modifies this Surveillance to indicate that diesel engine runs for this Surveillance may include gradual loading, as recesmended by the manufacturer, so that mechanical stress and wear o esel engine are minimized.
.s.
Note 2 mod s Surveillance by ng that momentary transients cause of changing bus lo not invalidate Op,q o d $!ML M this test. Similarly, momentary powe ctor transients-abows. permal yy 'th: Mrit do not invalidate the test. Note 3 indicates that this Surveillance should be conducted on only one DG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations. I Note 4 s pulates a prerequ Ite requirement for performan f.3 of thi SR. A successful
<credi satisfactory per ruance s start must precede t p test to SR 3.8.1.4 This SR provides verification that the level of fuel oil in the day tank-[W ea$t :::t:d 0;;M is at or above the level at which fuel oil is automaticaily added. The level is expressed as an equivalent volume in gallons, and is selected to ensure adequate fuel oil "or a minimum of I hour of DG Q9,1 operation at full load { ; ".l The 31 day Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period.
SR 3.8.1.5 Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in 1 (continued)
"'"f t "S
. B 3.5-18 Rev 1, 04/07/95 Ret 7
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE SR 3.B.III.(continued) ~ REQUIREMENTS
- b. fomance of the R will not cause pe urbations to the electrical distribution syst hat could res t n a challenge steady state oper on or to plan safety systems and c Perfomance f the SR, or failu of the SR, wi not cause, or sult in, an A00 wi attendant ch enge to plant taf y cytt .
SR 3.s.1. Regulatory Guide 3.108 (Ref 9), paragraph 2.a.(3), requires demonstrationonceperp8monthsjtthattheDGscanstartand run continuously at ful load capability for an interval of f.\ not less than 24 hours-22 hours of which is at a load equivalent to the continuous rating of the DG, and 2 hours of ~. 22hwere At which is at a load equivalent to 1105 of the continuous dutyprinj-@ l rating of the DG./Prant smmhas taken an exception to thi qpedatdt hD'/o reouirement and perfoms thed2 hour run at th 2000 Sn mei% l of40 Umhnuous rating (yee sw). ine IK, starts for this Surveillance can be N i performed ither from standby or hot conditions. The Mnw ; ftthg(290 kW-bNgi provision for prelube and warmup, discussed in SR 3.8.1.2, j i gIpQ g Dnd fo dual loading, discussed in SR 3.8.1.3, are applica e to this SR. , hno er to ensure th the DG is tested nder load con hKW -2foD t are as close t esign conditions s possible, t ing on m st be performed ing a power fact s [0.9 . Th power ( ' factor is chose o be representat eofthea]ctu d 7
,3 W sis inducti loadina that the could exoeri e A load 7
bana is provi'ded to avoid routine overloading of the DG. Routine overloading may result in more frequent teardown (9
/M 5EET inspections in accordance with vendor reconnendations in order i g to maintain DG OPERABILITY.
The tf18 monthpFrequency is consistent with the reconnendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(3); takes into consideration plant conditions required to perfom the Surveillance; and is intended to be consistent with expected fuel cycle lengths. (continued) D'"!/t ST: 8 3.8-27 Rev 4 -04/07/95 Rev 7
AC Sources-0perating B 3.8.1 Insert B 3.8.1-9 . Although no power factor requiresents are established by this SR.
- the EDG is normally operated at a power factor between 0.8 lagging C i and 1.0. The 0.8 value is the design rating of the machine, while a the 1.0 is an operational limitation to ensure circulating currents are minimized.
[ l FERMI UNIT 2 Page. B 3.8 27 (Insert) REVISION 7 06/18/99l
AC Sources-Operating B 3.B.1 BASES SURVEILLANCE SR 3.8.1. continued) REQUIREMENTS 0-This Surveillance has been modified by $ Note'K. Note'k states that momentary transients due to chanoino bus loads do not invalidate this test. /Simpiarly, somentpy power
' factor The
/ason transients for No mave 2 is the thatlimit / do d ing not invalidate operatio the te with the rea or critical performance this Surveil ance could ause
[,3 pe urbations t the electric distribution systems t at would cha' enge continu steady state operation nd, as result, pla ; safety syst s. Credit be taken or unplanned av ts that satis y this SR. j - SR 3.8.1. Of.'$ This Surveillance demonstrates that he diesel engine can restart from a hot condition, such as subsequent to shutdown O' from normal Surveillances, and achieve GM SfatLVol$ and frequency within 11 R secondsr TheWMeauired voltaae second time is Qo
#g g derivec from the requirements of the acc'idert analysis to respond to a design basis large break LOCA. The 8 month)o Frequency is consistent with the recommendations @of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(5).
This SR is modified by two Notes. Note 1 ensures that the ! test is performed with the diesel sufficiently hot. The { requirement that the diesel has operated for at least 2 hours Og new full load conditions prior to performance of this urveillance is based on manufacturer recommendations for '>- achieving hot conditions. Sne so.u v.uv ,, ,,. .. : d;d t; e . . d - I
,vuuns v1 riveuing vi ... % . Routine overloads may result ~
in more frequent teardown inspections in accordance with 'k vendor reconnendations in order to maintain DG OPERABILITY. Momentary transients due to changing bus loads do not invalidate this test. Note 2 allows all DG starts to be preceded by an engine prelube period to minimize wear and tear l on the diesel during testing. SR 3.8.1. As required by Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(6), this Surveillance ensures that the manual p,9 synchronization ind u t===t w 1oad transfer from the DG to the offsite source can be made and that the DG can be returned (continued) SWR /4-STS- B 3.8-28 ":V 1, 04/07/05 Rav7
AC Sources-Oporating B 3.8.1 BASES REFERENCES (continued) 12hSAR,Sectiong6.3g
- 13. ASME Boiler and Pressure Vessel Code, Section XI.
- 14. IEEE Standard 308.
N
.r SWR /4 STS. B 3.8-34 Rev 1, 04/07/95-Rev 7
I JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ) ITS: SECTION 3.8.1 AC SOURCES 0PERATING J e I
- e. Not used. lh I
- f. ISTS SR Notes limiting Modes that an SR can be performed in..
-are not adopted, consistent with CTS requirements. CTS detail '
prescribing Mode limitations has been relocated via Amendment 95 consistent with Generic Letter 91 04.
- g. ISTS SR details incorporating EDG power factor limitations is not adopted - consistent with CTS level of detail. Any applicable power factor limitations on EDG testing will continue to be addressed outside of Technical Specifications.
- h. During the restoration from a loss of-offsite power (ITS SR 3.8.1.15) Fermi 2 (per CTS) returns the EDG to a " standby" status. This criteria imposes an additional confirmation J beyond the ISTS requirement to only return the EDG to a " ready-to load" status.
- 1. The change to ITS SR 3.8.1.8 is based on the fact that Fermi 2 electrical design is such that each ESF division is not allowed bo to be transferred to the opposite division offsite source l during plant operation. An offsite power source is cross tied to the opposite _ division only in maintenance situations. JFD d l l
P.1 will be modified to reflect this justification.
- j. The change to ITS SR 3.8.1.12 is based on the fact that the bypass of Fermi 2 EDG automatic trips on ECCS initiation signals does not require a concurrent bus loss of voltage k
i signal. P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses. P.3 Bases changes are made to reflect changes made to the Specification. Refer to the Specification, and associated JFD if applicable, for additional detail. Some are specifically addressed: a. A ITS SR 3.8.1.13 (based on CTS) does not impose an explicit power T factor limitation. Therefore the Bases are modified to discuss the " normal" power factor operation. consistent with that provided in the Bases of ITS SR 3.8.1.3. P.4 Editorial Bases change made for clarity, due to Fermi specific design and terminology, or consistency. FERMI UNIT 2 2 REVISION 7 06/18/99l
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.1 AC SOURCES 0PERATING N P.5 NUREG 1433, SR 3.8.1.2 Note 3 second sentence, is not adopted. _L The second sentence of the Note is a restriction not required by d CTS.- P.6 SR 3.8.1.2 does not accurately reflect the allowance for warmup l
' prior to loading" as its Bases do, and as SR 3.8.1.7 does, y Therefore, ITS SR 3.8.1.2 Note 2 is corrected to include this -
intended clarification of EDG allowed operation. k P.7 NUREG 1433 LCO Item c, and Condition F, explicitly address requirements and Actions for automatic load sequencers: but include a Reviewer's. Note indicating the acceptability of deleting the explicit treatment if the sequencer affects only affects the associated EDG. The Fermi 2 design for the load .sequencers is such that they do not affect offsite circuit loading, and only l affect EDG loading. Therefore. the option is implemented to implicitly include the sequencer Operability with the requirement for the Operability of the EDG and delete the explicit treatment. This is also consistent with the CTS treatment. P.8 : ' Additional detail added to the Bases to-reflect information relocated
'from CTS. Refer to. CTS Discussion Of Changes to the related requirement'.for a detailed justification of changes made to the current licensing basis, which are reflected in the ITS as presented.
P.9 - The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification
" split" criteria found in 10 CFR 50.36(c)(2)(ii).
GENERIC CHANGES 3 n C.1 TSTF 163. Rev 2: NRC' approved change to NUREG 1433. FERMI'- UNIT 2 3- REVISION 7 06/18/99l
SPET.-1 Ft CArtaN f,?.2 fAGf kEYHWED ,
/Al d'67' 7 l
l l l PAGE / _0F 02 Tgv7
DISCUSSION OF CHANGES ITS: SECTION 3.8.2 AC SOURCES-SHUTDOWN M.2 CTS 3.8.1.2 Action a for inoperable AC sources, requires immediate corrective actions to restore the inoperable AC sources, but only "whea in H00E 5 with the water level less than 20 feet. 6 inches above the reactor vessel flange." ITS 3.8.2 requires the immediate corrective actions to restore the inoperable AC. sources regardless of plant conditions. This eliminates flexibility and is therefore a more restrictive change. TECHNICAL CHANGES - LESS RESTRICTIVE
" Generic" LA.1 CTS LC0 3.8.1.2.b provides details defining the design features of _
the EDGs (i.e.. "each diesel generator with: " . and "A fuel l transfer pump"). The details relating to system design function. f 4 and Operability are not necessary in the ITS. These details are relocated to the Bases, which maintains consistency with NUREG- Q 1433. The definition of Operability, the Bases outline of Operability details (which requires change control in accordance with ITS 5.5.10. Bases Control Program), and the surveillance requirement for the fuel oil transfer pump (ITS SR 3.8.1.6), provides sufficient control of these details. These details are not required to be in the ITS. and ITS LCO. to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. This approach provides an effective level of regulatory control and provides for a more appropriate change control process. The level of safety of facility operation is unaffected by the change because there is no change in the requirement to maintain the equipment Operable. Furthermore. NRC and Detroit Edison resources associated with processing license amendments to these requirements will be reduced. This change is a less restrictive ! administrative change with no impact on safety. FERMI - UNIT 2 3 REVISION 7 06/18/99l
r DISCUSSION OF CHANGES ITS: SECTION 3.8.2 - AC SOURCES-SHUTDOWN
-LA.2 CTS 3.8.1.2 Action a for the inoperability of a required AC source. requires suspension of " crane operations over the spent fuel pool ." These " crane operation" issues are relocated from the CTS (as in the case of. CTS 3.9.7. " Crane Travel-Spent Fuel Storage Pool"), based on the administrative controls of heavy -
loads (which are in accordance with Fermi 2 positions on NUREG- J. 0612 and Generic Letter 80 113). Therefore, the Actions associated with crane operation following a loss of power sources have been relocated to the UFSAR. consistent with other heavy-loads issues. . Relocation to UFSAR maintains consistency with
-NUREG 1433. Changes to the UFSAR will be controlled by the provisions of 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the requirement for power source Operability and restoration remains in the Technical Specifications.
LA.3 CTS 3.7.1.4 includes details relating to system design, function. and Operability for the EDG Cooling Water System. ITS 3.8.1 T~ includes only a requirement for EDG Operability and relocates the 9 details of subsystem design and specific Operability requirements O to the UFSAR. This is acceptable because these details do not < impact the' requirement to maintain the EDG Operable and the ITS definition for Operability ensures that all equipment required to maintain Operability is functioning. These details can be adequately defined and controlled in the UFSAR which require change control in accordance with 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety acceptable because these details do not impact the requirement to maintain the EDG Operable. i i LA.4 CTS 4.7.1.4 details a requirement for the EDG cooling water pump to automatically start upon receipt of a start signal for the associated EDG. ITS SR 3.8.2.1 requires EDG automatic starts i (i.e., SP 3 8.1.10 and SR 3.8.1.11) for proper operation of an l Operabli ED The detail of verification of proper EDG starting. ! such thet i1 includes verification of EDG cooling water pump start. is relocated to the Bases for SR 3.8.1.10 and SR 3.8.1.11. This detail can be adequately defined and controlled in the Bases, which require change control in accordance with Chapter 5 of the ITS.. This detail is not required to be in the ITS to provide adequate protection of the public health and safety since the detail in the ITS is adequate for assuring proper performance of j the EDGs. FERMI UNIT 2 4 REVISION 7 06/18/99l
r I DISCUSSION OF CHANGES l ITS: SECTION 3.8.2 AC SOURCES SHUTDOWN LR.1 CTS 4.7.1.4 requires explicit verification of the proper positioning of the valves in the EDG cooling water flow path every 31 days. ITS does not retain this explicit verification: however. l ITS SR 3.8.1.2 and SR 3.8.1.3 does require EDG start and run (for a minimum of 60 minutes). Since the EDG cooling water system provides the required cooling for all EDG operation, the proper lineup is implicitly assured every 31 days by satisfactory operation of the required EDG load run. Regulatory control of changes to these requirements (e.g.. Technical Specification amendment or 10 CFR 50.59) is not necessary to provide adequate protection of the public health and safety since these details do l not impact the requirement to maintain the EDG in an Operable i status. l TECHNICAL CHANGES LESS RESTRICTIVE "Speci fi c" L.1 CTS SR 4.8.1.2. Surveillance Requirements for EDG and offsite sources while shutdown, includes the requirement to perform the ! CTS equivalent of ITS SR 3.8.1.18 (simultaneous EDG start test). i ITS SR 3.8.2.1 does not require this test to be applicable for determining Operability when shutdown. The change is acceptable because simultaneous start of all four EDGs is not needed because only 2 EDG are required to be Operable. Therefore. this exception has minimal impact on safety. Furthermore. ITS SR 3.8.2.1, Note. provides several exceptions to required demonstrations (although still retaining the applicability of the specific functional capability to be Operable) that are not provided in CTS SR 4.8.1.2. The reason for the Note is to preclude requiring the Operable EDG from being i paralleled with the offsite power network or otherwise rendered l inoperable during the performance of SRs. and to preclude de energizing a required 4160 V ESF bus or disconnecting a required offsite circuit during performance of SRs. With limited AC sources available, a sinole event could compromise both the required circuit and the EDGs. The Fermi 2 EDG design is such that on any EDG surveillance test start the EDG is rendered - inoperable. Therefore, the exception list includes all ITS SRs involving an EDG start (i.e.. ITS SRs 3.8.1.2. 3.8.1.7. and - 3.8.1.11 are included, in addition to those proposed in the l ._ NUREG). This change is consistent with NUREG-1433. k FERMI UNIT 2 5 REVISION 7 06/18/99l l L
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l
@l Diesel Fuel Oil and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS @l3.8.3 Diesel Fuel Oil and Starting Air 3.8.3 The stored diesel fuel oil and starting air subsystem shall - @ l LC0 be within limits for each required emergency diesel i generator (EDG).
i APPLICABILITY: When associated EDG is required to be OPERABLE. ' ACTIONS-
..................................... NOTE---- - -- - - -- - - -- -- - -
Separate Condition entry is allowed for each EDG. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore fuel oil 48 hours EDGs with fuel oil level to within level < 35.280 gal and limits. i
> 30.240 gal.in l storage tank. i- @i B. One or more required B.1 Restore fuel oil 7 days EDGs with stored fuel -total particulates to oil total particulates within limit.
not within limit. 4
#l C. One or more required C.1 Restore stored fuel 30 days EDGs with new fuel oil oil properties to properties not within within limits.
limits. (continued) u-l FERMI - UNIT 2 3.8 13 Revision 7 06/18/99
ngl Diesel Fuel Oil and Starting Air W 3.8.3
-ACTIONS (continued)
C0lOITION REQUIRED ACTION COMPLETION TIME l l gj~D. Required Action and D.1 Declare associated Immediately 1 associated Completion -EDG inoperable. 1 Time not met. l .QB y L One or more required EDGs with diesel fuel Mj -011. or starting air
. v.;/ subsystem not within
! limits for reasons other than I .hj Condition A, B, or C. SU'RVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY I i SR' 3.8.3.1 Verify each required EDG fuel oil storage 31 days tank contains = 35,280 gal of fuel. l SR 3.8.3.2 Ver4fy each required EDG fuel oil In accordance properties of new and stored fuel oil are with the tested in accordance with, and maintained ' Emergency within the limits of, the Emergency Diesel Diesel Generator Fuel Oil Testing Program. Generator Fuel ! 011 Testing i l Program 1 l (continued) 1~ 1 J
,l FERMI UNIT 2- 3.8 14 Revision 7 06/18/99 l
L
. 1
.hl' Diesel Fuel Oil and Starting Air 3.8.3 '
SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY kj SR 3.8.3.3 - Verify each required EDG air start receiver 31 days pressure is a 215 psig. hj SR 3.8.3.4 Check for and remove accumulated water from each required EDG fuel oil storage tank. 31 days l l l l I i l i l i I l FERMI UNIT 2 3.8 15 Revision 7 06/18/99 i
l Diesel Fuel Oil and Starting Air B 3.8.3 4 8 3.8 ELECTRICAL POWER SYSTEMS l B 3.8.3 Diesel Fuel 011 and Starting Air BASES
' BACKGROUND Each emergency diesel generator (EDG) is provided with a storage tank having a fuel oil capacity sufficient to operate that EDG for a period of 7 days while the EDG is supplying maximum continuous load discussed in UFSAR, Section 9.5.4 (Ref. 1). This onsite fuel oil ca)acity is l sufficient to operate the EDGs for longer than t1e time to replenish the onsite supply from outside sources.
1 Fuel oil is transferred from storage tank to day tank by either of two transfer pumps associated with each storage tank. Redundancy of pumps and piping precludes the failure I of one pump, or the rupture of any pipe valve, or tank to result in the loss of more than one EDG. For proper operation of the standby EDGs, it is necessary to ensure the proper quality of the fuel oil. Regulatory Guide 1.137 (Ref. 2) addresses the recommended fuel oil i practices as supplemented by ANSI N195 (Ref. 3). The fuel oil properties governed by these SRs are the water and sediment content, the kinematic viscosity, specific gravity (or API gravity), and impurity level. Each EDG has an air start system with adequate capacity for five successive start attempts on the EDG without recharging the air start receiver (s). APPLICABLE The initial conditions of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses in UFSAR. Chapter 6 (Ref. 4), and Chapter 15 (Ref. 5), assume Engineered Safety Feature (ESF) systems are OPERABLE. The EDGs are designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ESF systems so that fuel Reactor Coolant System, and containment design limits are not exceeded. These limits are discussed in more detail in the Bases for Section 3.2, Power Distribution Limits: Section 3.4, Reactor Coolant System (RCS): and Section 3.6 Containment Systems. jFERMI-UNIT 2 B 3.8.3 - 1 Revision 7 06/18/99
/p Diesel Fuel Oil and Starting Air B 3.8.3 BASES
' APPLICABLE SAFETY ANALYSES (continued) hl .
Since diesel fuel oil and starting air subsystem support the operation of the standby AC power sources, they satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). LC0 Stored diesel fuel oil is required to have sufficient supply for 7 days of full load operation. It is also required to gl meet specific standards for quality. This requirement, in con,iunction with an ability to obtain replacement supplies within 7 days, supports the availability of EDGs required to shut down the reactor and to maintain it in a safe condition for an anticipated operational occurrence (A00) or a postulated DBA with loss of offsite power. EDG day tank fuel oil requirements, as well as transfer capability from the storage tank to the day tank, are addressed in LC0 3.8.1. "AC Sources-0perating." and LC0 3.8.2. "AC Sources -Shutdown. " The starting air system is required to have a minimum capacity for five successive EDG start attempts without recharging the air start receivers. APPLICABILITY The AC sources (LC0 3.8.1 and LC0 3.8.2) are required to ensure the availability of the required power to shut down the reactor and maintain it in a safe shutdown condition I after an A00 or a postulated DBA. Because stored diesel ' fuel oil and starting air subsystem support LC0 3.8.1 and LC0 3.8.2. stored diesel fuel oil and starting air are required to be within limits when the associated EDG is required to be OPERABLE. ACTIONS The ACTIONS Table is modified by a Note indicating that separate Condition entry is allowed for each EDG. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable EDG subsystem. Complying with the Required Actions for one inoperable EDG subsystem may allow for continued operation, and subsequent inoperable EDG subsystem (s) governed by j separate Condition entry and application of associated < Required Actions. 1 l FERMI - UNIT 2 B 3.8.3 - 2 Revision 7, 06/18/99 I i
jl Diesel Fuel Oil and Starting Air B 3.8.3 BASES ACTIONS (continued) L1 In this Condition. the 7 day fuel oil supply for a required EDG is not available. However, the Condition is restricted to fuel oil level reductions that maintain at least a 6 day supply. These. circumstances may be caused by events such as:
- a. Full load operation required for an inadverte.nt start while at minimum required level: or
- b. Feed and bleed operations that may be necessitated by increasing particulate levels or any number of other oil quality degradations.
This restriction allows sufficient time for obtaining the requisite replacement volume and performing the analyses required prior to addition of the fuel oil to the tank. A period of 48 hours.is considered sufficient to complete restoration of the required level prior to declaring the EDG inoperable. This period is acceptable based on the remaining capacity (> 6 days), the fact that procedures will be initiated to obtain replenishment, and the low probability of an event during this brief period.
@ u This Condition is entered as a result of a failure to meet the acceptance criterion for particulates in one or more required EDG storage tanks. Normally, trending of particulate levels allows sufficient time to correct high particulate levels prior to reaching the limit of acceptability. Poor sample procedures (bottom sampling),
contaminated sampling equipment, and errors in laboratory analysis can produce failures that do not follow a trend. Since the presence of particulates does not mean failure of the fuel oil to burn properly in the diesel engine, since particulate concentration is unlikely to change significantly between Surveillance Frequency intervals, and since proper engine performance has been recently demonstrated (within 31 days).-it is prudent to allow a brief period prior to declaring the associated EDG inoperable. The 7' day Completion Time allows for further evaluation. resampling, and re analysis of the EDG fuel oil. l ; FERMI f UNIT 2? B 3.8.3 3 Revision 7 06/18/99
J
@ Diesel Fuel Oil and Starting Air B 3.8.3 BASES ACTIONS (continued) @l u
With the new fuel oil pro)erties defined in the Bases for
@l SR 3.8.3.2 for new fuel t1at has already been added to a required EDG storage tank not within the required limits, a period of 30 days from the time of obtaining new fuel oil sample results is allowed for restoring the stored fuel oil properties. This period provides sufficient time to test the stored fuel oil to determine that the new fuel oil, when mixed with previously stored fuel oil, remains acceptable, or to restore the stored fuel oil properties. This restoration may involve feed and bleed procedures, filtering, or combination of these procedures. Even if a EDG start and load was required during this time interval and the fuel oil 3roperties were outside limits, there is high likelihood tlat the EDG would still be capable of performing its intended function.
I u With a Required Action and associated Completion Time not (Aj met, or the stored diesel fuel oil or starting air subsystem not within limits for reasons other than addressed by "l Conditions A through C, the associated EDG may be incapable of performing its intended function and must be immediately declared inoperable. SURVEILLANCE SR 3.8.3.1 REQUIREMEtHS This SR provides verification that there is an adequate inventory of fuel oil in the storage tanks of each required EDG to support each EDG's operation for 7 days at full load. The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. The 31 day Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and unit operators would be aware of any large uses of fuel oil during this period. u l FERMI UNIT 2 B 3.8.3 -4 Revision 7 06/18/99
I i Ogj Diesel Fuel Oil and Starting Air B 3.8.3 l EASES SURVEILLANCE REQUIREMENTS (continued) gl SR 3.8.3.2 The tests of fuel oil prior to addition to the storage tank nc? a means of determining whether new fuel oil is of the appropriate grade and has not been contaminated with substances that would have an immediate detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the fuel oil may be added to the storage tanks without concern for contaminating the l entire volume of fuel oil in the storage tanks. These tests are to be conducted prior to adding the new fuel to the storage tank (s), but in no case is the time between sampling (and associated results) of new fuel and addition of new fuel oil to the storage tank to exceed 31 days. The tests, limits, and applicable ASTM Standards for the new fuel oil tests listed in the Emergency Diesel Generator Fuel Oil Testing Program of Specification 5.5 are as follows:
- a. Sample the new fuel oil in accordance with ASTM D4057-88 (Ref. 6):
h b. Verify that the sample has an API Gravity of within 0.3 degrees at 60*F or a specific gravity of within 0.0016 at 60/60'F. when compared to the suppliers certificate, , or an absolute specific gravity at 60/60*F of a 0.83 and s 0.89 or an API gravity at 60*F of a 27" and s 39 . Also, verify in accordance with the tests t specified in ASTM D975 91 (Ref. 6) a kinematic viscosity at 40*C of a 1.9 centistokes and s 4.1 centistokes, and a flash point of a 125*F: and
- c. Verify that the new fuel oil has a clear and bright appearance with proper color when tested in accordance with ASTM D4176 86 (Ref. 6).
Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the LC0 since the fuel oil is not added to the storage tanks. ' Following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in Table 1 of ASTM 0975 91 (Ref. 6) are met for new fuel oil when tested in accordance with ASTM D975 91 (Ref. 6), except that the analysis for sulfur may be performed in accordance < with ASTM D1552-90 (Ref. 6) or ASTM D2622 87 (Ref. 6), s. l FERMI-UNIT 2 83.8.3-5 Revision 7. 06/18/99 i
hl Diesel Fuel Oil and Starting Air B 3.8.3 BASES SURVEILLANCE REQUIREMENTS (continued) These additional analyses are required by Specification 5.5.9. " Emergency Diesel Generator Fuel Oil Testing Program." to be 3erformed within 31 days following sampling and addition. T11s 31 days is intended to assure: 1) that the sample taken is not more than 31 days old at the time of adding the fuel oil to the storage tank, and 2) that the results of a new fuel oil sample (sample obtained arior to addition but not more than 31 days prior to) are o)tained within 31 days after addition. The 31 day period is acce) table because the fuel oil properties of interest. even if t1ey were not within stated limits, would not have an immediate effect on EDG operation. This Surveillance ensures the availability of high quality fuel oil for the required EDGs. Fuel oil degradation during long term storage shows up as an increase in particulate, mostly due to oxidation. The presence of particulate does not mean that the fuel oil will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment, however, which can cause engine failure. Particulate concentrations should be determined in accordance with ASTN D2276 88 (Ref. 6). Method A. This method involves a gravimetric determination of total particulate concentration in the fuel oil and has a limit of 10 mg/1. It is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing. The Frequency of this test takes into consideration fuel oil j degradation trends that indicate that particulate concentration is unlikely to change significantly between Frequency intervals. l SR 3.8.3.3 This Surveillance ensures that, without the aid of the refill compressor, sufficient air start capacity for each EDG is available. The system design requirements provide for a minimum of five engine start cycles without recharging. The pressure specified in this SR is intended to reflect the lowest value at which the five starts can be accomplished. The 31 day F.ecuency takes into account the capacity, capability, recundancy, and diversity of the AC sources and l FERMI . UNIT 2 B 3.8.3 - 6 Revision 7 06/18/99
1
'hi Diesel Fuel Oil and Starting Air B 3.8.3 BASES SURVEILLANCE REQUIREMENTS (continued) other indications available in the control room, including alarms, to alert the operator to below normal air start pressure, SR 3.8.3.4 hl Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive. Removal of water from the required EDG fuel storage tanks once every 31 days eliminates the necessary environment for bacterial survival.
This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during EDG operation. Water may come from any of several sources, including condensation, ground water. rain water, contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily represent failure of this SR. provided the accumulated water is removed during performance of the Surveillance. i REFERENCES 1. UFSAR, Section 9.5.4. ;
- 2. Regulatory Guide 1.137.
- 3. ANSI N195. 1976.
- 4. UFSAR Chapter 6.
- 5. UFSAR Chapter 15.
- 6. ASTM Standards: D4057 88: D975 91: D4176 86: D1552 90:
D2622 87: and D2276 88. l l w j l FERMI UNIT 2 B 3.8.3 - 7 Revision 7. 06/18/99
l 3/4.8 ELECTRICAL POWER SYSTEMS S PE4FicknorJ S.9 3 l 3/4.8.1 A.C. SOURCES [b505c4SgdhtnNoy) 8.8. / ) l l A.C. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: a Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, y and M3' * ! bg Two separate and independent onsite A.C. electrical power sources, Division I and Division II, each consisting of two emergency ' diesel generators, each diesel generator with:
- 1. A separate day fuel tank containing a minimum of 210 gallons L of fuel, gR 3.g ~3,1 2. A separate fuel stora e system containing a minimum of 35,280 gallons of fue , and {*l AM. LCO 3,3,3
- 3. A separate tuei transter pump Ag); cab l lip
,ffitCABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. St M S CTION:
With one or both offsite circuits of the above required A.C. electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTOOWN within the next 24 hours; demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1. within one hour and at least once per 8 hours thereafter and, g J. With one or both diesel generators in one of the above required g.g onsite A.C. electrical power divisions iaoperable; J.8.1 1. Demonstrate the OPERABILITY of the remaining A.C. sources by ' performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours thereafter, and if the diesel generator (s) became inoperable due to any cause other l than an inoperable support system, an independently testable l component, or preplanned preventive maintenance or testing, by performing Surveillance Requirement 4.8.1.1.2.a.4 for one diesel generator at a time within 24 hours, unless the absence of any potential common mode failure for the remaining diesel generators is deterrined, and , i FERMI UNIT 2 3/4 8-1 Amendment No. SJ,119 PAGE / OF 05 gev 7
l l f SPECAPICM70h.l 3 S'.3 ELECTRicAt POVCR SYSTEMS SURVEILLANCE REOUTREMENTS F4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability. 4.8.1.1.2 Each of the above required diesel generators shall be demonstrated OPERABLE: l Sti . a. At least once per 31 days hnMTAGGERJB' TEST SAffE]5y: Squi$icahn l 3.2 1 1. Verifying trie fuel Tever in the day fuei tank.. . . * * . , ySt :
- 2. Verifying the fuel level in the fuel storage tank.ll'*
"3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank. '
- 4. Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in less than or equal to 10 seconds.* The generator voltage and frequency shall be 4160 a 420 volts and 60 a 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started for this test by using one of the following signals:
gel
) a) Hanua1.
Qejf; cob. r. 5' b) Simulated less-of-offsite power by itself. c) Simulated loss-of-offsite power in conjunction with an 8 T-l ESF actuation test signal. d) An ESF actuation test signal by itself.
- 5. Verifying the diesel generator is synchronized, loaded to greater than or equal to an indicated 2500 2600 kW in accordance with the manufacturer's recommendations, and operates with this load for at least 60 minutes.
6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
- 7. Verifying the pressure in all diesel generator air start 6 4 3. 7, 3,.3 receivers to be greater than or equal to 215 psig. l Fall diesel generator starts for the purpose of this Surveillance Requirement g" ( may As arreceded by an engine prelube period. The diesel generatar start (10 sec) from ambient ' conditions shall be performed at least KStahn- once .per 184 days in these surveillance tests. All other engine star.ts for 3'g* g the purpose of this surveillance testing may be preceded by other warmup procedures reconrnended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.
h FERMI - UNIT 2 3/4 8-3
~
Amendment No. JJ,107 s PAGE c2 0F 05 g,g 7 i
9 ecd Pt c h'rtbrd 3. 7 3 j(so .% Spec &coHm 3.fr. I.) ELEETRICAL p0WER SYSTEMS ((bO b6 6 /6cibC4 b feb SURVEf tl ANCE pE0VIREMENTS (Continued) i
- b. By removing accumulated water:
seL From the day tank at least once per 31 days and after each pecificab J,3.l\/ 1. occasion when the diesel is operated for greater than I hour, and I 6/?. 3 2,,3,[ 2. From the storage tank at least once per 31 days. I D E 3 g,,, c. By sampling new fuel oil in accordance with ASTM 04057 88 prior to addition to the storage tanks and: l g*g , 1. By verifying in accordance with the tests specified in ASTM 0975-91 prior to addition to the storage tanks that the
- sample has:
4 sk 5Fificalia a) An API Gravity of within 0.3 degrees at 60'F or a specific gravity of within 0.0016 at 60/60'F, when f.F compared to the supplier's certificate or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity at 60'F of greater than or equal to 27 degrees but less than or equal to 39 degrees. b) A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by
, comparison with the supplier's certification.
c) , A flash point equal to or greater than 125'F, and d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176 86.
- 2. By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975 91 are met when tested in accordance with ASTM D975-91.
- d. At least once every 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276 88, and verifying that total particulate contamination is less than 10 mg/ liter when Wckgd in accordance with ASTM D2276 88, Method A.
(e. At least once per 18 months by: l N 1. Subjecting the diesel to an inspection in accordance with Qec.i(icahd . procedures prepared in conjunction with its manufacturer's reconrnendations for this class of standby service. FEP.MI - UNIT 2 3/484 Amenoment No. # , 95 i
~
PAGE_ 3 0F 05 Re 7 7 e e
' t.;
SPEGlF iCJtTlotJ 3.2.3 fAko Su Spalficalin 3.g.\) ELECTRicAt POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) e M f. At least once per 10 years or after any modifications whien could - affect diesel generator interdependence by starting all four I S pu.* scc,f im diesel generators simul'taneously, during shutdown, and verifying 3* g* g that all four diesel generators accelerate to at least 900 rpm in 1ess than or equal to 10 seconds. ; Ai 17.; .;.;. ;;r " - ;.r; ty: l 4./ Draining a fuel oil stora tank, removing e accumula sediment and c aning the tankf :. ; - adh _ S O(. 2. Performing a pressure test of those portions of the diesel Speciscafisw fuel oil system designed to Section 111. subsection ND of 3, g, g the ASME Code in accordance with ASME Code Section 11 Article IWD.5000. j (4.8.2.3.3 Reeerts - Not Used I l l j l 1 FERMI - UNIT 2 3/4 a.7 ,, Amendmnent No.107 L-PAGE OF 05 #ev 7 , 1
1 DISCUSSION OF CHANGES ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR lh ADMINISTRATIVE A.1 In the conversion of the Fermi 2 current Technical Specifications (CTS) to the proposed plant specific Improved Technical ! Specifications (ITS), certain wording preferences or conventions l are adopted which do not result in technical changes (either l actual or interpretational). Editorial changes, reformatting, and l revised numbering are adopted to make the ITS consistent with the I Boiling Water Reactor (BWR) Standard Technical Specifications ! NUREG 1433, Rev. 1. A.2 CTS 4.8.1.1.2.c details diesel fuel oil test requirements. These details are addressed in the ITS Administrative Controls Programs. Section 5.5, and required by ITS SR 3.8.3.2. This is an administrative presentation issue only. The details of the CTS lh j conversion to these ITS Program requirements are addressed in Section 5.0. j TECHNICAL CHANGES MORE RESTRICTIVE None TECHNICAL CHANGES LESS RESTRICTIVE
" Generic" l LA.1 CTS 4.8.1.1.2.g.1 requires a 10 year cleaning of the EDG fuel oil storage tank, which reflects a preventative maintenance type of SR. Failure to perform this SR, does not necessarily result in an inoperable EDG. Preventative maintenance SRs generally have been l relocated from the TS and allowed to be under licensee control, as they are not necessary for ensuring Operability. Relocating this surveillance maintains consistency with NUREG 1433. The required cleaning of the storage tanks is relocated to the Technical Requirements Manual-(TRM). This cleaning can be adequately defined and controlled in the TRM where revisions are controlled I by the provisions of 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the requirement for EDG Operability remains in the Technical Specifications.
FERHI - UNIT 2 1 REVISION 7 06/18/99l l
DISCUSSION OF CHANGES ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l[ TECHNICAL CHANGES LESS RESTRICTIVE "Speci fic" L.1 CTS LCOs 3.8.1.1 and 3.8.1.2 include requirements associated with diesel fuel oil storage. These requirements are moved to a new Specification ITS 3.8.3, Diesel Fuel Oil and Starting Air. The Applicability of this new LC0 is "when associated EDG is required l@ to be OPERABLE" which envelops the Applicabilities for the requirements moved into the new Specification. lh ITS LC0 3.8.3, Diesel Fuel Oil and Starting Air, includes the following new less restrictive allowances: Condition A (less than l@ 7 days but more than 6 days of EDG fuel available): Condition B l (fuel oil particulates not within limits): Condition C (new fuel oil properties not within limits): Condition D (Actions or g l Completion Time for other Required Actions not met). These new Conditions are less restrictive because they provide time to restore a Condition that, under the CTS equivalent requirements, would result in the EDG being immediately declared inoperable. This change is acceptable because each of these parameters, while supporting EDG Operability, contains substantial margin before reaching a condition that would prevent the EDG from performing its safety function. Therefore, the limited levels of degradation permitted by these new conditions justify some allowance for restoration. During the newly allowed restoration periods for these parameters, the EDG is still capable of performing its intended function. Specifically. Action A allows 48 hours to restore fuel oil level in the storage tanks prior to declaring the EDG inoperable provided fuel oil level is sufficient for 6 days of operation at the continuous rated load. Action B allows 7 days to restore fuel lg oil total particulates to within limits prior to declaring the EDG inoperable, because the most likely cause of high particulates is poor sampling and particulates for limited durations will not prevent EDG operation. Action C allows 30 days to restore other j new fuel oil properties to within limits because these tests are ( t intended to measure long term oil stability and are not indicative of conditions that would prevent EDG operation in the short run. Action D is provided to declare the EDG inoperable if previous Actions are not met. Therefore, these changes have no adverse N impact on safety.
; FERMI UNIT 2 2 REVISION 7 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.8.3 DIESEL FUEL 0IL AND STARTING AIR lh L.2 CTS SR 4.8.1.1.2 a requires the monthly verification of EDG fuel ; storage tank level be performed "on a STAGGERED TEST BASIS." The ) intent of this requirement for staggered testing was to maintain 4 jtonthesametestscheduleasthemonthlyEDGrun. Note that in I the DOCS for ITS 3.8.1. the staggered test basis for the EDG start y and load was deleted. Therefore, consistent with that change in i frequency, the EDG fuel oil level verification staggered testing Q requirements have been deleted. The system design continues to T provide fuel oil level alarms to alert the operator to any abnormal losses of fuel oil between EDG surveillance runs. RELOCATED SPECIFICATIONS None TECHNICAL SPECIFICATION BASES Bases for this Specification have been added that reflect the format and i applicable content of ITS 3.8.3 consistent with the BWR STS, NUREG 1433. I Rev. 1. l FERMI UNIT 2 3 REVISION 7 06/18/99l l
)
r Diesel Fuel Oil (_Ec: 0;QandStartingAir-3.8.3 lh 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel 011@stgrT[1) and Starting Air [ cts) LCO 3.8.3 The stored diesel fuel oil .ubr1rTT) ar.d starting air subsystem shall be within limits for each required diesel generator . f - [ APPLICABILITY: When associated'bG is required to be OPERABLE. l ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - -------
Separate Condition entry is allowed for each%G. i CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.I Restore fuel oil 48 hours fuel oil level level to within N)28 J : "^ limits.
> M, r galgaland in orage tank, eguidd E f
. One o moreDGswth( 8. Restore lube oil 4 ours lube o inventory inventor to within i i < 40Er al and limits.
>M 1. g
~
( One or mo're$6s with .I Restore fuel oil 7 days I l l stored fuel oil total 6 total particulates to particulates not within limit, within limit. V (continued) i BWR/4-STS. 3.8-21 R;v I, 04/07/95
./
Rev7
)
i DieselFuelOilf andStartingAir{h 3.8.3 ACTIONS (continued)
<as)
CONDITION REQUIRED ACTION COMPLETION TIME
. One or more 1 Restore stored fuel 30 days new fuel oil ( oli properties to properties not within within limits. L limits.
E. One or more,0Gs th E.1 Res re starting air 48 ours starting air eiver iver pressure to pressure < [ ] psig [225) psig. # and 2 [125) sig. Required Action and associated Completion D 1 Declare associated inoperable. Immediately g Time not met. V E One or more ,DGs with Uvguired E, diesel fuel oil, bda- . /h f.4 U
=rdi, or starting air subsystem not within limits for reasons other than n tion A, Cy)lfy 4 SWR /4-STS- 3.8-22 Rev 1, 04/07/95-Rev 7
Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REDUIREMENTS SURVEILLANCE FREQUENCY TlakVLJG$D Verifyeace_[fueloilstoragetankcontains SR 3.8.3.1 31 days (J. 7.l.l. b.2 ) 2 't ^^^' gal of fuel.
.t.p.2.a.1) 9e@ e.r. i.2.t.t>
SR .8.3.2 Ve ify lube oil inve ory is 2 f50GJ g . 31 days g SR 3.8.3 Verify
@ r*[ 6G3 4 3.l.i.1.c.34) 1 oil properties of new and In accordanc l stored fuel oil are tested in accordance with the Diesel
+ Fuel Oil h {
with,andmaintainedwithinthelimitso[f, the leseltluel Oil Testing Pro ram. Testing Program E mw w c yl -- ** ' 3.8.3. etaired C ) SR rify eac ir starr receiver pressure 31 days (Q,g.l.l.2,4.7) dib . "9 SR 3.8.3 Check for and remove accumulated water from 431Adays each4 fuel o_11 storage _ tank. f(quina E$G) f.g,f./,2,b,2.) SR 3.8.3.6 For ch fuel oil storage t k: years
- s. D in the fuel oil;
\cl b. Remo the sediment; and
- c. Clean t tank.
^
BWR/4-SYS- 3.8-23 Rev 1, 04/07/95 ./ Rd 7
)
Diesel Fuel 011 { Q and Starting Air B 3.8.3 p& B 3.8 ELECTRICAL POWER SYSTEMS g A/0T #4/kED *. B 3.8.3 Diesel Fuel 011Q,vbe-UTTiand Starting Air "OG ~* 06 g BASES (eemp _ BACKGROUND Each Mtesel erator (DG) is provided with a storage tank. having a fue oil capacity sufficient to operate that DG f -- I a_ period of 7 days while the DG is supplying maximum can6nuous ! OPa @u;; FSAR,e ::::rt ---id::t Section 19 (l.%",}-load-d-- 1 . u" -- - .d (Ref.u-) ' discussed
'- ' "- -in' '-
;;;e:tg .f ; n. ... ;;;;; ;; =; ;7;-
miletier This onsite fuel oil capacity is sufficient to operate the DGs for longer than the time to replenish the onsite supply from outside sources. . l Fuel oil is transferred from storage tank to day tank by either of two transfer pumps associated with each storage tank. Redundancy of pumps and piping precludes the failure of one pump, or the rupture of any pipe, valve, or tank to result in the loss of more than one DG. -All at:id: t=E:, h ;-+ ad pipir; r: M st=d e=de;-e: d. For proper operation of the standby DGs, it is necessary to ensure the proper quality of the fuel oil. Regulatory Guide 1.137 (Ref. 2) addresses the recomended fuel oil practices as supplemented by ANSI N195 (Ref. 3). The fuel oil properties governed by these SRs are the water and sediment content, the kinematic viscosity, specific gravity (orAPIgravity),andimpuritylevel. I The DG lubr ation system is designed to provide surf lubricati to permit proper opefation of its associate G 3 under al loading conditions, he system is required circul e the lube oil to th diesel engine working rfaces and t remove excess heat . ersted by friction dur g oper tion. Each engine-ci sump contains-an inve cry ca ble of supporting a nimum of !F} days of o ration. e onsite storage in dition to the engine o sump is ufficient to ensure 7 ays' continuous opera on.y This supply is sufficient o allow the operator t replenish lube i (11 from outside so es. j - Each DG has an air start system with adequate capacity for five successive start attempts on the DG without recharging the air start receiver (s). (continued) BWR/4-US B 3.8-41 -Rev 1, M/0W Rev 7
Diesel Fuel 011Cl.ube-t!TT~) and Starting Air jg> B 3.8.3 0' BASES (continued)
' -APPLICABLE The initial conditio of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses i , Chapter [6k (Ref. 4), and Chapter [15A(Ref.5 ssume Engine)ered Safety Feature (ESF) systems are OPERABLE. The DGs are designed to provide sufficient capacity, capability, redundancy and reliability to ensure the availability of necessary powe,r to ESF . systems so that fuel, Reactor Coolant System, and containment design limits are not exceeded. These limits are discussed in more detail in the Bases for Section 3.2, Power Distribution Limits; Section 3.4, Reactor Coolant System (RCS); and Section 3.6, Containment Systems..
Since diesel fuel oilf.3ebe m.1 and starting air subsystem support the operation of the standby AC power sources, they l@ p'7 satisfy Criterion 3 of '" ""I .";;;cy OutM S Q q CFR50. % % @ % D.J LC0 Stored diesel fuel oil is required to have sufficient supply for 7 days of full load operation. It is also required to meet specific standards for quality. .^f it M i!!;. ,
-suff4cient-1;h eil-supply-must-h :=9 tM- +a
-->-- tS ~
capab Fity +a aaan+= =* fem-load-foe 4-days. This requirement, in con. junction with an ability to obtain replacement supplies within 7 days, supports the availability of DGs required to shut down the reactor and to maintain it in a safe condition for an anticipated operational occurrence (A00) or a postulated DBA with loss of offsite power. DG day tank fuel oil requ'eements, as well as transfer capability from the storage tank to the day tank, are addressed in LCO 3.8.1, "AC Sources-Operating," and LCO 3.8.2, 'AC Sources-Shutdown." The starting air system is required to have a minimum capacity for five successive DG start attempts without recharging the air start receivers. APPLICABILITY The AC sources (LCD 3.8.1 and LCO 3.8.2) are required to ensure the availability of the required power to shut down the reactor and maintain it .in a safe shutdown condition after an A00 or a fuel cit .___ ... postulated DBA. air a and starting Because stored subsystem diesel support 8 \ LCO 3.8.T and LCD 3.8.2, stored diesel fuel oil,;4ebe-wit / I (continued)
-BWR/4-STS- 8 3.8-42 Rev-Ir-04/07/g5-Reu7 t
1 -
?.
Diesel Fuel 011 6 and Starting Air Vgp B 3.8.3 BASES APPLICABILITY and starting air are required to be within limits when the (continued) associated DG is required to be OPERABLE. ACTIONS The ACTIONS Table is modified by a Note indicating that separate Condition entry is allowed for each DG. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable DG subsystem. Complying with the Required Actions for one inoperable DG subsystem may allow for continued operation, and subsequent inoperable DG subsystem (s) governed by separate Condition entry and application of associated Required Actions. L1 (~tyi! In this Condition, the 7 day fuel oil supply for a tG is not available. However, the Condition is restricted to fuel oil level reductions that maintain at least a 6 day supply. These circumstances may be caused by events such as:
- a. Full load operation required for an inadvertent start while at minimum required level; or
- b. Feed and bleed operations that may be necessitated by increasing particulate levels or any number of other oil quality degradations.
This restriction allows sufficient time for obtaining the requisite replacement volume and performing the analyses required prior to addition of the fuel oil to the tank. A period of 48 hours is considered sufficient to complete i restoration of the required level prior to declaring the DG l inoperable. This period is acceptable based on the remaining capacity (> 6 days), the fact that procedures will be initiated to obtain replenishment, and the low ' probability of an event during this brief period, t
'g Yi lobe oil inventor < Soe gal, sufficient lu oil to l supp 7 days of contin s DG operation at full ad condit s may not be avail e. However, the Condi n is j F
(continued) BWR/4-ST& B 3.8-43 Ris I, 04/07/95 av 7
)
. . . , . . . . .s .. .:.... . .:
. Diesel Fu21011IM_and Starting Air l B 3.8.3 BASES ACTIONS P
' L 1 (continued) ^ 1 restricted to lu (11volumereductionsth intain at least a 6 day ly. This restriction ws sufficient time for obt ing the requisite repipement volume. A Period of hours is considered s ff'icient to complete -
restorat n of the required vol prior to declaring the 03 inoper le. This period is a eptable based on the
, rama ing capacity fa that procedures (>will6 day , the low rate of usag e r plenishment, and the 1 initiated to obtain probabili_ty of an event durin.
J is brief perio fd _ _ _ in ru. of vMvt (pd M
.5 k aqt M ES This Cor.dition is entered as a result of allure to meet the acceptance criterion for particulate Normally, trending of particulate levels allows sufficient time to correct hig particulate levels prior to reaching the limit of acceptab 11ty. Poor sample procedures contaminated sampling equipment, and errors (bottom sampling),
in laboratory analysis can produce failures that do not follow a trend. Since the presence of particulates does not mean failure 't 1 l the fuel oil to burn properly in the diesel engine, sirs ! particulate concentration is unlikely to change significantly between Surveillance Frequency intervals, and i i since proper engine perfonsknce has been recently ' demonstrated (within 31 days), it is prudent to allow a brief period prior to declaring the associated DG inoperable. The 7 day Completion Time allows for further evaluation resampling, and re-analysis of the DG fuel __ oil.
.fg g[sa) }& ltaS ahlady k.a+1 addCd h"
~ ' ~
Q fegwired EDG [u!A o*1 SWCofe &$ MMM With the new uel oil properties defined in the Bases for SR 3.8.3 ot within the required limits, a period of doW ni 9 M W fwd ~30 days 11 lowed for restoring the stored fuel oil p;l Sufk,(LWIb Properties. This period provides sufficient time'to test
. the stored fuel oil to detrmine that the new fuel oil, when mixed with previously storea fuel oil, remains acceptable, or to restore the stored fuel oil properties. This '
restoration may involve feed and bleed procedures, filtering, or combination of these procedures. Even if a DG start and load was required during this time interval and (continued) SWR /4.5TS. B 3.8-44 Rev-Ir04/07f95-2d7
DieselFuelOilf:Eube.4n)andStartingAir j B 3.8.3 1 BASES ACTIONS ,23 (continued) l the fuel oil properties were outside limits, there is high likelihood that the DG would still be capable of performing its intended function. [Withstartinga capacity for elver pressure < [225] psi ficient l e successive DG start att oes not exist. H er, as long as the receiv ressure is
> [1 sig, there is adequate ty for at least one s attempt, and the DG c considered OPERABLE while air receiver press s restored to the required 11 .
A period of 48 h f.3 restoration s considered sufficient to c e required pressure prior to e ring the DG ino e. This period is acceptable ed on the rye ing air start capacity, the fac at most DG starts l 1re accomplished on the first att , and the low probability of an event durin is brief period ; l l With a Required Action and associated Completion Time not met, or the stored diesel fuel oilf"W = mor starting air subsystem not within limits for reasons other than [@ addressed by Conditions A through , the associated DG may be incapable of performing its inten e function and must be imediately declared inoperable. G l$ SURVEILLANCE SR 3.B.3.1 REQUIREMENT 4 This SR provides verification that there is an adequate inventory of fuel oil in the storage tan to support each DG's operation for 7 days at full load. The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. The 31 day Frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are (continued) SWR /4-STS- B 3.8-45 Rev 1, 04/07/95-s
&v7
_- o
Diesel Fuel 011(~EtrbeJ and Starting Air T B 3.8.3 BASES
' SURVEILLANCE SR 3.8.3.1 (continued)
REQUIREMENTS provided and unit operators would be aware of any large uses of fuel oil during this period. SR 3.8.3.21
\
This Surveilla . ensures that sufficient lu icating oi
. inventory i vailable to support at least days of full load oper on for each DG. The requirement is based o the DG manufacturer's s con on[500)-
values for the i run t of the DG. Implicit in th SR is the requiremerit to rify the capability to trans r the lube oil from its p, s rage location to the DG, whe the DG lube oil sump does t hold adequate inventory f 7 days of full load (Q operation without the level aching the manufacturer's U recommended minimum level A 31 day Frequency is dequate to ensure that a ficient \ lobe oli supply is phsite, since DG starts and ntimearjr i
< closely monitored tiy the plant staff- -
6 I SR 3.B.3 o$ [w) Dil ffief-{0 addili-g & ,5/gy a ge. M/t l@ s
- The tests ii;t:d 5:h e are a means of determining whether new fuel oil is of the appropriate grade and has not been contaminated with substances that would have an immediate/
detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the fuel oil Mh d may be added to the storage tanks without concern for ! os,socW N contaminating the entire voltane of fuel oil in the storage i tanks. These tests are to be conducted prior to adding the l new fuel dgm jM , betweengothestoragetank(s),butinnocaseisthetime
..ceipbof new fuel ancb::-de: ting t% tests- to exceed 31 days. The tests, limits, and applicable ASTM hpfb6$ M Standardsfareasfollows: .fo .ga nco fue,\dOtsbskd a. Sample the new fuel oil in accordance with ASTP -
Rd b'ij D4057-pa)(Ref.6); 4 /A)SER7 Tdsb)hWom p( b. Verif *
@yjirigr}
accordance with (Ref. 6)fthat the the~testkecifica sample hasdan absonn inemarg
$pec}Mcdon 6.6 spectu e gravity at 60/60'F of 2 0.83 and s 0.89 or an API gravity at 60*F of 2 27' and 5 39'3fa kinematic
[. C Also,
- vcM[& ,J(continued) g-D ~
4WR/4-STS- B 3.8-46 -Rev-1,-04/07/95-
@7 j; j e ,
- '.V ,.
'i ,, G :
Diesel Fuel Oil and Starting Air l h B 3.8.3 INSERT B 3.8.3-1 an API Gravity of within 0.3 degrees at 60 F or a specific
. gravity of within 0.0016 at 60/60"F, when compared to the suppliers certificate, or... ..3 FERMI UNIT 2 Page B 3.8 46' (Insert) REVISION 7 06/18/99l
DieselFuel011[ nd Start n l( BASES SURVEILLANCE SR 3.8.3 ' (continued) REQUIREMENTS I viscosity at 40'C of h 1.9 centistokes and 5 4.1 centistokes, and a flash point of 2 125'F; and
- c. Verify that the new fuel oil has a clear and bright appearance with proper color when tested in accordance with ASTM D4176- g (Ref. 6).
Failure to meet any of the above limits is cause for i rejecting the new fuel oil, but does not represent a failure ' g to meet the LC0 4sstu b since the fuel oil is not added to the storage tanks. P.4 a - _;,.;g,;,, the fue I:o:3
'1 ; ,,[11owing is analyzed to establish the thatinitial new fuel oli sample, the other l
properties specified in Table 1 of ASTM D975 4W4 (Ref. 6) are met for new fuel oil when tested in accordance with ASTM j
. D975 4mic (Ref. 6), except that the analysis for sulfur may '
be performed in accordance with ASTM D15524901. (Ref. 6) or '%EflT $ 3,q,3 7, ASTM D2622-197} (Ref. 6)./ The day period is acceptable because tne rues ou propertie o nterest, even if they " ~ were not within stated limits, would not have an immediate effect on DG operation. This Surveillance ensures the availability of high quality fuel oil for the Fuel oil degradation during long term storage shows up as an increase in particulate, mostly due to oxidation. The presence of particulate does not mean that the fuel oil will not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel oil injection equipment, however, which can cause engine failure. Particulate concentrations should be determined in accordancewithASTMD2276-4n)(Ref.6),MethodA. This method involves a gravimetric detemination of total particulate concentration in the fuel oil and has a limit of 10 mg/1. It is acceptable to obtain a field sample for subsequent laboratory test,ing in lieu of, field, testing. M n'",".O+ _2: .- ". I"_ 3"L.2 "+' u m""2": '"'. '"I ' I"C
- ' ' i' ' 7 ' ~
The Frequency of this test takes into consideration fuel oil degradation trends that indicate that particulate (continued) BWR/4 !TS B 3.8-47 6 1, 01/07/95 (fev1 J
I l l Diesel Fuel Oil and Starting Air @ B 3.8.3 INSERT 8 3.8.3 2 These adNional analyses are required by Specification 5.5.9. " Emergency Diesel Generator Fuel Oil Testing Program." . to be performed within 31 days following sampling and I addition. This 31 days is intended to assure: 1) that the sample taken is not more than 31 days old at the time of adding the fuel' oil to the storage tank. and 2) that the 1 results of a new fuel oil sample (sample obtained prior to ) addition but not more than 31 days prior to) are obtained within 31 days after addition, i l FERMI- UNIT 2 Page B 3.8 47 (Insert) REVISION 7 06/18/99l
l Diesel Fuel Oilfp} and Starting Air l@/ B 3.8.3 \._ i BASES ( . l 2' l l SURVEILLANCE REQUIREMENTS SR 3.8.3 7 (continued) lh l concer.tration is unlikely to change significantly between Frequency intervals. SR 3.8.3. l @ This Surveillance ensures that, without the aid of the refill compressor, sufficient air start capacity for each DG is available. The system design requirements provide for a , m}n g- of p el end ne spart,cyg es w g oup,gecpar g g L.-- , j w[.. wh a muse w t suas h.h w u rw h h[ . w[ ,[,h a ved L.,Ai v .,,.... l---The pressure specified in this SR is intended to ref" eet the lowest value at which the (fivel starts can be accomplished. The,(31kdayFrequencytakesintoaccountthecapacity, capability, redundancy, and diversity of the AC sources and i other indications available in the control room, including alarus, to alert the operator to below normal air start pressure. SR 3.8.3 Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water Ifg g environment in order to survive. Removal of water from the fuel storage tanks once every ,L31kdays eliminates the necessary environment for bact'eYtal survival. This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during DG operation. Water may come from any of several sources, including condensation, ground water, rain water, contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity 'of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily represent failure of this SR, provided the accumulated water is removed during performance of the Survelliance. (continued) BWR/4-STS B 3.8-48 Jtey 1, 04/07/95 Ren
Diesel Fuel Oil and Start n BASES SURVEILLANCE SR 3.BI6 ' REQUIREMENTS ' (continued) Drai ng of the fuel oil store n.thusupplytanhs, removal of cumulated sediment, and nk cleaning are required at 1 year intervals by Regulat Guide 1.137 (Ref. 2), aragraph 2.f. This SR is ypically performed in conjunction with ASME Boi r-end Pressure Vessel Code, Section XI (Ref. 7), ex inations of the tanks. To prec1 e g,( the introduction of s actants in the fuel oil system, e cleaning should be a amplished using sodium hypochio e solutions or their uivalent, rather than soap or detergents. This R is for preventive maintenane The presence of sedi nt does not necessarily repre nt a failure of this R provided that accumulated ediment is W wed durino erformance of the Surveillan g REFERENCES 1. SAR,Section(9.5
- 2. Regulatory Guide 1.137.
- 3. ANSI N195, 1976.
4.hSAR, Chapter 46{. 5 $ 5AR, Chapter {15h
- 6. ASTM Standards: D4057-Tssi;D975-Yqs};D4176-Ju};
D1552-pop D2622-J37); and 02276-yt J. a = w . . . . .. . . - . .
!""./' US B 3.8-49 Rev-1,-04/07/95-Rev7 1
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.3 DIESEL FUEL OIL AND STARTING AIR lh i NON BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and consnitments. Additional rewording, reformatting, and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. P.2 Bases changes are made to reflect plant specific design details. ) equipment terminology, and analyses. ' P.3 Not used. ! P.4 The Bases discussion regarding implementation of the Emergency Diesel Generator Fuel Oil Testing Program is revised. These revisions include, editorial enhancement for clarity, supplying the basis and intent of some of the required time limits of the Program: and include plant specific corrections for consistency with approved testing methods and procedures. Given the varying options for " receipt" of fuel oil, there may be potential delays between " receipt", sampling, analysis. and addition to the EDG storage tank. Therefore, additional detailed l clarification is appropriate. The Bases presented in the NUREG ' assumes that any and all fuel oil received is promptly added to , the storage tanks (after initial sampling). The clarification is ' needed specifically in the event fuel oil is " received" and stored on site for a period prior to addition to the tanks. The h inference in the ITS Bases would be that a fully tested sample is .d. required within 31 days after this " receipt": even if it is many $' months before the fuel oil is to be added to the storage tenk. The correct intent is supplied with this change (which is the same as the STS in the event the fuel oil is promptly added). The sample that will have a detailed follow-up analysis must be a recent sample of fuel oil: taken no more than 31 days before addition. This will leave a window for receipt of the sample analysis results from 31 days prior to addition to up to 31 days after addition. FERMI UNIT 2 1 REVISION 7 06/18/99 l
m. 4 l JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l@
- P.5 ISTS 3.8.3 Action E for EDG air receivers below minimum air pressure, is not adopted. This Action reflected new, added flexibility to the CTS requirements which consider the EDG inoperable as soon as low air pressure is. discovered. Similarly.
~
'ISTS 3.8.3 Action 8 and SR 3.8.3.2 for EDG lube oil minimum volume, is 'not adopted. This would have provided new, added flexibility to considering the EDG inoperable while providing time
-to~ restore lube oil quantities. The additional flexibility would require additional design testing, analyses, and or procedures and programs beyond the scope of the Fermi 2 conversion effort.
Therefore. this flexibility is not adopted at this time. P.6 ~ Editorial changes to reflect Writer's Guide conventions. When the LCO requirement might be requiring Operability of only some of the EDG subsystems (because in shutdown operations not all EDGs are required Operable), the convention is to use " required" in the Actions and Surveiliances when referring to the EDG. P.7 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification.
" split" criteria found in 10 CFR 50.36(c)(2)(ii).
GENERIC CHANGES ! C.1 TSTF 2: NRC approved change to NUREG-1433. O 4 FERMI - UNIT 2 .2 REVISION 7 06/18/99l u
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 DIESEL FUEL OIL AND STARTING AIR l@ TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.3 "L.1" Labeled Comments / Discussions) Detroit Edison has evaluated the proposed Technical Specification change identified as "Less Restrictive" in accordance with the criteria specified by 10 CFR 50.92 and has determined that the proposed change does not involve a significant hazards consideration. The bases for the determination that the proposed change does not involve a signifirant hazards consideration is an evaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below.
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
This change provides an allowable out of service time for diesel fuel oil and lube oil when these parameters are less than the required value. ] but which do not prevent the EDG from performing its safety function. This change will not result in a significant increase in the probability of an accident previously evaluated because the status of diesel fuel oil and lube oil does not affect the initiators of any analyzed event. This change does not affect the ability of the EDGs to support the performance of any credited equipment. As a result. no analyses assumptions are violated. Each of these EDO parameters contains substantial margin before reaching a condition that would prevent the EDG from performing its safety function and during the period allow for restoration, the EDG is still capable of performing its intended function. Based on this evaluation. there is no significant increase in the consequences of a previously analyzed event.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
This proposed change will not involve any physical changes to plant systems, structures. or components (SSC), or changes in normal plant operation. Therefore, this change will r.ot create the possibility of a new or different kind of accident from any accident previously evaluated. FERMI - UNIT 2 1 REVISION 7 06/18/99l
i l N0 SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l@ TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.3 "L.1" Labeled Comments / Discussions)
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change provides an allowable out of service time for diesel fuel oil and lube oil when these parameters are less than the required value. Each of these parameters contains substantial margin before reaching a condition that would prevent the EDG from performing its safety function. During the time allowed for restoring an out of limits parameter, the EDG is still capable of performing its intended function. There is no detrimental impact on any equipment design parameter, and the plant will still be required to operate within prescribed limits. While certain margins are decreased, based on the limited extent of the degradation (at least 6 days of fuel oil remains: EDG start capability remains: and fuel oil is still expected to support EDG operation), and the limited duration of these degradations, the change does not involve a significant reduction in the margin of safety. FERMI - UNIT 2 2 REVISION 7 06/18/99l
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 - DIESEL FUEL OIL AND STARTING AIR l@ TECHNICAL CHANGES - LESS RESTRICTIVE (Soecification 3.8.3 "L.2" Labeled Comments / Discussions) Detroit Editon has evaluated the proposed Technical Specification change identified as "Less Restrictive" in accordance with the criteria specified by 10 CFR 50.92 and has determined that the proposed change does not involve a significant hazards consideration, i The bases for the determination that the proposed change does not involve a significant hazards consideration is an evaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below.
- 1. Does the change involve a significant increase in the probability or i consequences of an accident previously evaluated?
The EDG fuel oil level verification staggered testing requirements have been deleted. This change will not result in a significant increase in 4 5 1 the probability of an accident previously evaluated because the test T schedule or verification of EDG fuel oil level has no effect on the initiators of any analyzed events. This change will not result in a significant increase in the consequences of an accident previously evaluated because the normal Technical Specification surveillance testing schedule provides adequate assurance that the Operable EDGs will be capable of performing their intended safety functions without additional verification of fuel oil level. Staggered testing provides no additional assurance of reliability because the EDGs are independent and the potential of a common cause failure is evaluated promptly whenever any EDG becomes inoperable.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
This proposed change will not involve any physical changes to plant systems, structures, or components (SSC), or changes in normal plant operation. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. FERMI UNIT 2 3 REVISION 7 06/18/99l
NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.3 DIESEL FUEL OIL AND STARTING AIR lh TECHNICAL CHANGES - LESS RESTRICTIVE (Soecification 3.8.3 "L.2" Labeled Comments / Discussions) )
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change, which allows only more scheduling flexibility in i performing EDG Surveillances while continuing the same frequency of g testing, is acceptable because the Operability of the EDGs is unaffected 2 by testing schedules, there is no detrimental impact on any equipment design parameter, and the plant will still be required to operate within g assumed conditions. The normal Technical Specification Surveillance testing schedule provides adequate assurance that the Operable EDGs will be capable of performing their intended safety functions. Staggered testing provides no additional assurance of reliability because the EDGs are independent and the potential of a common cause failure is evaluated promptly whenever any EDG becomes inoperable. Therefore the change does not involve a significant redetion in the margin of safety. i FERMI UNIT 2 4 REVISION 7 06/18/99l l
DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS
' SURVEILLANCE FREQUENCY m SR' 3.8.4.1 Verify battery terminal voltage is a 130 V 7 days for Division I and a 125.7 V for lb Division II on float charge.
6 SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors. 2 Verify each battery cell to-cell and terminal connection resistance is s 1.5E 4 ohm. t4 SR 3.8.4.3 Verify battery cells, cell plates, and 18 months J. racks show no visual indication of physical i 4 damage or abnormal deterioration that could i
%, degrade battery performance.
SR 3.8.4.4 Remove visible corrosion and verify battery 18 months cell to cell and terminal connections are coated with anti corrosion material. j SR 3.8.4.5 Verify each battery cell to cell and 18 months terminal connection resistance s 1.5E-4 ohm. SR 3.8.4.6 Verify each required battery charger 18 months O supplies for Division I: a 100 amps at g a 129 V for a 4 hours; and Division II:
= 100 amps at = 124.7 V for a 4 hours.
L% (continued) .s l FERMI UNIT 2 3.8-17 Revision 7 06/18/99
J l DC Sources-Operating B 3.8.4
' BASES' BACKGROUND (continued) a- Each DC battery subsystem is separately housed in a
. ventilated room a) art from its charger and distribution j centers. Each su) system is located in an area separated
' physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class IE subsystems such as batteries, battery chargers, or distribution panels. '
The batteries for DC electrical power subsystems are sized to produce required capacity at 80% of nameplate rating, m corresponding to warranted capacity at end of life cycles A and the 100% design demand. The minimum design voltage 4 limit is 105/210 V. Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation. while at the same time maintaining its battery bank fully charged. Each battery charger has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 24 hours while supplying normal steady state loads (Ref. 11). 4 APPLICABLE ~ The initial conditions of Design Basis Accident (DBA) and
- SAFETY ANALYSES ' transient analyses in the UFSAR. Chapter 6 (Ref. 4) and '
Chapter 15 (Ref. 5). assume that Engineered Safety Feature- , (ESF) systems are OPERABLE. The DC electrical power system provides. normal and emergency DC electrical power for the EDGs. emergency auxiliaries, and control.and switching during all MODES of. operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis '
' of the unit. This includes maintaining sufficient DC i sources OPERABLE during accident conditions in the event of: :
E a. . An assumed loss of all offsite AC power or all onsite AC power; and
- b. A worst case single failure.
The DC sources satisfy Criterion 3 of 10 CFR ; 50.36(c)(2)(ii). [ FERMI UNIT 2' B 3.8.4-2 Revision 7 06/18/99 I
1 l DC Sources-Operating B 3.8.4 BASES i LC0 The DC electrical power subsystems-with each DC subsystem
, consisting of two 130 VDC batteries in series, two battery chargers, and the corresponding control equi > ment and interconnecting cabling supplying power to t1e associated bus, are required to be OPERABLE to ensure the availability of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (A00) or a postulated DBA. Loss of any DC electrical power subsystem does not prevent the minimum safety function from being performed (Ref. 3).
APPLICABILITY The DC electrical power sources are required to be OPERABLE in MODES 1, 2. and 3 to ensure safe unit operation and to ensure that:
- a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of A00s or abnormal transients: and i
- b. Adequate core cooling is provided, and containment l integrity and other vital functions are maintained in !
the event of a postulated DBA. ; i' The DC electrical power requirements for MODES 4 and 5 are addressed in the Bases for LCO 3.8.5 "DC Sources-Shutdown." ACTIONS A.1 and B.1 Conditions A and B represent one division with a loss of i ability to completely respond to an event, and a potential loss of ability to remain energized during normal operation. If one of the re inoperable (e.g., quired DC electrical inoperable power subsystems battery, inoperable battery is charger (s), or inoperable battery charger and asscciated inoperable battery), the remaining DC electrical power subsystems have the capacity to support a safe shutdown and to mitigate an accident condition. A subsequent worst case single failure could, however. result in the loss of minimum necessary DC electrical subsystems to mitigate a worst case accident. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the hlFERMIUNIT2 B 3.8.4 - 3 Revision 7 06/18/99 i
L l l DC Sources-Operating B 3.8.4 l ! BASES. ACTIONS (continued) potential for com)lete loss of DC power to the affected
.- division. The 4 lour Completion Time (Required Action A.1) for restoration of an inoperable battery charger allows time to replace the inoperable charger with an OPERABLE spare
, battery charger, if available. The four hour. limit is reasonable based on the remaining capability of the battery i to carry the loads for this period. The 2 hour limit for l Required Action B.1 is consistent with the allowed time for an inoperable DC Distribution System division. The 2 hour , l Completion Time is based on Regulatory Guide 1.93 (Ref. 6) I and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and. if the DC electrical power subsystem is not restored to l OPERABLE status, to prepare to effect an orderly and safe l unit shutdown. C.1 and C.2 . If the station service DC electrical power subsystem cannot l < be restored to OPERABLE status within the required Completion Time, 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 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the recuireti plant conditions from full power conditions in an orcerly manner and without challenging plant systems. -The Completion Time to bring the unit to MODE 4 is consistent I with the time required in Regulatory Guide 1.93 (Ref. 6). SURVEILLANCE SR 3.8.4.1 REQUIREMENTS Verifying battery terminal voltage while on float charge for , the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with manufacturer recommendations and IEEE 450 (Ref. 7) j B 3.8.4 -4 Revision 7 06/18/99 hlFERMI-UNIT 2
(L DC Sources-Operating l B 3.8.4 l BASES
. SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.4.2 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each inter cell and terminal connection, provides an indication of. physical damage or abnormal deterioration that could potentially degrade battery performance. The connection resistance limits procedurally established for this SR are no more than 20% above the resistance as measured during installation and not above the ceiling value established by the manufacturer. This provides conservative measures to assure the Technical Specification limit is not exceeded. The Frequency for.these inspections, which can detect conditions that can.cause power losses due to resistance heating is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends. SR 3.8.4.3
. Visual-inspection of the battery cells cell plates, and
' battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. The presence of physical damage or
'd deterioration does not necessarily represent a failure of J - this SR. provided an evaluation determines that the physical g . damage or deterioration does not affect'the OPERABILITY of
<the battery (its ability to perform its design function).
The 18 month ~ Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable from a standpoint of maintaining reliability. s_ . . l FERMI UNIT ~2 'B 3.8.4 - 5 Revision'7. 06/18/99
- /
} .
l l DISCUSSION OF CHANGES ITS: SECTION 3.8.4 - DC SOURCES-0PERATING ADMINISTRATIVE l A.1 In the conversion of the Fermi 2 current Technical Specifications ! (CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not result in technical changes (either actual or interpretational). Editorial changes, reformatting, and re' vised numbering are adopted to make the ITS consistent with the Boiling Water Reactor (BWR) Standard Technical Specifications l NUREG 1433 Rev. 1. A.2 CTS SR 4.8.2.1.e limitation on the 60 month battery performance discharge test, to perform it "during shutdown." is more specifically presented in ITS SR 3.8.4.7 Note. The ITS SR is l presented with a more specific Note limiting the performance in Modes 1, 2, and 3. This specific limitation is consistent with the intent of "during shutdown" for this surveillance (as discussed with the NRC during ITS negotiations). Since this is , only a change in presentation of the CTS intent and current l practice, this change is considered administrative. l TECHNICAL CHANGES MORE RESTRICTIVE l None TECHNICAL CHANGES - LESS RESTRICTIVE " Generic" l LA.1 CTS LC0 3.8.2.1 provides details defining the two divisions of DC T power sources. The details relating to system design. function. 9 ar.d Operability are not necessary in the ITS. This information is 4 relocated to the Bases, which maintains the consistency with NUREG 1433. The definition of Operability, the Bases outline of Operability details (which requires change control in accordance with ITS 5.5.10. Bases Control Program) provides sufficient l control of these details. These details are not required to be in the ITS, to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable. FERMI UNIT 2 1 REVISION 7 06/18/99l l
DISCUSSION OF CHANGES ITS: SECTION 3.8.4 DC SU'JRCES 0PERATING LA.2 CTS 3.8.2.1. Action a. details one procedure for restoring an inoperable battery charger to Operable status " replace with the spare battery charger." This detail is relocated to the Bases for the ITS 3.8.4 Action to restore the battery charger to Operable status. The relocation of this information maintains the consistency with NUREG-1433. This is acceptable because these details do not impact the requirement to restore an Operable charger to service. These ' details can be adequately defined and controlled in the Bases which require change control in accordance with ITS 5.5.10. Bases Control Program. These details are not required to be in the ITS to provide adequate protection of the public health and safety, because these details do not impact the requirement to restore the required equipment to Operable. LA.3 The CTS details incl'ude the design duty cycle (4 hours), and, with l the option to simulate the emergency loads (using a " dummy load") by specifying the design load profile. CTS SR 4.8.2.1.d.2 details , the requirement for performance of a simulated battery service 4 test. ITS SR 3.8.4.7 relocates these design details to the UFSAR 6 and Technical Requirements Manual (TRM) but does retain the y requirement for the battery service test, and allowance for an t
" actual or simulated" test. Relocating these surveillance details maintains consistency with NUREG 1433. These relocated design details can be adequately defined and controlled in the UFSAR and TRM. Changes to the UFSAR and To.M will be controlled by the provisions of 10 CFR 50.59. These details are not required to be in the ITS to provide adequate protection of the public health and safety since the requirement for the battery service test remains in the Technical Specifications. ,
LA.4 CTS 4.8.2.1.f provides details defining battery performance degradation. The relocation of this information to the ITS Bases maintains the consistency with NUREG 1433. Any change to these details requires change control in accordance with ITS 5.5.10. Bases Control Program, which provides adequate control of these details. These details are not required to be in the ITS to provide adequate protection of the public health and safety. because these details do not impact the requirement to maintain the equipment Operable, or the requirement to perform the battery performance discharge test. FERMI UNIT 2 2 REVISION 7 06/18/99l
r-l l l DC Sources-Operating i 3.8.4 l l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 7 days kfl ' 2 - T"1%on float charee. - *
*7
- g ' g-fa @ Diyisie7 Awd h.125q sW bm H.
SR 3.6.4.2 Verify no visible corrosion at battery 92 days teminals and connectors. g eac k-fo _cdl and 44kinh Verify attery connection resistancee[is . s 41.5E-4 ohn)ef - i=+- -re" e-----t4e-r, l P. I s ::.;; c.;: <a- <=+- rut car.r.;nic;.;, - f L EE ' ^M f:r int:r ti;, ......d ;m.e,
- M f (LLL_6] f ,7 ;;.;inel-
- ntit,r.;].
C'I SR 3.8.4.3 Verify battery cells, cell plates, and months ; racks show no visual indication o ical 4 l damage or abnormal deterioration -tha .%.7 . l ,0- l- k (c oyta cityade, leaW1 p u %_ nw. SR 3.8.4.4 Remove visible corrosion and verify battery months cell to cell and terminal connections are f,l --[:l::: : d it;ht, M] coated with 4*8'2*I'01 anti-corrosion material.
@ d^d D lD M k_fHbattery7connectionresistance /8 SR 3.8. Ver' montns tac -"
5 0 5E 4 oh t fr- 4-t M .',:-; cler, ~----t aae-M :r :rn i ::n---ti:::, p'g . s ;;."., -4 i,; , f;r intoe-44cr :: nn tirn:. V, E,2 ) . 0. 3
- d ; !!.5El &] fsr t:--i- '
ee;.ndies) . (continued) St W 4- N 4 3.8-25 "= 1, Ot/07/05 AEV ] j
DC Sources-Operating B 3.8.4 BASES BACKGROUND In case of loss of normal power to the battery charger, the (continu DC loads are automatically powered from the-e;.ti n - (' 2. batteries. The DC power distribu ion system is described in more detail
. in Bases for LCO 3.8. , " Distribution System-Operating,"
and LC0 3.2, " Distribution System-Shutdown." Each battery has adequate storage capacity to carry the required load continuously for approximately hours (Ref. 4 4 n, i fach battery subsystem is separately housed in a ventilated room apart from its charger and distribution centers. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class IE subsystems such as batteries, battery chargers, or distribution panels. The batteries for DC electrical power subsystems are sized to produce required capacity at 80% of nameplate rating, (9 corresponding to warranted capacity at end of life cycles 1 and the 100% design demand. The minimum design voltage R limit is 105/210 V. W Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation , of connected loads required during normal operation, while at the same time maintaining its battery bank fully charged. P.3 Each M"4 -
- nin battery charger has sufficient capacity ,
1 to restore the battery from the design minimum charge to its l fully charged state within 24 hours while supplying n9rmal I steady state loads (Ref. . APPLICABLE The initial conditions o sign Basis Accident (DBA) and SAFETY ANALYSES transient analyses in th SAR, Chapter 4k (Ref. 4) and Chapter 115k (Ref. 5), assume that Engin{eered Safety Feature (ESF)sfs1ensareOPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the ! DGs, emergency auxillaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial issumptions of the (continued) 4"!/1 ST: B 3.8-51 6 1, 0?/07/;: -
/
Rev7
/
1 DC Sources-0perating B 3.8.4
/
INSERT B 3.8.4-2
<< R OVED in Revi ion 7 >> i l
l 1 l l l
/$- 0 FERMI UNIT 2 Page B 3.8 51 (Insert) REVISION 7' 06/18/99l }
DC Sources-Operating B 3.8.4 BASES I SURVEILLANCE SR 3.8.4.2 (continued) REQUIREMENTS acceptable based on operating experience related to detecting corrosion trends. SR 3.8.4.3 I
/NMT Visual inspection of the battery cells, cell plates, and f 3,3,Q qq battery racks provides an indication of physical damage or 1
abnormal deterioration that.could potentially degrade e1 battery performance. 3 I g,,Qpgtifib....pg'ertii.!"1: 9.,.pi:t:gtejth }
- t _E*
r. 3 ;*
- v' 6 * ' NU *u*
n".".L*..' t. !.6'v"e'.w"i 6 : en anu rau i6fn v. 6 .vi. ym. . .y q h3,7 4k - J p,1 SR 3.8.4.4 and SR 3.8.4.5 Visual inspection and resistance measurements of inter-cell,. int:r r::h, int:r ti:r s and terminal connections provides W indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti-corrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each teneinal connection. The removal of visible corrosion is a preventive maintenance SR. The presence of visible corrosion does not necessarily represent a failure of this SR, provided visible corrosinn is removed during performance of this Surveillance. 1 er's Note: The requiremen to verify that term on etions are lean and tight applies only to nickel a ium batter s as per IEEE tandard P1106, EEE Op.3 Re on. ended e etice for Ins iation, nainte ance, Testi a d Replace t of Vented Ni kel - Cadmium B tteries for tationary plications. his requirement y be remo d or lead a d batteries. , , (continued) BWR/4 STS B 3.8-55 Rey-1704f07j95 eav7 i
)
DC Sources Operating B 3.8.4
, INSERT B 3.8.4 4a The presence of physical damage or deterioration does not necessarily represent a failure of this SR provided an
[ evaluation determines that the physical damage or g deterioration does not affect the OPERABILITY of the battery P (its ability to perform its design function). 8 k t INSERT B 3.8.4 4b l/ The 18 month Frequency is based on engineering judgement, taking into consideration the desired plant conditions to perform the Surveillance. Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable -from a standpoint of maintaining reliability. FERMI UNIT 2 Page B 3.8 55 (Ir 't) REVISION 7. 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.8.5 DC SOURCES. SHUTDOWN M.2 CTS 3.8.2.2 Actions for inoperable DC sources, does not require corrective action to restore the inoperable source. ITS 3.8.5 requires the immediate corrective actions (Required Action A.2.4) to restore the inoperable DC sources. This eliminates flexibility, and is therefore a more restrictive change assures efforts to return the plant to acceptable safe operation from the standpoint of necessary electrical support. As such, this more restrictive change has no negative impact on safety. TECHNICAL CHANGES - LESS RESTRICTIVE
Generic" LA.1 CTS LC0 3.8.2.2 provides details defining the two divisions of DC power sources. The details relating to system design, function. Y and Operability are not necessary in the ITS. This information is 9O relocated to the Bases, which maintains the consistency with NUREG 1433. The definition of Operability, the Bases outline of Operability details (which requires change control in accordance with ITS 5.5.10. Bases Control Program) provides sufficient control of these details. These details are not required to be in the ITS to provide adequate protection of the public health and safety, because these details do not impact the requirement to maintain the equipment Operable.
)
1 1 FERHI UNIT 2 2 REVISION 7 06/18/99l !
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.5 DC SOURCES SHUTDOWN NON BRACKETED FLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current Technical Specification requirements. Specifically. LC0 3.0.3 is not Fequired to'be applied to the Actions of this Specification. P.2 Bases changes are made to reflect plant specific design details. equipment terminology. and analyses. P.3 Bases changes are made to reflect changes made to the Specification. Refer to the Specification and associated JFD if applicable for i additional detail. P.4 NUREG-1433 imposes excessively restrictive DC power source requirements when features on both divisions are required to be Operable. This change continues to require Operable DC power ! sources on both divisions. but relaxes the ISTS requirements for one division. This will allow for appropriate surveillance and testing activities during shutdown conditions. CTS requirements I were made more restrictive to reflect this proposed ITS. Refer to associated DOC M.1 provided below for reference: M1 CTS 3.8.2.2 requires one division of battery and battery charger to be Operable during shutdown conditions, but is not specific as to which division it must be powering. ITS imposes additional requirements consistent with the Operability requirements of all other features that may be required to be Operable by the ITS. Specifically ITS 3.8.5. DC Sources - Shutdown requires: 1) one div.ision to be Operable with both 125 V batteries and both associated battery chargers, and 2) when the other DC distribution subsystem division is required to be energized, providing power from at least one battery or one battery charger. Since the DC sources Operability requirements are extended to require the capability of supplying power to all necessary loads. if one or more required DC sources are not Operable, sufficient DC sources may still be available to support sufficient required components to allow continuation of refueling activities for a limited time. Therefore. it may not be necessary to suspend all Core Alterations, irradiated fuel handling, and OPDRVs. Conservative Actions can be assured if all required equipment associated with the inoperable DC source are declared inoperable and their associated Actions taken. Therefore, along with the conservative additional requirements placed on Operable DC sources. Required Action A.1 is also proposed. FERMI - UNIT 2 1 REVISION 7 06/18/99l . J
Battery Cell Parameters 3.8.6 3.8- ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 - Battery cell parameters for the Division I and Divis. ion II batteries shall be within limits. APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.
. ACTIONS
..................................... NOTE----- - --- - -- ------ - -- ----
Separate Condition entry is allowed for each battery. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cells 1 hour with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6 1 !
@l
# Table 3.8.6 1 Category Category C limits. '
A or B limits. ;
! AND k
~
A.2 Verify battery cell 24 hours , parameters meet Table 3.8.61 AND Category C limits. , Once per 7 days ' thereafter AND A.3 Restore battery cell 31 days parameters to , Table 3.8.6 1 hl l Category A and B limits. (continued) l FERMI UNIT 2- 3.8 22 Revision 7 06/18/99 i
Battery Cell Parameters 3.8.6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable. Time of Condition A not met. 08 One or more batteries with average electrolyte temperature of the representative cells not within limits. 08 One or more batteries with one or more battery cell parameters not within Table 3.8.6 1-Category C values. SURVEILLANCE REQUIREMENTS SURVEILLANCE- FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.6 1 Category A limits. (continued)
- l. FERMI UNIT 2 3.8-23 Revision 7 06/18/99
Battery Cell Parameters B 3.8.6 BASES ~ SURVEILLANCE REQUIREMENTS (continued) Category C' defines the limits for each connected cell. These values. although reduced, provide assurance that
. sufficient capacity exists to perform the intended function
' and maintain a margin.of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and
' the battery must be declared inoperable.
The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates. suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value for voltage is based on IEEE 450 (Ref. 3), which states that a cell voltage of 2.07 V or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement. The Category C limit'on average specific gravity a 1.190. is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit. it is required that
+he specific gravity for each connected cell must be no less
'than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery. '
2I -Footnote (b) to Table 3.8.6 1 is applicable to Category A. ! Q B. and C specific gravity. Footnote (b) of Table 3.8.6 1 requires the above mentioned correction for electrolyte 3 level and temperature. : Because of specific gravity gradients that are produced l
.during the recharging process. delays of several days may occur while waiting for the specific gravity to stabilize.
A stabilized charger current is an acceptable alternative to sacific gravity measurement for determining the state of m c1arge of the designated pilot cell. This phenomenon is 1 ' discussed in IEEE 450 (Ref. 3). Footnote (c) to Ql ' Table 3.8.6 1 is applicable to Category A and C. and allows the float charge current to be used as an alternate to
- speci fic . gravity.
l FERMIL UNIT 2 B 3.8.6 -6 Revision 7 06/18/99 j
b i i ELECTRICAL-POWER SYSTEMS 3/4.8.2 fpfc / F/ e4 77DM .3 7 le D.C. SOURCES D.C. SOURCES - OPERATING g g.gg g,g, j (Also .sa .spuiRca He 3 7.2-) LIMITING CONDITION FOR OPERATION (3.8.2.I As a minimum, the following 0.C. electrical power sources shall.be OPERABLE: ; a .. . Division 1. consisting of: El. 130 VDC Battery 2A-1.
- 2. 130 VDC Battery 2A-2. i
- 3. Two 130 VDC full capacity chargers. -
- b. Division II. i:onsisting of:
- 1. 130 VDC Battery 2B-1.
,2 . 130 VDC Battery 28-2.
- 3. Two 130 VDC full capacity chargers. ,
APPLICABILfTY: OPERATIONAL CONDITIONS 1, 2, and 3. d A'Y ACTION: sf d
\ N /
t. With a battery charger in either Division I or Division II of the above D.C. electrical power sources inoperable, restore the inoperable battery l I charger to OPERABLE status or replace with the spare battery charger f within in COLD4SHUTDOWN hours or be inthe within at following least HOT SHUTDOWN within the next 12 hours 24 hours.
- b. ;
With either Division I or Division II of the above required D.C. electrical power sources otherwise inoperable, restore the inoperable . division to OPERABLE status within 2 hours or be in at least HOT SH within"the'next 12 hours and in COLD SHUTDOWN within the following 24 hours. SURVEILLANCE REOUTREMEt'TS l 4.8.2.1
< demonstrated OPERABLE:Each f of the above required 130-volt batteries and chargers s
- a. i At least once per 7 days by verifying that:
S A 3.3.4 1 1. The and parameters in Table 4.8.2.1-1 meet the Category A limits, su- . spa ge gm 7.r. ~ Total battery terminal voltage is greater than or equal to 130 for nlvision 11 on float charge. volts for Division I and 'greater th
- b. ,l !
At least onceJer 92 dals/and withinW.a eryL/ N hovd [i battery r overcharge with battery terminal e voltagdiscTarge eater than 150
' li gl i_ 1 and greater than 145 volts f_ D1 vision 11 y
.I
, l SA 34,(,,'2 J 1. 1_( 4.< sA 3. s 4. 3 ') l. . -+-
The parameters in Table 4.8.2.1-1 meet the Category B limits, 1d t
'This
'3.7.1.2 are ACTION taken. may be delayed for up to 16 hours for batte f SR. S)Lati$ cal 3n 3.&
FERMI - UNIT'2 3/4 8-10 Amendment No. BB.121 PAGE 3- # 03 Ra 7 t
DISCUSSION OF CHANGES ITS: SECTION 3.8.6 BATTERY CELL PARAMETERS Additionally. CTS 4.8.2.1.b requires- a verification that battery parameters, meet Category B limits within 7 days after a battery discharge or overcharge. This 7 day " allowance" is consistent with the CTS 7 day action time discussed above. ITS SR 3.8.6.2 provides a more restrictive requirement to surveil battery parameters within 24 hours after a battery discharge or overcharge. While this surveillance is a more restrictive frequency, it is accompanied by the extended (31 day) Completion Time discussed above: and is therefore, of minimal impact on operation. L.2 CTS Table 4.8.2.1 1 requires that the electrolyte level be maintained in a specified range. ITS Table 3.8.6-1 footnote (a) allows for a temporary electrolyte level increase during and following an equalize charge and is based on guidance from Appendix A to IEEE-450. The level excursion due to gas generation during an equalizing charge would be expected to return to normal following completion of the equalize charge. Therefore, this less restrictive change will have a negligible impact on safety. L.3 CTS 4.8.2.1.b.3 requires that once every 92 days and within 7 days after a battery discharge or overcharge, the average electrolyte temperature is verified to be above 60 F. ITS SR 3.8.6.3 requires this same verification to be performed only once every 92 days, eliminating the increased frequency after a battery discharge or > overcharge. This is acceptable because a large discharge or d overcharge of the battery will tend to heat the battery electrolyte not reduce the temperature. The need to increase the k frequency of monitoring electrolyte temperature is not necessary. Therefore, this less restrictive change will have no impact on safety. RELOCATED SPECIFICATIONS None 4 TECHNICAL SPECIFICATION BAE S Bases for this Specification have been added that reflect the format and applicable content of ITS 3.8.6 consistent with the BWR STS. NUREG-1433. _.. Rev. 1. l FERMI - UNIT 2 3 REVISION 7 06/18/99l l
Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS [ CTS) 3.8.6 ' Battery Cell Parameters _ LCO 3.8.6 OivifikI cwd Civisih Battery cell parameters for the-pt:ti;r, ;...w . .riu uuj gg 4, batteries shall be within@ limits-;f ide,0.9.5 L APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE. ACTIONS
-NOTE - - - - - - - - - - - - - - - - - - - - - - - -
Separate Condition entry is allowed for each battery. 3 CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verifypilotcell,[sl I hour 78t 4.12 8-1; with one or more electrolyte level and nok 0h(D battery cell float voltage meet parameters not within Table 3.8.6-1 1 Category A or B Category C limits. limits. Q3 4 l TabitS8 A.2 Verify battery can 24 hours g OC.I .. parameters meet Table 3.8.6-1 M Category C limits. Once per 7 days thereafter M A.3 Restore battery cell 31 days parameters to Category A and B _ limits D( sf Table 3.5.6-J. (continued)
--0WRf4-GM-- 3.8-30 ^ev 1, 04/07/06-
@v7
l l l Battery Cell Parameters 3.8.6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME-l B. Required Action and B.1 Declare associated Imediately
. associated Completion battery inoperable.
Time of Condition A T6L 941.1-l) not met. g , g y) E ; One or more batteries i with average I electrolyte temperature of the 3.1.1. b.3 ) representative cells not within limits. E One or more batteries with one or more battery cell parameters not within 1 yCategort C values. NT abl&3.8E-D 1 1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days A Table 3.8.6-1 Category A limits. 4 0 2.l A .j p i (continued) ; l L;/4 :T: 3.8-31 L.1, C4/C7/>6-- Ren/ 7
i Battery Ce*1 Parameters i B 3.8.6 l BASES
)
SURVEILLANCE Table 3.B.6-1 (continued) REQUIREMENTS Category C defines the limits for each connected cell. These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function ) and maintain a margin of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and the battery must be declared inoperable. ( The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the i plates suffer no physical damage and maintain adequate I electron transfer capability. The Category C Allowable Value for voltage is based on IEEE-450 (Ref. 3), which states that a cell voltage of 2.07 Y or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement. The Category C limit on average specific gravity 3 ..!?!), is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit, it is required that the specific gravity for each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not k overall degradation of the battery. otnote @ET Table 3.8.6-1 tu t y t: ;;;d 'h
; s;Zy = ) applicable to Category A, 8, and C specific 7
gravity. Footnote (b) of Table 3.8.6-1 requires the above ln mentioned correction for electrolyte level and temperatute f Ni sne xception Inat levpl correction is not requi ma when ba ery charging curr nt, while on f1 at charge, is
<1 for station serv e batteries an < 0.5 amp for,DG bat ries. This curre provides, in eral, an ind Watio V f overall battery c dition. f j
Because of specific gravity gradients that are produced during the recharging process, delays of several days may occur while waiting for the specific gravity to stabilize. A stabilized charger current is an acceptable alternative to specific gravity measurement for determining the state of charge of the designated pilot cell. This phenomenon is discussed in IEEE-450 (Ref. 3). Footnote (c) to Table 3.8.6-1
'mL (Is ApplicaMe. k Castgwy Aa*d C d*tQ ~
1k (continued) Z/4 ST: - B 3.8-69
- 1, 04/07/05 b7
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.8.6 BATTERY CELL PARAMETERS NON-BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG-1433 to reflect Fermi 2 current l licensing basis: including design features, existing license requirements and commitments. Refer to CTS Discussion Of Changes to i the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. Additional rewording. reformatting. and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses. P.3 Bases changes are made to reflect changes made to the Specification. Refer to the Specification, and associated JFD if applicable, for additional detail. P.4 Not used. lh P.5 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification
" split" criteria found in 10 CFR 50.36(c)(2)(ii).
GENERIC CHANGES C.1 TSTF 278. Rev 0: NRC approved change to NUREG-1433. J FERMI UNIT 2 1 REVISION 7 06/18/99l i i
i NO SIGNIFICANT HAZARDS EVALUATION ! ITS: SECTION 3.8.6 BATTERY CELL PARAMETERS i TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.6 "L.3" Labeled Comments / Discussions) Detroit Edison has evaluated the proposed Technical Specification change identified as "Less Restrictive" in accordance with the criteria specified by l 10 CFR 50.92 and has determined that the proposed change does not involve a I significant hazards consideration. The bases for the determination that the proposed change does not involve a significant hazards consideration is an evaluation of these changes against each of the criteria in 10 CFR 50.92. The criteria and the conclusions of the evaluation are presented below.
- 1. Does the change involve a significant increase in the probability or !
consequences of an accident previously evaluated? The proposed change eliminates the increased frequency of monitoring battery electrolyte temperature after a battery discharge or overcharge. The DC electrical power sources and this requirement are not an ; initiator of any previously analyzed accident. Therefore, the change y will have no impact on the probability of an accident previously 1 analyzed. The ITS LC0 and SRs continue to provide adequate assurance of Operable batteries because a large discharge or overcharge of the battery will tend to heat the battery electrolyte not reduce the temperature. Therefore, the proposed change does not involve an increase in the consequences of any accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
This proposed change will not involve any physical changes to plant systems, structures, or components (SSC), or changes in normal plant operation. Therefore this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. FERMI UNIT 2 5 REVISION 7 06/18/99l
l l NO SIGNIFICANT HAZARDS EVALUATION ITS: SECTION 3.8.6 - BATTERY CELL PARAMETERS TECHNICAL CHANGES LESS RESTRICTIVE (Soecification 3.8.6 "L.3" Labeled Comments / Discussions)
- 3. Does this change involve a significant reduction in a margin of safety?
This change does not involve a significant reduction in a margin of ty-safety because a large discharge or overcharge of the battery will tend ) to heat the battery electrolyte not reduce the temperature. Therefore. 22 the need to increase the frequency of monitoring electrolyte temperature QC is not necessary to assure the battery's capability to perform its safety function. l l l l FERMI UNIT 2 6 REVISION 7 06/18/99l j
, . . .y . . Distribution Systems-Operating 3.8.7 3.8 ELEC1RICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating l LC0 3.8.7 The following Division I and Division II AC and DC electrical power distribution subsystems shall be OPERABLE:
- a. AC electrical power distribution subsystems:
Division I Division II
- 1. 4160 V Buses 11EA. 12EB 13EC. 14ED 64B. 64C 65E. 65F
- 2. 480 V Buses 72EA. 72EB 72EC. 72ED 72B. 72C 72E. 72F
- 3. 120 V MPU 1 MPU 2
- b. DC electrical power distribution subsystems:
Division I Division II
- 1. 130 V Distribution 2PA 2 2PB 2 Cabinet
- 2. 260 V MCC 2PA 1 2PB 1 APPLICABILITY: MODES 1. 2. and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required. A.1 Restore AC electrical 8 hours
'AC electrical power power distribution distribution subsystem (s) to 6N_Q subsystems inoperable. OPERABLE status.
16 hours from discovery of failure to meet LC0 (continued)
, } FERMI UNIT 2 3.8 26 Revision 7 06/18/99 i
( . ,- .o ,g[ ;f g '
Spec t rienTieu 3. 6,7 A.I ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS (/ AISo (Mg w # A c k s.s'.t ) m hui[icAS.5,7.7) Of 5TRIBUT10N OPERATING LIMITING CONDITION FOR OPERATION L.0 0 4.aa.'m The following power distribution system divisions and busses shall be
.'3
- I O energ>ced41Wtte breaktpf oDen bt(ween reduAhant buspts within EMe unif)L , g
- a. A.C. power distribution: j
- 1. Division 1. sistincLof*
a) 4160V R mple usses llEA and 12EB. b) 4160V R tor Bu. ina Busses 64B and 64C. c) 480V Complex usses 72EA and 72EB. d) 480V eactor B'ut Busses 72B and 72C. e) 120V Division [] Powp Suppfy unrU MPU 1.
- 2. Division 11. sisting h I a) 4160V mpiex susses 13EC and 14ED.
b) 4160 Re ter Bu Busses 6SE and 65F. c) 480V R Comple usses 72EC and 72ED. d) 480V actor i M Busses 72E and_72F. e) 120Y ptvision 1111W rower suppiy # nit) MPU 2.
" y, YC *
- b. D.C. power distribution:
- 1. Division 1. consisting of:
a) 130 volt D.C. Distribution Cabinet 2PA 2. b) 260 volt D.C. MCC 2PA 1.
- 2. Division !! consisting of:
a 130 volt D.C. Distribution Cabinet 2PB 2. l b 260 volt D.C. MCC 2PB 1. 1 APPtfCABitfTY: OPERATIONAL CONDITIONS 1, 2 and 3. \ 00: AcT104 D / ,' ACTION: 0MW ' a.. With one of the above required A.C. distribution system division - not energized, reenergize the division within}8'fiours' or be in at \ riAC3cM g ACTIDM C least HOT SHUTDOWN within the next 12 hours and T CDL SHUTDOWN within the f 24 hours.' [,l bt 4 J^ *% k
- b. With one f the above required D.C. distribution system divisions Q N ON not energized, reenergize the division withindfiobrs~ lor be in at j l ACTiotJ C., least HOT SHUTDOWN within the next 12 hours and inl 6LD SHUTDOWN l
[ within the following 24 hours.
- c. titth the swing bus not energized or the swing bus automatic W- throwcver scheme inoperable, declare both low pressure coolant Spec'eficafiirr 55.l injection (LPCI) system subsystems inoperable and take the ACTION
, required by Specification 3.5.1. l / Su ihis ACTION may be delayed for up to 16 hours for A.C. distribution system '
j' components made inoperable due to loss of EECW cooling providad theI ACTIONS of
'ft&iSicdh. w- Specification 3.7.1.2 are taken. !
y 17.'L l FERMI - UNIT 2 3/4814 Amendment No. 29, 80 PAGE L _0F 02 g,g 7 L )
DISCUSSION OF CHANGES ITS: SECTION 3.8.7 - DISTRIBUTION SYSTEMS OPERATING ADMINISTRATIVE A.1 In the conversion of the Fermi 2 current Technical Specifications (CTS) to the proposed plant specific Improved Technical Specifications (ITS), certain wording preferences or conventions are adopted which do not result in technical changes (either actual or interpretational). Editorial changes, reformatting, and revised numbering are adopted to make the ITS consistent with the Boiling Water Reactor (BWR) Standard Technical Specifications NUREG 1433. Rev. 1. IECHNICAL CHANGES MORE RESTRICTIVE M.1 CTS 3.8.3.1. Action a. and CTS 3.8.3.1. Action b. require restoration of the AC electrical power distribution subsystem within 8 hours and restoration of the DC electrical power distribution subsystem within 2 hours: however, there is no limit on overlapping inoperabilities of AC and DC subsystems. ITS 3.8.7 Action A. and ITS 3.8.7 Action B. have the same 8 hour and 2 hour Completion Times, but also establish a maximum time of 16 hours g that any combination of AC and DC electrical power distribution i subsystems fails to meet LC0 3.8.7. Therefore, to place an appropriate restriction on any unusual situation, the additional d T Completion Time of "16 hours from discovery of failure to meet the LC0" is added. This Completion Time restriction although more restrictive, ensures consistent application of the ITS and therefore, will have no negative impact on safety. TECHNICAL CHANGES - LESS RESTRICTIVE " Generic" LA.1 CTS 3.8.3.1 requires power distribution divisions and buses to be
" energized with tie breakers open ", and also includes descriptive information on distribution nomenclature. ITS LC0 3.8.7 relocates specific details of Operability and descriptive information to the j Bases. This is acceptable because these details do not impact the requirement to maintain Operability and the ITS definition for {
i Operability ensures that the buses are energized and not cross I tied. These details can be adequately defined and controlled in l the Bases which require change control in accordance with ITS j 5.5.10. Bases Control Program. These details are not required to i be in the ITS to provide adequate protection of the public health and safety, because these aetails do not impact the requirement to l maintain the equipment Operable. 1 FERMI UNIT 2 1 REVISION 7. 06/18/99l
DISCUSSION OF CHANGES ITS: SECTION 3.8.7 DISTRIBUTION SYSTEMS 0PERATING IfCHNICAL CHANGES LESS RESTRICTIVE "Speci fic" L.1 CTS LC0 3.8.3.1 allows restoration times for one division of AC distribution (8 hours Action a), and one division of DC distribution (2 hours Action b), de energized. ITS 3.8.7 Action A and B, allows one "or more" AC and DC electrical power distribution subsystems to be inoperable for the same times. respectively. Concurrently, however, ITS Action D is also added to require that if two or more electrical power distribution subsystems are inoperable, resulting in a loss of function, enter LC0 3.0.3 immediately. The combinatior of the "or more" addition to ITS 3.8.7 Actions A and B and the addition of Action D, along with ITS LCO 3.0.6, Safety Function Determination Program, ensure that with the loss of any electrical power distribution system no loss of function will occur without the appropriate action. This presentation will allow the Action A or Action B Completion Time for a portion of one division to be inoperable in conjunction with . a portion of the second division to be inoperable, provided these M portions do not affect redundant systems required for safe 1 operation. In the event a loss of function exists, ITS Action D ] will provided actions consistent with the CTS Actions for g inoperabilities in both divisions. Therefore, this less restrictive change will have a negligible impact on safety. BJLOCATED SPECIFICATIONS None I TECHNICAL SPECIFICATI0t[ BASES The CTS Bases for this Specification have been replaced by Bases that reflect the format and applicable content of ITS 3.8.7 consistent with the BWR STS, NUREG 1433. Rev. 1. FERMI UNIT 2 2 REVISION 7 06/18/99l
Distribution Systems-Operating 3.8. 3.8 ELECTRICAL POWER SYSTEMS 3.8. V Distribution S st -Operati ud , j [ CTS Y na S.IloA r .
<, _, ,, g LCO 3 vision andbivision AC DC, -{e,M AC';it;l :, ;J t f electrical power distribution su systems shall be OPERA 8LEAh f/t/ SERT 3.8.1-1, y APPLICABILITY: MODES 1, 2, and 3.
1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME O'fk"
.. One or more nc -
fje.) A.1 Restore AC electrical 8 hours a electrical power power d tion - distribution subsyst o E subsystems inoperable. OPERABL tus. 16 hours from g discovery of /g,g T , failure to meet ; LCO E One or more A vital B.1 MestoreACvital us 2 houri uses inoperabl distribution subiystems to E OPERAh E status, k.I khoursfrom dit very of , fail to meet ' LCO i 6 . One no snon- 1 Restore D lectrical 2 hours 5:nvies} DC electrical power d ution g; h power distribution subsyst subsystems inoperable. E OPERABL tus. 16 hours from u discovery of (Doc M.I) 1 failure to meet << LCO T (continued) W.rTS- 3.8-38 n;; 1, 01/07/05
#cv 7 oc .
s y t t'
- y. . r - . . .
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ! ITS: SECTION 3.8.7 DISTRIBUTION SYSTEMS OPERATING NON BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and comitments. Refer to CTS Discussion Of Changes to the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. Additional rewording, reformatting, and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. P.2 Bases changes ara made to reflect plant specific design details, equiprent terminology. and analyses. P.3 Not used. P.4 Fermi CTS details some. but not all. distribution buses in the requirements of CTS LC0 3.8.3.1. The remaining distribution subsystems are inferred to be associated with Operability of individually powered features (as such, they are not allowed the l
" blanket" 8 hours (for AC)/2 hours (for DC) to restore power). !
ITS reflects the Fermi 2 current licensing basis (CLB). Only l
" primary" AC buses. MPUs. DC distribution cabinets, and DC MCCs l are addressed in ITS LC0 3.8.7: the remainder of the distribution system is directly addressed by Operability of the associated powered features.
P.5 Editorial changes made for clarity. The Bases statement. "..the remaining are capable of supporting the minimum functions " is based on the implicit assumption that Action D is not also entered d (which is required if there is a loss of safety function). 4. Therefore, these changes simply include this assumption for added clarity. Q P.6 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification
" split" criteria found in 10 CFR 50.36(c)(2)(ii). l FEPsMI UNIT 2 1 REVISION 7 06/18/99l
1 I
)
l l I JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.8.8 DISTRIBUTION SYSTEMS SHUTDOWN I l NON BRACKETED PLANT SPECIFIC CHANGES - P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license j l requirements and commitments. Refer to CTS Discussion Of Changes to ! the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. Additional rewording, reformatting, and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. Specifically, some of these changes are discussed as follows: j
- a. An editorial clarification is inserted in the LC0 Bases --
acknowledging that during shutdown conditions what would 1 otherwise be redundant safety related divisions, may be cross tied. This acknowledgement is provided in the NUREG 1433 k l Bases for Specification 3.8.2, and is similarly added here. P.2 Not used. P.3 Not used. P.4 Editorial correction to Bases to include information consistent with the associated ITS Required Action. P.5 The reference to the NRC Policy Statenent has been replaced with a more appropriate reference to the Improved Technical Specification 1
" split" criteria found in 10 CFR 50.36(c)(2)(ii). l l
4 FERMI UNIT 2 1 REVISION 7 06/18/99l j
INSERT THIS PAGE IN FRONT OF VOLUME 11 Volume 11: CTS MARKUP COMPILATION Remove Replace 3/4 3-23 (3.5.1 CTS M/U) pg i of 10 3/4 3-23 (3.5.1 CTS M/U) pg 1 of 10 Rev 7 3/4 4-2 (3.5.1 CTS M/U) pg 2 of 10 3/4 4-2 (3.5.1 CTS M/U) pg 2 of 10 Rev 7 3/4 5-3 (3.5.1 CTS M/U) pg 5 of 10 3/45-3(3.5.1 CTS M/U) pg 5 of 10 Rev 7 3/4 5-3 (3.5.2 CTS M/U) pg 1 of 8 3/4 5-3 (3.5.2 CTS M/U) pg i of 8 Rev 7 3/4 5-4 (3.5.2 CTS M/U) pg 2 of 8 3/4 5-4 (3.5.2 CTS M/U) pg 2 of 8 Rev 7 3/4 5-6 (3.5.2 GS M/U) pg 3 of 8 3/4 5-6 (3.5.2 CTS M/U) pg 3 of 8 Rev 7 3/4 5-8 (3.5.2 CTS M/U) pg 5 of 8 3/4 5-8 (3.5.2 CTS M/U) pg 5 of 8 Rev 7 3/473(3.5.1 CTS M/U) pg 8 of 10 3/4 7-3 (3.5.1 CTS M/U) pg 8 of 10 Rev 7 3/47-5(3.8.1 CTS M/U) pg 1 of 8 3/47-5(3.8.1 CTS M/U) pg i of 8 Rev. 7 3/4 7-5 (3.8.2 CTS M/U) pg 1 of 2 3/4 7-5 (3.8.2 CTS M/U) pg 1 of 2 Rev. 7 3/4 S-1 (3.8.1 CTS M/U) pg 2 of 8 Rev 2 3/4 8-1 (3.8.1 CTS M/U) pg 2 of 8 Rev 7 3/4 8-) (3.8.3 CTS M/U) pg 1 of 5 Rev 2 3/4 8-1 (3.8.3 CTS M/U) pg i of 5 Rev 7 3/48-2(3.8.1 CTS M/U) pg 3 of 8 Rev 2 3/4 8-2 (3.8.1 CTS M/U) pg 3 of 8 Rev 7 3/48-3(3.8.1 CTS M/U) pg 4 of 8 3/48-3(3.8.1 CTS M/U) pg 4 of 8 Rev 7 3/4 8-3 (3.8.3 CTS M/U) pg 2 of 5 3/4 8-3 (3.8.3 CTS M/U) pg 2 of 5 Rev 7 3/4 8-4 (3.8.3 CTS M/U) pg 3 of 5 3/4 8-4 (3.8.3 CTS M/U) pg 3 of 5 Rev 7 3/4 8-7 (3.8.3 CTS M/U) pg 4 of 5 3/4 8-7 (3.8.3 CTS M/U) pg 4 of 5 Rev 7 3/4 8-10 (3.8.6 CTS M/U) pg 1 of 3 Rev 2 3/4 8-10 (3.8.6 CTS M/U) pg 1 of 3 Rev 7 3/4 8-14 (3.8.7 CTS M/U) pg 1 of 2 3/4 8-14 (3.8.7 CTS M/U) pg i of 2 Rev 7 3/4 8-15a (3.5.2 CTS M/U) pg 8 of 8 3/4 815a (3.5.2 CTS M/U) pg 8 of 8 Rev 7 Rev 7 06/18/99 l j l
e l SpecaricAmo 2. r.1 \ b50 54 SpedMCANM 3,3 f.l) INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMEN ON LIMITING CONDITION FOR OPERATION 6 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2. APPLICABILITY: As shown in Table 3.3.3-1. AC.IlQH:
- a. With an ECCS actuation instrumentation channel trip setpoint less 1 i
conservative than the value shown in the Allowable Values column I of Table 3.3.3-2, declare the channel inoperable until the channel i is restored to OPERABLE status with its trip setpoint adjusted g consistent with the Trip Setpoint value,
- b. With one or more ECCS actuation instrumentation channels 3 inoperable, take the ACTION required by Table 3.3.3-1.
Vc eb y 3 '
- c. With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within:
- 1. 7 days, provided that the HPCI and RCIC systems are OPERABLE, otherwise,
- 2. 72 hours.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours i and reduce reactor steam dome pressure to less than or equal to l 150 psig within the following 24 hours. l SURVEILLANCE REOUTREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK', CHANNEL FUNCTIONAL TEST and , CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the i frequencies shown in Table 4.3.3.1-1. l 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of 11 channels shall be performed at least once per 18 months.* fR35.l.N 4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function ** shall be demonstrated to be within the limit at least once per 18 months. s fu for the diesel generator output breakers: Completion of logic system
. gym j functional testing, for the loss of power function, to positively verify that the breaker reciosure permissive relay ~(52xx) is re-energized by the SI*"M' 3 associated bus load shedding logic contact closing, rather than the 52XX being re-energized by a parallel path, may be deferred and must be completed no later than during the first plant outage after September 29, 1995.
SR 3.5.t.l y **ECCS actuation instrumentation resonnte time need not be measured and may be 1y poTE (assumeg n De the/ design instrpfhentation respodse time) !i
,k ,
v FERMI - UNIT 2 3/4 3 23 Amendment No. Jpp, 195.111 PAGE I 0F 10 8'" 7
j i 59eD Rc,Fnand 5 6 / l [dfso sedpecharne 3.% / ) i REACTOR COOLANT SYSTEM ' sunVEfttANCE RFOUTREMENTS 4.4.1.1.3 Each pump discharge valve shall be demonstrated OP8RAELE by I g 3.Lt.7 cycling once pereach valve through at least one complete cycle of full travel at least} 18 months. ll h.l.1.2 DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in Su operation, at least once per 12 hours verify that: ' See.cdkah%j SSI a. THERMAL POWER is less than or equal to 67.2% of RATED THERMAL POWER, and
- b. The individual recirculation pump flow centroller for the operating recirculation pump is in the Manual mode, and
- c. The speed of the operating recirculation pump is less than y or equal to 754,of rated pump speed.
j 4.4.1.1.4 With one reactor coolant system loop not in operatjon with THERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
/
M \q
- a. Less than or equal to 145"F between reactor vessel steam k"4"gA b.
space coolant and bottom head drain line coolant, and 3.'f. I Less than or equal to 50*F between the reactor coolant
/
within the loop not in operation and the coolant in the reactor pressure vessel **, and
- c. Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the operating loop.**
Al .- ; S ta. Cpec;6ca hm
**Reouirement does not apply when the recirculation loop not ih operation is isolated from the reactor pressure vessel.
3M.c FERMI - UNIT 2 3/440 Amendment No. 53, 69. 87. US.133 M PAGE $ OF 10
r 5P&c.IFicAT104 M. l {hl40 $st Spes\Cce,4,'er. S.c.2) EMERGENCY CORI? C00llNC SYSTEMS LIMITING COND 'T10N FOR OPERAT10N fContinued) ACTION: (Continued)
.3. S'. I _ d. For the ADS: (ADO Ac.nouP/
.2 1.
Mc7 san '3" (HPCI systeaQ Oe~ CSS =dWith N l ec t one of the_ a_bove reanired ADShalve avs*= are OPERABLE, restore the A cyg q inoperaDle ADS valve to OPERABLE status within 16 days or be in at Ac7tod .I . least HOT SHUT 00WN within the next 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours.
/C'TroM I 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTD0WN within 12 hours and reduce reactor steam done pressure.to s 150 psig within the next 24 hours,
- e. / With a CSS h ader AP instrumentation channel inoperable perable, restore bbk annel to OPERABLE status with 72 hours or deters e th CSS head AP lo; ally at least once per hours; otherwise. clare/
l tthe as ciated CSS subsystem inoperab1 f _ Ii . ith an LPCI or 5 system discharge line " keep / filled" alm instrumentatio operable. nerform Surveillante RequiremenL/ [R,)
.5.1.a.l.a.
3
~
(g. the event an tcc5 system is ctuated and injects water into the ~ I actor Coolant System, a Sp tal Report shall be prep d and submitted to the Commissio pursuant to Specification .9.2 within 90 days describing the circ stances of the actuation the total accumulated actuation c les to date. The current alue of the usage factor for each affec d safety injection nozzle all be provided in i . Special Report enever its value exceeds .70 E SURVEILtANCE REQUIREMENTS 4.5.1 The emergency core cooling systems shall be demonstrated OPERABLE by:
- a. At least once per 31 days:
- 1. For the CSS, the LPCI system, and the HPCI system: _ _ _
s g 3 5 1.-3 a) Verifying [by)entino Et the hiah sj.inuent that the system piping from the. pump discharge valve to t e system isciation vai ,e is filled with water. l
'5R3714- b) Verifying that each valve, manual, power operated or automatic, in the flow path that is not lockedi sealed, or otherwise secured in position, is in its correct
- position.
g g g 3,q ,) 6 2. , For the LPCI system, verifying that the ross-tie valve is open. (6/15ESI [iExcept t)tt an autpinatic valve rgpable of automafic return tofts ECCS position g,g,g,4when ar/ECCS standl is presentAay be in positi4n for anothe(mode of operation FERMI . UNIT 2 3/4 5 3 PAGE 5 0F 10 Sgy 7
1 1 1 i ( l
-boca bc4 dien. 5.5 2. {
[if/so see specifiedian B.s'.Q l 1 1
/ I EMERCENCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION Montinuedi ACTIdN: (Continued)
- d. For the ADS:
j ' 1, With one of the above required ADS valves inoperable, provided the HPCI system, the CSS and the LPCI system are OPERABLE, restore the inoperable ADS valve to OPERABLE status within 14 days or be in at l least HOT SalTDOWN within the next 12 hours and reduce reactor steam done pressure to s 150 psig within the next 24 hours.
- 2. With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours and reduce reactor steam dome pressure to s 150 psig within the next 24 hours.
l ' e. With a CSS header AP instrumentation channel inoperable, restore the l g - inoperable channel to OPERABLE status within 72 hours or deterinine the CSS header AP locally at least once per 12 hours; otherwise, declare
*g the associated CSS sut' system inoperable.
gi # 3,6,I f. With an LPCI or CSS system discharge line " keep filled
- alarm instrumentation inoperable, perform Surveillance Requirement 4.5.1.a.1.a.
- g. In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Connission pursuant to Specification 6.g.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in l
l this Special Report whenever its value exceeds 0.70. SVRVElllANCE REOUIREMENTS r 4.5.1 The emergency core cooling systems shall be demonstrated OPERABLE by: (CC. ,
~
"" a. At least once per 31 days:
$yeC[
- 1. For the CSS, the LPCI system, and the HPCI, system M.
a) Verifying [by v/ntina at the Idah noint unt0that the system M 3*b'g'q pipin from the pump discharge valve to'the system isolation valve l is fi led with water. A b) verifying that each valve, manual, power operated or automatic, in 5R 3.5 7,6 the flow path that is ' lot locked, sealed, or otherwise secured in position, is in its correct
- position.
i g ', For the LPCI system, verifying that the cross. tie valve is open. [$,4 2. S Pf,,. 5.1
*Exceptfhatanautomati valve capable of automatfor c return to its [CCS po[ tion another mode of oppration.
when ajt ECCS signal is present may be in positi FERMI - UNIT 2 3/4 5 3 PAGE l OF 08 gev 7
n a . . . .. . . . e
- 4. J'. ..r. . .$ .
. . -. . . . . . u . U... D .L..-
Sp.e cificad io n. 3. 5. 2 l (Als sec speewca-(sn. e. s.O
- 4.1 Eerectury ener con 1HC MYSTEMS SJRVEILLANCE RE 1U1 tEMEN"5 (centinued) l r
4*c.d..g*. g 3. -for the HPCI system, verifying that the HPCI pump flow controller is j g $#c { in the correct position. 3' ' b. Verifying that, when pursuant to Specification 4.0.5: g 2;'g,g* g 11. The two CSS pumps in,_each subsystem together deve_lsp a, flow of at 1 $_t 6350 come]Qhst~a te:M~We p'ressuce.o" arandr ma oradat
- k Mt.N i i FNfgisiiill'n~g to a reacWr~vesse i pressure of a 100 '
psig. ___ i
- 2. Each J.PCI pump in each subsystem develops [ow of at least 10,000 gpe(acaWCTJ61[Ena iWisatref a zJuAsi
~
asponding to a reactor vessel to ori-m i 6am.a t 6 vii i. . ... , ressure of a 20 ' psig. ./O
$CO 3. The HPCI pump develops a flow of at least 5000 gpm in the test flow i path with a system head corresponding to reactor vessel operating
$f *gghof).
3 ,g pressure including injection line losses when steam is being supplied Qotheturbineat 1025 +20. -80 psig.*
- c. At least once per 18 months g.(ud( W" '
- l. For the CSS, the LPCI system. M d the HPCI systeeD performing a GR 3.C.2 7 system functional test which includes,stmulated automatic actuation g l gg of the systas throughout its emergency operating sequence and l .
verifying that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel may be excluded from this test.
- 2. or the HPCI system, verifying that:
a) The system develops a flow of at least 5000 gpm in the test flow l path with a system head corresponding to reactor vessel operating pressure including injection line losses when steam is being supplied to the , turbine at 165 + 50. ,0 psig.* u b) The suction for the HPCI system is automatically transferred from gyCC%{'pf/o the condensate storage tank to the suppression chamber on a
$ *g ,) condensate storage tank water level - low si nal and on a suppression chamDer - water level high signa . j
- 3. Performing a CHANNEL CALIBRATION of the CSS and the LPCI system discharge line ' keep filled" alarm instrumentation.
4 Performing a CHANNEL CAllBRATION of the CSS header AP instrumentation and verifying the setpoint to be s the allowable value of 1.0 psid.
$Cd
. rQ,o./ *The provisions of Specification 4.0.4 are not applicable provided the gfrCil surveillance is performed within 12 hours after reactor steam pressure is
~>; ,6 . I - adequate to perform the test.
FEllMI - UNIT 2 3/454 Amendment No. 87 b c2 PAGE 0F 08 del 7 s P :. (! # , 6 %.:
l l L 68ECi Ac+ Weal 5. f.2. FMFRCENCY CORF cont TE SYETTMS 3/4 5.7 Fres . SHUTDrud A,l l tIMITING CONDITION FOR OPERATION ' / 3.5.2 At least two f the f lowing (subsystemsshallbeOPERABLE: re spray syst (CSS) subsyst with a subsystem rised of: f a. '
- 1. At leas two OPERABLE CS pumps. and
- 2. An OP E flow path apable of taking s tion from at 1 st one f the following ter sources and t nsferring the t Y
~
h I
- - , . u i .. . = = - ' T L.3 ' T When the suppression chamber water level is less than h l 6ft 3,6,2.'E limit required in Specification 3.5.3 or is drained, com the condensate storage tant with an indicated level of at least.19 ft.
I Low essure coolant in,j ion (LPLO system uusy= 6cr. 6.. . L(l su ystem comprised of: At least two OP LE LPCI (RHR) s. and
. An OPERABLE path capable of sking suction from t suppression si2er and transfer ing the water to the/~eactor eta 1**
APPIIrARfITTY: OPERATIONAL CONDITION 4 and $*, ACIlQli: Actroa A _,- Witn one of the tbove required subsystem (s) inoperable, restore at least two subsystem (s) to OPERABLE status within 4 hours or suspend ' l AG## g all operations with a potential for draining the reactor vessel. l ' AcTtod C X ,With Ju='=U:ndboth ofallthe above required operations with a subsystem potential for(s) inoperable, draining the suspen 40Rt
- reactor vessel. Restore at le3st one s nsyntem to OP MABLE 4tatus l
' kG0d g within 4 hours or stabli (SLcDNDARY CNTA NMrMT IWTMRITD%thte
----2 : m- . in;*a . i .,
'--- ach +o ERABLE provided that the ;rt:- = '
ppl%*ggJ 'l -heart-tr The meinerECCStheiscavity is flooded, the not required to spent fuel pool cates are T
,. removed. and water level is maintained within the limits of(S m F. = m 1
.2'O
.rl
'd ".: =: :.:.3
** Ln,1 subsystem (s) may be considered OPERABLE during alionment and operation SR 35.2,6 for decay heat removal if capable of being manually realigned and not l NN otherwise inoperable.
l l FERMI - UNIT 2 3/4 5 6 Amendment No. 226.131 1 3 0F 08 PAGE /fev7
6PECGickno*J 3..& 2-. i (Also 3te Speen(ica% 3.G.2.2b LIMfTING c0NDITION FDR OPERATION 3.5.3 The suppression chamber shall be OPERA 8LE: f
- 4. a. !n OPERATIONAL CONDITIONS 1, 2, and 3 with a contained water volume of LGo 3,6,2.2. <{atleast 121,000 ft', equivalent to a level of 14'4' (-2 inches 44.3 Qadication).
$A 5.s/2.g b. la OpraA"f m m enuntTtnm A and te trHh a A =#I "duduneofftleadO car umaj ,e ^hlent to afevel (9'0" may 55 <nches <n61 cation),
$4 3,5, t.l.a. 'except that the suppression :- -.i be less than the limit or may be drained provided that: W ACTIDAl 6 -h Nooperationsareperformedthathaveapotentialfordraining) h y
r.Fs 3.5.2.2 b Notf the rtacter vessel actor switch is ked in the 5 downorpdu}e f/( 3,5,2.'7. . b A The condensate storage tank water level is at least 19 ft., and
-4. The core spray system is OPERABLE per Specification 3.5.2 with g g'g*1 an OPERABLE flow path capable of taking suction from the 4 g 3,g ,2 ,') , 6 condensate storace tank ana u .ii. 1, inu uw 6 i snur auray Epaitsi Ao the re86 tor ves . /
/1.
APPLICABILITY: OPERATIONAL CONDITIONS @ 2, 3h4, and 5*} Eng: k O E*G'2*L l L(D B5,*1. . \
- a. n OPERATIONAL CONDITION 1. 2, or 3 with the suppression chamber water level less than the above limit, restore the water level to within the 4to 3 4 '2. 2. N I@rslimit and within in CDLDI SHUTDOWN hour or bewinthin 4bowsG at the.4 following 24 leastICSS rs. HOT ancst)SHUTDOWN d.
- b. In OPERATIONAL CONDITION or 5' with the suppression chamber water
/} con) C., O level less than the above limit or rained and iw above reovired )
conditions not satisfied, suspend wn AutRATIDG andlall operations - that have a potential for draining the reactor vesse' : ' ': _ ' "" lF r n;t:- - ' :-it:5 i: # ; St:tt r ..... %.; EstaF ish SECONDARY CONTAtaserNT INTKGRIlY= :-- : nrgg li Criifiak che En hV
. 'The suncretnian e"*-r is not required to be OPERASLE provided that the '
dyactor vessel head is removRDthe cavity is flooded, or being flooded N Igd' ; from the suppression pool, the spent fuel pool gates are .. - .. wnen Ine cavity is flooded. and the water level is maintained within the limits of (Specifications J.p.5 and 3W ' l FERMI - UNIT 2 3/4 5-8 Amendment No.131
,,/'
PAGE 5' 0F 08 Rev 7 .
, . . . ~ . . ..,. . .
. . . . . .a SPEctPrcA-nord 54 (
PLANT SYSTEMS A80 Sg6/Icc I hCdbh-3,7 )
.. ENERGENCY EDUfPMENT COOLING WATER SYSTEM Al506/-(I0&dhdob*vh8' f
LIMITING CONDITION FOR OPERATION 3.7.1.27wo independent emergency equipment cooling water (EECW) system subsystems shall be OFERABLE with each subsystem comprised of:
- p. 6cag, 'a. One OPERABLE EECW pump, and ge(;9 b. An OPERABLE flow path capable of removing heat from the assot.iated 3 safety related equipment.
APPLICABILITY: OPERATIONAL CONDIT!DNS 1. 2. 3, 4, and 5. ACTION: L
- a. In OPERATIONAL CONDITION 1, 2 or 3, with one EECW system subsystem
, A operable:
5a I
- 1. Within 2 hours:
g.g.g 68 L l a) Verify that all required systems, subsystems, trains, l ((s, components and devices that depend upon the remaining OPERABL? EECW system subsystem are also OPERABLE, and ACTtos tt - (I b) Verify that M s OPERABLE. /_. Z Otherwise", be in at least H0T SHUTDOWti within the next 12 hours
! 5g and in COLD SHUT 00WN within the following 24 hours. l i
( 5 ptcikc d h .
\ J,7 2. Declare the associated safety-related equipment inoperable and take the ACTIONS required by the applicable Specifications.
Acr7eg C. 3. Restore h =; r:bh EEC" :Ut M ubsystem to OPERABLE status witnin iz nours or be in at least HOT SHUT 00WN within A CT70M O the next 12 hours and in COLD SHUTDOWN within the following 24 hours. r
- b. I In OPERATIONAL CONDITION 4 or 5, determine the OPERABILITY of the I safety-related equipment associated with an inoperable EECW system
$feci b han subsystem and take any ACTIONS required by the applicable 37 Specifications.
A.
'YI(;gW[;h/ ADS
/ thanis or notequal requiredto 150 to be OPERABLE when reactor steam dome pressure is less PSIG.
"Except for an inoperable Drywell Cooling Unit, required by Specification 4th y 3.7.11 or.an inoperable primary containment oxygen monitoring instrumentation
.Q(A channel, required by Specification 3.3.7 S. that depends ^,n the remaining giu OPERABLE EECW system subsystem. In these cases, take the ACTION required by ,
pJ h Specification 3.7.11 for the inoperability of both required Drywell Cooling Units or Specification 3.3.7.5 for the inoperability of both required primary ' containment oxygen monitoring instrumentation channels. ! FERMI - UNIT 2 3/4 7 3 Amendment No. # , M ,132 PAGE f 0F 10 gev 7
, s . .4 .
(; , I' l 1 G PectF r eertvu 52.l , 9f G6 REmov5D l Y. SEV l l l l l . 1 l i l l \ i l l
~
.5 l4- 7-3
/
l PAGE OF 08 %7 L
SPET 1 FiCkrtaN 3,Tr. 2 k e no ess 7 4 I i 3/47-5 PAGE / OF 02 ggv 7 i
1 l SPECI'=lCkTroM 3 E l \ ! .3 /4 . 8 ELECTRICAL POWER SYSTEMS [AlsoSu he b b 5-I3) 3/4.8.1 A.C. SOURCES A.C. SOURCES - OPERATING f,f ) LIMITING CONDITION FOR OPERATION LLO 3.8 As a minimum, the following A.C. electrical power sources shall be OPE :
- a. Two p..;mmi ind: pend:nt circuits between the offsite l
transmission network and the onsite Class IE distribution system, and LA.l
- b. Two se ate and A depende onsite A.f4 electrical power / sour y ,
Div sion I and E_ivision ,[each consisting of two emergency dieselgeneratorsteac diesel generator wu,rg 64 3,$.l Y 1. A separate day fuel tank containing a minimum of 210 gallons _ of fuel, f g ) 2. A separate fuel storage system containing a minimum of
\ f y, g. 3
[ 35,280 gallons of fuel, and
. A .ip:re.tc N:1 tr:r, m r ; r;. (p -
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACTION:
- a. With one or both offsite circuits of the above required A.C.
kc.g C electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; . demonst te the OPERABI Y of the remain a . t. . sources Dy 3 perfo ing Surveillan jit Requirement ast once per 8 ours thereafter dy 4.8 .l.1.withinonegourandJ MD A kb. With one or both diesel generators in one of the above required onsite A.C. electrical power divisions inoperable; Demonstrate the OPERABILITY of the remaining A.C. sources by b
'l kt h) 1. ' -
performing Surveillance Requirement 4.8.1.1.1 within one l, hour and at least once per 8 hours thereafte pr na if he idie generator (s ~ ecame inoperao aue to any ca eot]er h g i th an inoperabl support system, independenti testable ' mponent, or o lanned preventi maintenance testina.1 4 i Iperforming Surveillance Requirement 4.8.1.1.2.a.4 for one Ref cb Ad.2. ll diesel generator at a time within 24 hours, unless the O c 4 g 'I absence of any potential common mode failure for the / 4.2 \ 1 remaining diesel generators is determined, and lg FERMI UNIT 2 3/4 8-1 Amendment No. pp,119 PAGE L OF 08 BV 7
.3/4.8 ELECTRICAL POWER SYSTEMS S PE(-IFt cA17orJ E9 3 i 3/4.8.1 A.C. SOURCES [ 4 /50 4 Q tM h 82 N O M 8.8.l )
A.C. SOURCES - OPERATING { A.I ' LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power-sourcer shall be OPERABLE: Two physically indeoendent circuits between the offsite transmission network and the onsite Class IE distribution system, ! Su and
- bg I
Two separate and independent onsite A.C. electrical power sources, Division I and Division II, each consisting of two emergency diesel generators, each diesel generator with:
- 1. A separate day fuel tank containing a minimum of 210 gallons t of fuel, gR 3.g,3,1 2. A separate fuel storage system containing a minimum of {,l 35,280 gallons of fuel, and habLCO3.3,3
- 3. A separate tuei transfer pump
/)fgicabilip PPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. M@S CTION:
With one or both offsite circuits of the above required A.C. electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1. within one hour and at least once per 8 hours thereafter and, g . With one or both diesel generators in one of the above required g.g onsite A.C. electrical power divisions inoperable; f,$ .l 1. Demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours thereafter, and if the diesel generator (s) became inoperable due to any cause other , than an inoperable support system, an independently testable ' component, or preplanned preventive maintenance or testing, by performing Surveillance Requirement 4.8.1.1.2.a.4 for one i diesel generator at a time within 24 hours, unless the aosence of any potential common mode failure for the remaining diesel generators is determined, and FERMI UNIT 2 3/4 8-1 Amendment No, pp,119 PAGE / OF 05 ev7 ,
~_
SPece conou 3.g.: ElFCTRICAL POWER SYST MS t1MITING CONDITION FOR OPERATION (Continued) ACTION (Continued) verify within a nours and at least once ar B hours A R T AaA32. thereafter, that CTG 11 1 15 OPERABLE. testore the fee Ae t 44 inoperable division to OPERABLE status within 7 days or be 19 F in at least HOT SHUTDOWN within the next 12 hours and in Ac770N C COLD SHUTDOWN within the following 24 hours. -
- 3. requirements f ACTION b.2. a!
rIf t be , either re re the inoperab'e)dve for CTG 11-1Aannot) divisiontoOP/RABLEj g,sta within 72 esRnot to exceuo I osys nw uw use Rap Ad 4 6 lthe~ division becdme inoperable): or, satisfy the
, ',!Irequirements of ACTION ).2 above within 72 hours and restore L.
RegAd AS ', lthe inoperable division to OPERABLE status within 7 daysfrom th least HOT SHUTDOWN within the next 12 hours and in COLD k ANg f)lSHUTDOWN within the following 24 h - y- __ ___
- c. With one or both diesel generators i one f the above required onsite A.C. electrical power divi 1 inoperable. in addition toi \
Ac,t A,2 ' ACTION b above, verify within hours that all required systems Ru/ subrystems, trains. components and devices
- that depend on the L,'2 remaining onsite A.C. electrical power division as a source of emeroency power are also OPERABLE: . wise. oe in at least wi ,
g wgn n m ljtnours g inCOLDSlyTDOWNwithi th3
/ (McLedwe reduk4- h4vn ijsep)
~
d With both of the above required onsite A.C. electrical power ALTiod b . divisions inoperable:
- 1. Demonstrate the OPERABILITY of the remaining A.C. sources by !
def M 4'I performing Surveillance Requirement 4.8.1.1.1 within one l F- hour and at least once per 8 hours thereafter: and , h Acj 6,/ 2. Restore at least one of the above required inoperable 7 - divisions to OPERABLE status within 2 hours or be in at least HOT SHUTDOWN within the next 12 hours'and in COLD Mod C SHUTDOWN within the following 24 hours; and a3 Restore the second of the above required divisions to OPERABLE status within the time required by Action b above
% M n'b . frc;: the time of initial loss or be in at least HOT SHUTDOWN MfDPJC. within the r.ert 12 hours and in COLD SHUTDOWN within the ,
following 24 hours. j
- l
*Except for an ino rable primary containment oxygen monitoring l M instrumentation c nnel, required by Specification 3.3.7.5. that 'entis on
.%- the remaining OPERABLE onsite A.C. electrical power division. In is case. take the ACTION required by Specification 3.3.7.5 for the inoperability of [v l both required primary containment oxygen monitoring instrumentation channels. FERMI - UNIT 2 3/4 8 2 Amendment No. 119. 132 i PAGE S OF 08 g7 l l
l SPEllFicWrland 3 ? l ELECTRICAL POWER SYSTEMS 0 S R h iY '(4 b 8. SURVElllANCE RE00fREMENTS g y*j, f .6.i.i.c Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be , determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability. Each of the above required diesel generators shall be demonstrat
- a. At least once per 31 days p : .:rs:x= = ??I" by: l SR 5.3.1. 9 1. Verifying the fuel level in the day fuel tank.
(5.4.5P ecifitagg,g3g2. ferifyingthefuellevelinthefuelstoragetank. g g 'j' g 3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the_ day fuel tank. TR 3 r
- I* 7 319 4. verifying the diesel starts t condition and accelerates to at leastL900 romlin less than or equal to SR 3*1*1'1 10 seconds.* Theegenerator voltage and frequenc 4 4160 s 4ZD volts and 60 a 1.2 Hz Mth'- "' - - y shall be !
/ t :f':- " _lL
. -* irt : t :'. . _f ih aisses 3.o res snas pu st so to Il r sni test oy usi one of the fo owing signal :
1 a Manual, Simula d loss-of-offs e power by i elf. g,g g i c) Simul ed loss-of-off te power in njunction ith an l ESF tuation test gnal. d)__ An F actuation t t signal by i elf. - I s,R 3,g ),3 5. Verifying the diesel generator is synchronized. loaded to
; Lreater than or equal to an indicated 2500 2600 kW in I . . g ,q t --- s a accordance with the manufacturer's recommendations, and i operates wi
%DD Nok 2 is load for at least 60 minutes.
foe NON. 3 f. 3 t ?SNN;);;iltirr""-4 @rC* ='=^' * (Su $pe(A4cdon 3 3.'5)F7. Verifying the pressure in all diesel generator air start sat..2.na.q'-<.a.u m.-,,,em,q;,mt.a;4 u receivers to be greater th Sit F.R I."1 ##k SR F.31.l4 dok 2-)YAll diesel generator starts for the purpose of this Surveillance Requirement I@ may As preceded by an engine prelube period. The diesel generatar start 14 3.5 l.7 (10 see) from ambient conditions shall be perforised at least onca JDer __of the purpose 184 inis days sw in these surveillance w.iisance testine may betests. Tallbyother preceded other engine warmue sta:T.s for q { SE3*I*b%- ' Q# ear gthe dieselnrecedures}ecosamenceafy the manufacturg so tpet the mecyhnical GI V stress aptO fMok 3 enprne is minimized.( -
- Y 4
FERMI - UNIT 2 3/4 8 3 Amendment No. JJ,107 d 0F PAGE 08 g,, 7
L 1 l l 4 SP w Fickn k 3 2.3 ELECTRICAL POWCR SYSTEMS ' SURVElllANCE RE0UIREMENTS
.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class IE distribution system shall be determined OPERA 8LE at least once per 7 days by verifying correct breaker alignments and indicated power availability.
4.8.1.1.2 Each of the above required diesel generators shall be demonstrated l QPERABLE-Se4 . a. At least once per 31 days hnMAGGERJJffEST BASI 5j6y: ' >,1 Spati M* + l St 3,g,g ( 1. Verifying the fuel Tever in the day fusi tank.". . **., T gl 2. Verifying the fuel level in the fuel storage tank.ll' [3. Verifying the fuel transfer pump starts and transfers fuel i from the storage system to the day fuel tank. I
- 4. Verifying the diesel starts from ambient condition and l accelerates to at least 900 rps in less than or equal to i 10 seconds.* The generator voltage and frequency shall be 4160 a 420 volts and 60 a 1.2 Hz within 10 seconds after the i start signal. The diesel generator shall be started for ;
this test by using one of the following signals: SeL a) Hanua1. l Qadf;aM. b) Simulated loss-of-offsite power by itself. c) Simulated Icss-of-offsite power in conjunction with an
>T. I ESF actuation test signal, d) An ESF actuation test signal by itself.
- 5. Verifying the diesel generator is synchronized, loaded to i greater than or equal to an indicated 2500 2600 kW in '
accordance with the manufacturer's recommendations, and operates with this lead for at least 60 minutes. 6. Verifying the diese1' generator is aligned to provide standby power to the associated emergency busses.
- 7. Verifying the pressure in all diesel generator air start 6 A 3. 7. 3,.3 m receivers to be greater than or equal to 215 psig.
FA11 diesel generator starts for the purpose of this Surveillance Requirement g" \ may h preceded by an engine prelube period. The diesel generatar start (10 sec) from ambient ' conditions shall be performed at least gec$tak- onca per 184 days in these surveillance tests. All other engine starts for 39*g the purpose of this surveillance testing may be preced'i by other warmup procedures recommended by the manufacturer so that the Achanical stress and wear on the diesel engine is minimized. C FERMI - UNIT 2 3/4 8 3 ' Amendment No. JJ.107
.J PAGE e2 0F 05 jp,g 7 t
b
9 EClP7chT2 bro 2.7 3
/](so .% SfecdScnfim 5.T.1.) , ELECTRICAL POWER SYSTEMS g[bo ICL 6 /6CI "C8 l'IM f' )
SURV[IllaNCE pE00fpFMENTS (Continued)
- b. By removing accumulated water:
fsL 3.3.l\ 1. QttiHegfM From the day tank at least once per 31 days and after each
/ occasion when the diesel is operated for greater than I hour, and SM 3 2,3,[ 2. From the storage tank at least once per 31 days.
F By sampling new fuel oil in accordance with ASTM D4057-88 prior to MId* ' ' ., c . addition to the storage tanks and: {k i l g 'g - 1. By verifying in accordance with the tests specified in ASTM D975 91 prior to addition to the storage tanks that the i l
- -sample has.
( se<.5'Cscab- a) An API Gravity of within 0 3 degrees at 60*F or a P specific gravity of within 0.0016 at 60/60'F, when f.E compared to the supplier's certificate or an absolute specific gravity at 60/60'F of greater than or equal i to 0.83 but less than or equal to 0.89 or an API 1 gravity at 60'F of greater than or equal to 27 degrees but less than or equal to 39 degrees, b) A kinematic viscosity at 40'C of greater than or equal l to 1.9 centistokes, but less than or equal to ; 4.1 centistokes, if gravity was not determined by ; comparison with the supplier's certification. ' c) A flash point equal to or greater than 325'F, and l d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176 66.
- 2. By verifying within 31 days of obtaining the sample that the other properties specified in Tabla 1 of ASTM D975 91 are met when tested in accordance with ASTM D975 91.
- d. At least once every 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2276 88, and verifying that total particulate contamination is less than 10 mg/ liter when Mharted in accordance with ASTM D2276 88, Method A.
(e. At least once per 18 months by: l M 1. Subjecting the diesel to an inspection in accordance with Qecj(icahd y procedures prepared in conjunction with its manufacturer's reconsnendations for this class of standby service.
- FEPJil - UNIT 2 3/4 B-4 Amenoment No. # , 95 PAGE 3 0F 05 Re 7
- 3:
bPEG lF ICAT1otJ 3. 2.3 Ako Su. spwRca+;qe 3.g.\) ELECTRICAL POWER SYSTEMS , SURVFillANCF REOUTREMENTS (Continued) M
- f. At least once per 10 years or infter any modifications whien could affect diesel generator interdependence by starting all four Spe.cS6Ng diesel enerators simultaneously, during shutdown, and verifying 3* g' g that al four diesel generators accelerate to at least 900 rps in 1
less than or equal to 10 seconas. Al i< a .,;.;; ;;r ^ ;;,r; 5;;: / 4*/ 1 Draining a fuel oil stora tank, removing a accumula sed =a h u.. . . a . .. ..,iment and c aning the tank f :.r;
,,_....a... ....u...-...
$ 4. 2. Performing a pressure test of those portions of the diesel Spcib b fuel oil system designed to section !!I. subsection no of 3, g, l the ASME Code in accordance with ASME Code Section 11 i Article IWD 5000.
1 (4,. 8.1.1. 3 Reeerts - Not Used l l l l l l 1 i i l FERMI - UNIT 2 3/4 B-7
- Amendmnent No.107 PAGE OF 05,
&v7 L !
r
]
i ELECTR1 CAL POWER SYSTEHS 3/4.8.2 D.C. SOURCES Qgc I ft (A TID'J 33'Io D.C. SOURCES - OPERATING g g.f. g g g,g q {Afso Set .SpeciflOa fidrs 3. ? 2b LIMITING CONDITION FOR OPERATION i (3.8.2.1 As a minimum, the following D.C. electrical power sources shall be ! OPERABLE: a . .. Division 1. consisting of: {
- 1. 130 VDC Battery 2A-1. i
- 2. 130 VDC Battery 2A-2.
- 3. Two 130 VDC full. capacity chargers.
- b. Division 11, consisting of:
,1. 130 VDC Battery 28-1.
- 2. 130 VDC Battery 28-2.
! 3. Two 130 VDC full capacity chargers. ApptfCABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
. gd' ACTION:
1 .QP 8Aw. a
\h I
With a battery charger in either Division I or Division II of the above D.C. electrical power sources inoperable, restore the inoperable battery charger to OPERABLE status or replace with the spare battery charger within in COLD4SHUTDOWN hours or be in the within at following least HOT SHUTDOWN within the next 12 hours 24 hours. b. With either Division I or Division II of the above required D.C. electrical power sources otherwise inoperable restore the inoperable division to OPERABLE status within 2 hours or,be in at least HOT SHUTDOWN hours.#within the' next 12 hours and in COLD SHUTDOWN within the following 24 SURVEftlANCF REOUTREMENTS 4.8.2.1 tdemonstrated OPERABLE: /Each of the above required 130-volt batteries and char a. At least once per 7 days by verifying that: 5 A 3.3.t.. l 1. The and parameters in Table 4.B.2.1-1 meet the Category A limits, S te. - s pG kea km y.s. volts for Division I and greater than or equal to '125.7 vo for nivision 11 on float charge.
- b. 2Ll how.S3; l At least once per 92 dals/and within 7 s La er
[,\ [di~scTarge ' wit _h 5atTe_ry terminal volta tery N b 8 i attery overcharge with battery terminal voltageathan105 volts,orh gg r ijo 1 and greater than 145 volt eater than 150r Division II, y I l 6A 3.f.0,1 1. %_fw sa3.s+.O L. l The parameters in Table 4.8.2.1-1 meet the Category B limits,
, 1 i
- 1 lhis ACTION may be delayed for up to 16 hours for battery 3.7.1.2 are taken.
FER(MI-UNIT 2M IpebNm 37.2)
~
3/4 B.10 Amendment No. 80,121 PAGE 1 ._ QF 03 R" 7
1 I SPEO nen erJ 3. E 7 ELECTRICAL POWEp SYSTEMS p,l AISo sex Spuificak, s. g. j ) l 3/4 8 3 ONSITE POWER DISTRIBUTION SYSTEMS g g g ; f,.cg,g, 3,7, t} D15"R BUTION - OPERATING L"M T NG CONDITION FOR OPERATION l.00 -3.2.3.1 1he following power distribution system divisions and busses shall be 3 50 enero>ceop,itivise creakeos open b,(ween reoumeant busses witnin we unip pj
- a. A.C. power distribution:
- 1. Division I, s i s t i na__ o f- -
-}
a) 4160V HR mple sses 11EA and 12EB. b) 4160V R ter Bu Busses 648 and 64C. c) 480V Ccmply usses 72EA and 72EB. d) 480V eactor Fu Busses 72B and 72C. i e) 120V Division U Powpt Supp/y unrU MPU l. I
- 2. Division !!, nsisting of:/
a) 4160V mpiex susses 13EC and 14ED. b) 4160 Re ter Bu Busses 65E and 65F. c) 480V R Comple usses 72EC and 72ED. d) 480V actor i Busses 72E and_72F. 4 e) 120V Division 1111_& rower suppiy # nit) MPU 2. I
'h y, V
- b. D.C. power distribution:
- 1. Division 1, consisting of: I a) 130 volt D.C. Distribution Cabinet 2PA 2.
b) 260 volt D.C. MCC 2PA 1.
- 2. Division 11, consisting of: i a) 130 volt D.C. Distribution Cabinet 2PB-2. !
b) 260 volt D.C. MCC 2PB 1. APPLICABillTY: OPERATIONAL CONDITIONS 1, 2, and 3. \ 60: A cT10^l D J ,' l ACTION: -oLNC _ l a. With one of the above required A.C. distribution s_ystem division N fb A NCMDd g not energized, reenergize the division withinlB'60urs' or be in at l least HOT SHUTDOWN within the next 12 hours and'Tn' COLD SHUTDOWN i l /lCT70tdC within the fo 24 hours.' L,) i i g_rne(f, *
- b. With one of The above required D.C. distribution system divisions N ON b not energized, reenergize the division withint[6oTSs~ lor be in at ACTioA) C least HOT SHUTDOWN within the next 12 hours and in~16LD SHUTDOWN within the following 24 hours,
- c. [ With the swing bus not energized or the swing bus automatic I i'4 / throwover scheme inoperable, declare both low pressure coolant -
Sec'efice hirr 55.l 1 injection (LPCI) system subsystems inoperable and take the ACTION
< required by Specification 3.5.1. / g j'coponentsThis ACTION may l < m made inoperable duebete delayed loss of EECW for upcooling to 16 provided hours fortheA.C. distribution ACTIONS of system I */M. M.
3,7 2.
) Specification 3.7.1.2aretaken.
i l g FERMI - UNIT 2 3/4 8 14 Amendment No. 29, 80 s l PAGE < OF 02 gg7
O C/ /C.Q f /0 [L * . - CAlso =ee specWictison ? a 8) FtECTRICAL POWER SYSTEMS ' CC"C .
$URVEf tLANCE pf001REMENTS /
crecScdo.ch 38.8} Sp' 3.5.2.3 4 .a.3.2. t least th aboverecuiradpoussdistributionsystemdivisions)and the swing bus shals ce outermined energized at least once per 7 days by ' 'l verifying correct breaker alignment and voltage on the busses / cabinets, f4.8.3. 2 The A.C. power distriovita system swt g bus automatic throw sch shall be demonstr ted OPERABLE at least ce per 31 days by man 11y * [f3 ope og position 3C bu 72C and verifying tha he automatic transfer scheme , ates. , , l I l i l FERM] . UNIT 2 3/4 B-15a Amenoment No. 29 PAGE 2T OF 08
n ; l INSERT THIS PAGE IN FRONT OF VOLUME 12 Volume 12: IMPROVED TECHNICAL SPECIFICATIONS l Remove Replace 3.5.1 ITS pg 3.5-3 Rev 0 3.5.1 ITS pg 3.5-3 Rev 7 j 3.5.1 ITS pg 3.5-4 Rev 0 3.5.1 ITS pg 3.5-4 Rev 7 3.5.1 ITS pg 3.5-5 Rev 0 3.5.1 ITS pg 3.5-5 Rev 7 3.5.1 ITS pg 3.5-6 Rev 0 3.5.1 ITS pg 3.5-6 Rev 7 ! 3.5.1 ITS pg 3.5-7 Rev 0 3.5.1 ITS pg 3.5-7 Rev 7 3.5.1 ITS pg 3.5-8 Rev 0 3.5.2 ITS pg 3.5-8 Rev 7 3.5.2 ITS pg 3.5-9 Rev 0 3.5.2 ITS pg 3.5-9 Rev 7 l 1 l 3.5.2 ITS pg 3.5-10 Rev 0 3.5.2 ITS pg 3.5-10 Rev 7 ' 3.5.2 ITS pg 3.5-11 Rev 0 3.5.2 ITS pg 3.5-11 Rev 7 l 3.5.2 ITS pg 3.5 12 Rev 0 3.5.3 ITS pg 3.5-12 Rev 7 j 3.5.3 ITS pg 3.5-13 Rev 0 3.5.3 ITS pg 3.5-13 Rev 7 3.5.3 ITS pg 3.5-14 Rev 0 3.5.3 ITS pg 3.5-14 Rev 7 3.5.3 ITS pg 3.5-15 Rev 0 -- 3.8.1 ITS pg 3.8-1 Rev 0 3.8.1 ITS pg 3.8-1 Rev 7 3.8.1 ITS pg 3.8-2 Rev 0 3.8.1 ITS pg 3.8-2 Rev 7 l l 3.8.1 ITS pg 3.8-3 Rev 0 3.8.1 ITS pg 3.8-3 Rev 7 3.8.1 ITS pg 3.8-4 Rev 0 3.8.1 ITS pg 3.8-4 Rev 7 3.8.1 ITS pg 3.8-6 Rev 0 3.8.1 ITS pg 3.8-6 Rev 7 l 3.8.3 ITS pg 3.8-13 Rev 0 3.8.3 ITS pg 3.8-13 Rev 7 3.8.3 ITS pg 3.8-14 Rev 0 3.8.3 ITS pg 3.8-14 Rev 7 3.8.3 ITS pg 3.8-15 Rev 0 3.8 3 ITS pg 3.8-15 Rev 7 3.8.4 ITS pg 3.8-17 Rev 1 3.8.4 ITS pg 3.8-17 Rev 7 3.8.6 ITS pg 3.8-22 Rev 0 3.8.6 ITS pg 3.8 22 Rev 7 3.8.6 ITS pg 3.8-23 Rev 0 3.8.6 ITS pg 3.8-23 Rev 7 3.8.7 ITS pg 3.8-26 Rev 0 3.8.7 ITS pg 3.8-26 Rev 7 1 1 Rev 7 06/18/99
ECCS-Operating l 3.5.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME H. One ADS valve H.1 Restore ADS valve to 72 hours inoperable. OPERABLE status. SNQ gg D Condition A or . H.2 Restore low pressure 72 hours A Condition B entered. ECCS injection / spray
-4 subsystem (s) to OPERABLE status.
I. Two or more ADS valves I.1 Be in MODE 3. 12 hours inocerable. AN_Q DB I.2 Reduce reactor steam 36 hours Required Action and dome pressure to associated Completion 5 150 psig. Time of Condition E. F. G. or H not met. J. Two or more low J .1 -' Enter LC0 3.0.3. Immediately pressure ECCS injection / spray ; subsystems ino)erable ; for reasons otwr than i Condition B or C. ! 08 HPCI System and one or mort ADS valves
' inoperable.
k Condition C and Condition G entered. . l FERMI UNIT 2 3.5 3 Revision 7 06/18/99
l ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE- FREQUENCY SR 3.5.1.1 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. SR 3.5.1.2 - ------ -
- - - NOTE --- - - --- -
When LPCI is placed in an inoperable status solely for performance of this SR. or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG 12 being paralleled to the bus for required testing, entry into Conditions and Required Actions
'Y l may be delayed up to 12 hours for completion of the required testing.
Perform a functional test of the LPCI swing 31 days bus automatic throwover scheme. SR 3.5.1.3 Verify for each ECCS injection / spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve. (continued) l FERMI - UNIT 2 3.5 4 Revision 7 06/18/99
i i l ECCS -Operating l 3.5.1 l i SURv tILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY l SR 3.5.1.4 ---- --- ---
----NOTE------- - - -------- l Low pressure coolant injection (LPCI) l
- subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3. and for 4 hours after exceeding the RFR cut in permissive pressure in MODE 3.
if capable of being manually realigned and not otherwise inoperable. Verify each ECCS injection / spray subsystem 31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. SR 3.5.1.5 Verify primary containment pneumatic supply 31 days pressure is = 75 psig. SR 3.5.1.6 Verify the RHR System power operated cross 31 days tie valve is open. SR 3.5.1.7 04l Verify each recirculation pump discharge valve cycles through one complete cycle of 18 months full travel or is de energized in the closed position. (continued) i j FERMI UNIT 2 3.5 5 Revision 7. 06/18/99 I j
I 1 l l ECCS- Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR. 3.5.1.6 Verify the following ECCS pumps develop the In.accordance specified flow rate against a system head with the corresponding to the specified reactor Inservice ! pressure. Testing j SYSTEM HEAD Program N0. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray a 6350 gpm 2 = 100 psig LPCI = 10.000 gpm 1 a 20 psig
.SR 3.5.1.9 - -- ------- -
NOTE- - ---- - --- Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify with reactor pressure 51045 and In accordance a 945 psig, the HPCI pump can develop a with the flow rate a 5000 gpm against a system head Inservice corresponding to reactor pressure. Testing Program i SR 3.5.1.10 - --- -- NOTE- --- ---- - - Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify with reactor pressure s 215 psig. 18 months the HPCI pump can develop a flow rate a 5000 gpm against a system head corresponding to reactor pressure. (continued) a g l FERMI - UNIT 2 3.5-6 Revision 7 06/18/99
ECCS -Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.5.1.11- -
- . -. - - - NOTE- --- - -- - --- -
Vessel injection / spray may be excluded. Verify each ECCS injection / spray subsystem 18 months actuates on an actual or-simulated automatic initiation signal. SR 3.5.1.12 -- .-
- .. - - - NOTE - ---- - - -
Valve actuation may be excluded. Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal. SR 3.5.1.13 - -------- NOTE - ----- -- -- - Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test. Verify each ADS valve opens when manually 18 months actuated. SR'3.5.1.14 '- - .
-NOTE- -- - - - -- -
ECCS instrumentation response times are not required to be measured. Verify ECCS RESPONSE TIME.is within limits. 18 months J
)! FERMI UNIT 2 3.5 7 Revision 7 06/18/99
. 1 ECCS-Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2' ECCS-Shutdown LCO 3.5.2 Two low pressure ECCS. injection / spray subsystems shall be .
OPERABLE. l APPLICABILITY: MODE 4 MODE 5. except with the spent fuel storage pool gates i removed and water level = 20 *t 6 inches over the top of ' the reactor pressure vessel i nge. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l A. One required ECCS A.1 Restore required ECCS 4 hours injection / spray injection / spray subsystem inoperable. subsystem to OPERABLE status. B. Required Action and 8.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not' met. draining the reactor vessel (0PDRVs). C. Two required ECCS C.1 Initiate action to Immediately injection / spray suspend OPDRVs. subsystems inoperable. ANQ C.2 Restore one ECCS 4 hours injection / spray subsystem to OPERABLE status. (continued) hlFERMIUNIT2 3.5 8 Revision 7. 06/18/99
( ECCS-Shutdown 3.5.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary ! Completion Time net containment to , i met. OPERABLE status. M D.2 Initiate action to Immediately restore one standby l gas treatment I subsystem to OPERABLE status. m D.3 Initiate action to Immediately restore isolation ! capability in each required secondary containment
' penetration flow path not isolated.
i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify for each re 12 hours
. coolant injection (quired LPCI) low pressure subsystem, the suppression pool water level is a -66 inches.
(continued) h l FERMI UNIT 2 3.5-9 Revision 7 06/18/99
ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued) SURSEILLANCE FREQUENCY SR 3.5.2.2 Verify. for each required core spray (CS) 12 hours subsystem, the:
- a. Suppression pool water level is
= 66 inches: or
- b. - ---- -- ---- --NOTE- - - ----------
Only one required CS subsystem may take credit for this option during OPDRVs. i Condensate storage tank water level is l = 19 ft. l I SR 3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus. I SR 3.5.2.4 Verify, for each required ECCS injection / 31 days spray subsystem. the piping is filled with water from the pump discharge valve to the injection valve. 1 (continued) l FERMI UNIT 2 3.5 10 Revision 7 06/18/99
n , 1 i ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.5.2.5 - ---
--- NOTE- - - - --
OA-l LPCI subsystem (s) may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. Verify each required ECCS injection / spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. Ogl SR 3.5.2.6 Verify each required ECCS pump develo)s the specified flow rate against a system lead In accordance with the corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program N0. CORRESPONDING 0F TO A REACTOR SYSTEM FLOW RATE Pt)MPS PRESSURE OF CS = 6350 gpm 2 = 100 psig LPCI = 10.000 gpm 1 = 20 psig SR 3.5.2.7 : - -- NOTE-- -- -- -- - Vessel injection / spray may be excluded. Verify each required ECCS injection / spray 18 months subsystem actuates on an actual or simulated automatic initiation signal. l FERMI - UNIT 2 3.5 11 Revision 7. 06/18/99
i RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING ' l (RCIC) SYSTEM 3.5.3 RCIC System LC0 3.5.3 .The RCIC-System shall be OPERABLE. APPLICABILITY: MODE 1. MODES 2 and 3 with reactor steam dome pressure > 150 psig. ACTIONS CONDITION ' REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant 1 Injection System is l OPERABLE. 8N_Q A.2 Restore RCIC System 14 days to OPERABLE status. B. Required Action and B.1- Be in MODE 3. 12 hours associated Completion Time not met. 6NQ B.2 Reduce reactor steam 36 hours i dome pressure to s 150 psig. 4 l- FERMI - UNIT 2 3.5 12 Revision 7 06/18/99
n L 1 l RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS , 1 SURVEILLANCE FRE0VENCY l SR 3.5.3.1. Verify the RCIC System piping is filled 31 days l with water from the pump discharge valve to the injection valve. . SR 3.5.3.2 . Verify each RCIC System manual._ power 31 days operated, and automatic valve 'in the flow path. that is not locked, sealed, or otherwise secured in position, is in the correct position. l SR ~3.5.3.3
-- - - - -- - NOTE ------- --
'Not required to be performed until 12 hours
' after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 1045 psig 92 days and a 945 psig. the RCIC pump can develop a flov rate = 600 gpm against a system head-cor p;onding to reactor pressure. SR 3.5.3.4 - - -
- NOTE---- - - - --- -
Not. required to be performed until 12 hours aft.er reactor steam pressure and flow are adequate to perform the test. Verify,' with reactor pressure s 200 psig. 18 months the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure. (continued)
/PJ' FERMI--UNIT;2 3.5 13- Revision 7 06/18/99 l
t RCIC System l 3.5.3 1 l SURVEILLANCE REQUIREMENTS '(continued) 1 SURVEILLANCE , FREQUENCY l e SR 3.5.3.5 - -- - --
- - - NOTE ---- --- - ---- --
Vessel injection may be excluded.
~
l l Verify the RCIC System actuates on an 18 months actual or simulated automatic initiation signal . i t 4 l l l a l l l l l l l l'J
)l FERMIUNIT 2: 3.5 14 Revision 7 06/18/99 L.
1 l l AC Sources-0perating ! 3.8.1 j 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating l LC0 3.8.1 . The following AC electrical power sources shall be OPERABLE:
- a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and
- b. Two emergency diesel generators (EDGs) per division.
l 1 APPLICABILITY: MODES 1. 2. and 3. l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I A. . One or both EDGs in A.1 Perform SR 3.8.1.1 1 hour one division for OPERABLE offsite , inoperable. circuit (s). MQ Once per 8 hours thereafter MQ A.2 Declare required 4 hours from feature (s). su) ported discovery of an by the inopera)1e inoperable EDG EDGs. inoperable when concurrent with the redundant inoperability of required feature (s) redundant are inoperable. required feature (s) MQ A.3 Verify the status of Once per 8 hours
} CTG 11 1.
k @ (continued) l FERMI UNIT 2 3.8-1 Revision 7 06/16/99
l AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4.1 Determine OPERABLE 24 hours dl EDG(s) are not inoperable due to common cause failure. l A.4.2 Perform SR 3.8.1.2 24 hours for OPERABLE EDG(s).
~i 5
6 A.5 Restore availability of CTG 11 1. 72 hours from discovery of Condition A concurrent with CTG 11-1 not available V i l A.6 Restore both EDGs in 7 days the division to OPERABLE status. B. One or both EDGs in B.1 Restore both EDGs in 2 hours both divisions one division to inoperable. OPERABLE status. C. One or two offsite C.1 Be in MODE 3. 12 hours circuits inoperable. E @ Required Action and C.2 Be in MODE 4. 36 hours Associated Completion Time of Condition A or B not met. l FERMI UNIT 2 3.8 2 Revision 7 06/18/99
l AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days. indicated power availability for each offsite circuit. SR 3.8.1.2 -- --
-------...--NOTES----- --- - -----
- 1. All EDG starts may be preceded by an
'@ l engine prelube period and followed by a warmup period prior to loading.
- 2. A modified DG start involving idling h and gradual acceleration to synchronous speed may be used for this 6
4 SR as recommended by the manufacturer. l Verify each EDG starts and achieves steady 31 days state voltage a 3740 V and s 4580 V and frequency a 58.8 Hz and s 61.2 Hz. SR 3.8.1.3 - -
-- NOTES - - - - ---
- 1. EDG loadings may include gradual
. loading as recommended by the manufacturer.
- 2. Homentary transients outside the load range do not invalidate this test.
- 3. lhis Surveillance shall be conducted on only one EDG at a time.
Verify each EDG is synchronized and loaded 31 days and operates for a 60 minutes at a load a 2500 kW. (continued) l FERMI UNIT 2 3.8 3 Revision 7 06/18/99
AC Sources-Operating , 3.8.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains = 210 gal of 31 days , fuel oil. ' i i SR -3.8.1.5 Check for and remove accumulated water from 31 days each day tank. SR 3.8.1.6 Verify each fuel oil transfer system 31 days operates to automatically transfer fuel oil from storage tanks to the day tanks. SR 3.8.1.7 - ---- ---- - -
- NOTE-- -- - - -------
s All EDG starts may be preceded by an engine T prelube period and followed by a warmup
.4 g-period prior to loading.
Verify each EDG starts from standby 184 days condition and achieves:
- a. In s 10 seconds, voltage a 3740 V and frequency a 58.8 Hz: and l
- b. Steady state voltage = 3740 V and 5 4580 V and frequency a 58.8 Hz and 5 61.2 Hz.
i SR 3.8.1.8 Verify each EDG rejects a load greater than 18 months or equal to its associated single largest I post accident load, and following load rejection, the frequency is s 66.75 Hz. l l (continued) l FERMI UNIT 2 3.8-4 Revision 7. 06/18/99 j
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS Jcontinued) SURVEILLANCE FREQUENCY SR 3.8.1.11 ----- - -
---NOTE ---- -- - - - -
All EDG starts may be preceded by an engine prelube period. Verify on an actual or simulated Emergency 18 months Core Cooling System (ECCS) initiation signal each EDG auto starts and: , l
- a. In s 10 seconds after auto start and during tests, achieves voltage jl = 3740 V and frequency a 58.8 Hz:
0 b. Achieves steady state frequency 4 a s4 hV an ! jl c. Operates for a 5 minutes. SR 3.8.1.12 Verify each EDG's automatic trips are 18 months bypassed on an actual or simulated ECCS initiation signal except:
- a. Engine overspeed:
- b. Generator differential current:
- c. Low lube oil pressure:
- d. Crankcase overpressure; and
- e. Failure to start.
(continued) ! l I I I FERMI - UNIT 2. 3.8-6 Revision 7 06/18/99 J
@[ Diesel Fuel Oil and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS @ l 3.8.3 Diesel Fuel Oil and Starting Air 3.8.3 The stored diesel fuel oil and starting air subsystem shall @ l LC0 be within limits for each required emergency diesel generator (EDG).
APPLICABILITY: When associated EDG is required to be OPERABLE. ACTIONS
..................................---NOTE- - --- - ------ - - - - --- - --
Separate Condition entry is allowed for each EDG. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore fuel oil 48 hours EDGs with fuel oil level'to within level < 35.280 gal and limits.
> 30.240 gal in storage tank.
B. One or more required B.1 Restore fuel oil 7 days EDGs with stored fuel total particulates to oil total particulates within limit. not within limit. dl C. One or more required C.1 Restore stored fuel 30 days EDGs with new fuel oil oil properties to properties not within within limits. limits. (continued) l l FERMI UNIT 2 3.8-13 Revision 7 06/18/99
1 l rnl Diesel Fuel Oil and Starting Air
.& 3.8.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME i Required Action and D.1 Declare associated Immediately Ql D. associated Completion EDG inoperable. Time not met.
.QB One or more required ,
EDGs with diesel fuel ' Ol W/ oil, or starting air subsystem not within l limits for reasons other than hl Condition A, B, or C. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each required EDG fuel oil storage 31 days tank contains = 35.280 gal of fuel. l . SR 3.8.3.2 Verify each required EDG fuel oil In accordance properties of new and stored fuel oil are with the tested in accordance with, and maintained Emergency within the limits of. the Emergency Diesel Diesel Generator Fuel Oil Testing Program. Generator Fuel Oil Testing Program (continued) J l FERMI UNIT 2 3.8-14 Revision 7.. 06/18/99 m
hl- Diesel Fuel Oil and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)' SURVEILLANCE FRE0VENCY SR 3.8.3.3- . Verify each required EDG air start receiver 31 days Ok l . pressure is a 215 psig. [l SR 3.8.3.4 Check for and remove accumulated water from 31 days each required EDG fuel oil storage tank. l l l i s 1 FERMI. UNIT 2- 3.8 15' Revision 7. 06/18/99
r DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY m SR 3.8.4.-l' Verify battery terminal voltage is a 130 V 7 days for Division I and = 125.7 V for D Division II on float charge. 6 SR 3.8.4.2- Verify no visible corrosion at battery 92 days terminals and connectors. Verify each battery cell-to cell and terminal connection resistance is s 1.5E 4 ohm. d SR 3.8.4.3 Verify battery cells, cell plates, and . 18 months J. racks show no visual indication of physical T damage or abnormal deterioration that could
%, degrade battery performance. 1 SR 3.8.4.4 Remove visible corrosion and verify battery 18 months cell to cell and terminal connections are coated with anti-corrosion material.
SR 3.8.4.5 Verify each battery cell to cell and 18 months terminal connection resistance s 1.5E-4 ohm. SR 3.8.4.6 Verify each required battery charger 18 months O supplies for Division I: a 100 amps at g = 129 V for a 4 hours; and Division II: _% = 100 amps at = 124.7 V for a 4 hours. (continued)
] FERMI UNIT 2 3.8 17 Revision 7 06/18/99
.t
1 Battery Cell Parameters 3.8.6
)
3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LC0 '3.8.6 - Battery cell parameters for the Division I and Division II batteries shall be within limits. APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE. ACTIONS
....................................-NOTE - - --- ------ -------------- --
Separate Condition entry is allowed for each battery. CONDITION REQUIRED ACTION COMPLETION TIME i 1 A. One or more batteries A.1 Verify pilot cells 1 hour , with one or more electrolyte level and i battery cell float voltage meet i
. parameters not within Table 3.8.6 1 J
@l -
, Table 3.8.6 1 Category . Category C limits. ;
- A or B limits. l 1-6~ND k
A.2 Verify battery cell 24 hours parameters meet Table 3.8.61 AN_D Category C limits. Once'per 7 days thereafter 6NJ A.3 Restore battery cell 31 days
. parameters to Table 3.8.6 1 Category A and B -h- ll- limits.
(continued) l FERMI UNIT 2 3.8 22 Revision 7 06/18/99
Battery Cell Parameters 3.8.6 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable. Time of Condition A not met. E
'One or more batteries with average electrolyte temperature of the
' representative cells not within limits.
E One or more batteries with one or more battery cell parameters not within Table 3.8.6 1 Category C values. , l l i SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet 7 days Table 3.8.61 Category A limits. (continued) l FERMI - UNIT 2 3.8 23 Revision 7 06/18/99
]
1 Distribution Systems-Operating 3.8.7 { l 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating
@ l LC0 3.8.7 The following Division I and Division II AC and DC electrical power distribution subsystems shall be OPERABLE:
- a. AC electrical power distribution subsystemsi Division I Division II
- 1. 4160 V Buses 11EA. 12EB 13EC. 14ED 648. 64C 65E. 65F
- 2. 480 V Buses 72EA. 72EB 72EC 72ED 1 728. 72C 72E. 72F
- 3. 120 V MPU 1 MPU 2 !
- b. DC electrical power distribution subsystems:
Division I Division II
- 1. 130 V Distribution 2PA 2 2PB 2 Cabinet i
- 2. 260 V MCC 2PA-1 2PB 1 APPLICABILITY: MODES 1. 2. and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore AC electrical AC electrical power 8 hours power distribution distribution subsystem (s) to 6NQ subsystems inoperable. OPERABLE status. 16 hours from discovery of failure to meet , LCO (continued) l FERMI - UNIT 2- 3.8-26 Revision 7 06/18/99
' ~
i
INSERT THIS PAGE IN FRONT OF VOLUME 13 t Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES Remove Replace B3.5.1 ITS pg B 3.5.1-3 Rev 0 B3.5.1 ITS pg B 3.5.1-3 Rev 7 B3.5.1 ITS pg B 3.5.1-9 Rev 0 l B3.5.1 ITS pg B 3.5.1-9 Rev 7 B3.5.1 ITS pg B 3.5.1-11 Rev 0 B3.5.1 ITS pg B 3.5.1-11 Rev 7 , l B3.5.1 ITS pg B 3.5.1-13 Rev 0 B3.5.1 ITS pg B 3.5.1-13 Rev 7 B3.5.1 ITS pg B 3.5.1-17 Rev 0 B3.5.1 ITS pg B 3.5.1-17 Rev 7 B3.5.2 ITS pg B 3.5.2-4 Rev 0 B3.5.2 ITS pg B 3.5.2-4 Rev 7
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B3.5.2 ITS pg B 3.5.2-5 Rev 0 B3.5.2 ITS pg B 3.5.2-5 Rev 7 B3.5.2 ITS pg B 3.5.2-6 Rev 0 B3.5.2 ITS pg B 3.5.2-6 Rev 7 B 3.8.1 ITS pg B 3.8.1-6 Rev 0 B 3.8.1 ITS pg B 3.8.1-6 Rev 7 B 3.',.1 ITS pg B 3.8.1-7 Rev 0 B 3.8.1 ITS pg B 3.8.1-7 Rev 7 B 3.8.1 ITS pg B 3.8.1-8 Rev 0 B 3.8.1 ITS pg B 3.8.1-8 Rev 7 B 3.8.1 ITS pg B 3.8.1-9 Rev 0 B 3.8.1 ITS pg B 3.8.1-9 Rev 7 B 3.8.1 ITS pg B 3.8.1 10 Rev 0 B 3.8.1 ITS pg B 3.8.1-10 Rev 7 B 3.8.1 ITS pg B 3.8.1-11 Rev 0 B 3.8.1 ITS pg B 3.8.1-11 Rev 7 B 3.8.1 ITS pg B 3.8.1-12 Rev 0 B 3.8.1 ITS pg B 3.8.1-12 Rev 7 l B 3.8.1 ITS pg B 3.8.1-13 Rev 0 B 3.8.1 ITS pg B 3.8.1-13 Rev 7 B 3.8.1 ITS pg B 3.8.1-14 Rev 0 B 3.8.1 ITS pg B 3.8.1-14 Rev 7 B 3.8.1 ITS pg B 3.8.1-15 Rev 0 B 3.8.1 ITS pg B 3.8.1-15 Rev 7 B 3.8.1 ITS pg B 3.8.1-16 Rev 0 B 3.8.1 ITS pg B 3.8.1-16 Rev 7 B 3.8.1 ITS pg B 3.8.!-17 Rev 0 B 3.8.1 ITS pg B 3.8.1-17 Rev 7 B 3.8.1 ITS pg B 3.8.1-18 Rev 0 B 3.8.1 ITS pg B 3.8.1-18 Rev 7 B 3.8.1 ITS pg B 3.8.1 19 Rev 0 B 3.8.1 ITS pg B 3.8.1-19 Rev 7 B 3.8.1 ITS pg B 3.8.1-20 Rev 0 B 3.8.1 ITS pg B 3.8.1-20 Rev 7 B 3.8.3 ITS pg B 3.8.3-1 Rev 0 B 3.8.3 ITS pg B 3.8.3-1 Rev 7 B 3.8.3 ITS pg B 3.8.3-2 Rev 0 B 3.8.3 ITS pg B 3.8.3-2 Rev 7 B 3.8.3 ITS pg B 3.8.3-3 Rev 0 B 3.8.3 ITS pg B 3.8.3-3 Rev 7 B 3.8.3 ITS pg B 3.8.3-4 Rev 0 B 3.8.3 ITS pg B 3.8.3-4 Rev 7 B 3.8.3 ITS pg B 3.8.3-5 Rev 0 B 3.8.3 ITS pg B 3.8.3-5 Rev 7 B 3.8.3 ITS pg B 3.8.3-6 Rev 0 B 3.8.3 ITS pg B 3.8.3-6 Rev 7 B 3.8.3 ITS pg B 3.8.3-7 Rev 0 B 3.8.3 ITS pg B 3.8.3-7 Rev 7 B 3.8.4 ITS pg B 3.8.4-2 Rev 1 B 3.8.4 ITS pg B 3.8.4-2 Rev 7 B 3.8.4 ITS pg B 3.8.4-3 Rev i B 3.8.4 ITS pg B 3.8.4-3 Rev 7 Rev7 06/18/99
Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES (cont'd) Remove Replace B 3.8.4 ITS pg B 3.8.44 Rev I B 3.8.4 ITS pg B 3.8.4-4 Rev 7 B 3.8.4 ITS pg B 3.8.4-5 Rev 1 B 3.8.4 ITS pg B 3.8.4-5 Rev 7 B 3.8.6 ITS pg B 3.8.6-6 Rev 0 B 3.8.6 ITS pg B 3.8.6-6 Rev 7 Rev7 06/18/99
ECCS -Operating B 3.5.1 BASES BACKGROUND (continued) provided for the four LPCI pumps to route water from the suppression pool, to allow testing of the LPCI pumps without l injecting water into the RPV. These test lines also provide suppression pool cooling capability. as described in LCO 3.6.2.3, "RHR Suppression Pool Cooling." The HPCI System (Ref. 3) consists of a steam driven turbine pump unit, piping, and valves to provide steam to the , turbine. as well as piping and valves to transfer water from ' the suction source to the core via the feedwater system line, where the coolant is distributed within the RPV through the feedwater sparger. Suction piping for the system is provided from the CST and the suppression pool. Pump suction for HPCI is normally aligned to the CST source to minimize injection of suppression pool water into the l RPV. However, if the CST water supply is low, or if the suppression pool level is high, an automatic transfer to the suppression pool water source ensures a water supply for continuous operation of the HPCI System. The steam supply to the HPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve. ' The HPCI System is designed to provide core cooling for a wide range of reactor pressures (165 psig to 1146 asig). Upon receipt of an initiation signal, the HPCI turaine stop valve and turbine control valve open simultaneously and the turbine accelerates to a specified speed. As the HPCI flow increases, the turbine governor valve is automatically adjusted to maintain design flow. Exhaust steam from the HPCI turbine is discharged to the suppression pool. A full flow test line is 3rovided to route water to the CST to allow testing of t1e HPCI System during normal operation without injecting water into the RPV, The ECCS pumps are provided with minimum flow bypass lines, which discharge to the suppression pool. The valves in these lines automatically open to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, all ECCS pump discharge lines are filled with water. The LPCI and CS System discharge lines are kept full of water using a " keep fill" system. The core spray lines are kept charged with demineralized water and the RHR lines are kept charged with condensate water by a pressure regulating valve. The HPCI System is normally l FERMI - UNIT 2 B 3.5.1 - 3 Revision 7, 06/18/99
F-ECCS- Operating B 3.5.1 BASES
. ACTIONS (continued)
L1-The LC0 requires five ADS valves to be OPERABLE in order to provide the ADS function. The ECCS analyses are performed
. with the initial condition of one ADS valve out of service (Ref. 13). Per this analysis, operation of only four ADS valves will provide the required depressurization. However, overall reliability of the ADS is reduced. because a single failure in the OPERABLE ADS valves could result in a reduction in depressurization capability. Therefore, operation is only allowed for a limited time. The 14 day Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience.
H.1 and H.2 7 If any one low pressure ECCS injection / spray subsystem, or 1l one LPCI pump in both LPCI subsystems, is inoperable in W addition to one inoperable ADS valve. adequate core cooling is ensured by the OPERABILITY of HPCI and the remaining low pressure ECCS injection / spray subsystem. However, overall ECCS reliability is- reduced because a single active component failure concurrent with a design basis LOCA could
-result in the minimum required ECCS equipment not being available. Since both a high pressure system (ADS) and low pressure subsystem (s) are inoperable, a more restrictive Completion Time of 72 hours-is required to restore either the low pressure ECCS subsystem (s) or the ADS valve to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience.
I-1 and I.2 i' If any Required Action and associated Completion Time of Condition E. F. G. or H is not met, or if two or more ADS valves are inoperable, the plant must be brought to a condition in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours and reactor steam dome pressure reduced.to - s 150 psig within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. ;
'r
.l-FERMI-E UNIT 2 B 3.5.1- 9 Revision 7 06/18/99
l I l ECCS- Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) discharge valves, and LPCI cross-tie valve. The swing bus automatic throwover scheme must be OPERABLE for both LPCI subsystems to be OPERABLE. The 31 day Frequency has been found acceptable based on engineering judgment and operating 1 experience.
]
This SR is modified by a Note to indicate that when this test results in LPCI inoperability solely for performance of l this required Surveillance, or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG-12 being l paralleled to the bus for required testing, entry into l associated Conditions and Required Actions may be delayed s* for up to 12 hours until the required testing is completed. ( Upon completion of the Surveillance or expiration of the 12 hour allowance the swing bus must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. SR 3.5.1.3 The flow path piping has the potential to develop voids and pockets of entralned air. Maintaining the pump discharge lines of the HPCI System CS System. and LPCI subsystems full of water ensures that the ECCS will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent a water hammer following an ECCS initiation signal. One acceptable method of ensuring that the lines are full is to vent at the high points. The 31 day Frequency is based on the gradual nature of void buildup in the ECCS piping, the procedural controls governing system operation, and operating experience. SR 3.5.1.4 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a non accident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation rather, it involves { FERMI - UNIT 2 B 3.5.1 - 11 Revision 7 06/18/99
ECCS-Operating i B 3.5.1 l l BASES: ! i SURVEILLANCE REQUIREENTS (continued)' SR 3.5.1.6 Verification every 31 days that the RHR System power operated cross-tie valve is open ensures that each LPCI - 1
+ subsystem remains ca recirculation loop. pable of injaction A valve into the. selected that is inaccessible may be i
verified by administrative controls; If a RHR System cross-tie valve is not o>en. both LPCI subsystems must be considered inopera)le. The 31 day Frequency has been found acceptable, considering that these valves are under strict administrative controls that will ensure the valves continue to remain open. 4 I SR 3.5.1.7 Cycling the recirculation pump discharge valves through one complete cycle of full travel demonstrates that the valves . are mechanically OPERABLE and will close when required. i
-Upon initiation of an automatic LPCI subsystem injection '
signal, these valves are required to be closed to ensure i full LPCI subsystem flow injection in the reactor via the ' recirculation jet pumps. De energizing the valve in the
. closed position will also ensure the proper flow path for the LPCI subsystem. Acceptable methods of de ener valve include de energizing breaker control power.gizing racking the out the breaker or removing the breaker.
The specified Frequency is.18 months. Verification each i 18 months is an exception to the normal Inservice Testing Program generic valve cycling Frecuency of 92 days. but is considered acceptable due to the cemonstrated reliability of these valves. If the valve is inoperable and in the open position, both LPCI subsystems must be declared inoperable. 1 [ FERMI UNIT 2 B 3.5.1 -13 Revision 7 06/18/99
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ECCS -Operating B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) which this SR is to be performed is a 850 psig (the pressure recommended by the valve manufacturer). Adequate steam flow ; is represented by turbine bypass valves open at least 201. O/)l Reactor startup is allowed prior to performing this SR because valve OPERABILITY and the setpoints for overpressure. protection are verified, per ASME requirements', prior to valve installation. Therefore, this SR is modified by a Note that states the Surveillance is not required to be . performed until 12 hours after reactor steam pressure and I flow are adequate to perform the test. The 12 hours allowed I for manual actuation after the required pressure and flow are reached is sufficient to achieve stable conditions and provides adequate time to complete the Surveillance. SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TEST performed , in LC0 3.3.5.1 overlap this Surveillance to provide complete I testing of the assumed safety function. The Frequency is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a plant outage. Operating
' experience has shown that these components usually pass the ' SR when performed at the 18 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.5.1.14 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Response time testing acceptance criteria are included in Reference 15. This SR is modified by a Note stating that the ECCS instrumentation response times are not required to be measured. The contribution of the instrument response times to the overall ECCS response j time are assumed based on guidance of Reference 16. l The 18 month Frequency is based or, the need to perform this Surveillance under the conditions that apply during a plant ; outage and the potential for an un)lanned transient if the i Surveillance were performed with t1e reactor at power. Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency. l FERMI UNIT 2 B 3.5.1 17 Revision 7 06/18/99 l
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ECCS-Shutdown B 3.5.2 BASES ACTIONS (continued) to OPERABLE status. In this case, the Surveillance may need to be performed to restore the component to OPERABLE status. Actions must continue until all required components are l OPERABLE. : The 4 hour Completion Time to restore at least one low pressure ECCS injection / spray subsystem to OPERABLE status ensures that prompt action will be taken to provide the required cooling capacity or to initiate actions to place the plant in a condition that minimizes any potential fission product release to the environment. SURVEILLANCE SR 3.5.2.1 and SR 3.5.2.2 REQUIREMENTS The minimum water level indication of 66 inches (9 ft 0 inches actual level) required for the suppression pool is periodically verified to ensure that the suppression pool will provide adequate net positive suction head (NPSH) for j the CS System and LPCI subsystem pumps, recirculation volume. and vortex prevention. With the suppression pool water level less than the required limit, all ECCS injection / spray subsystems are inoperable unless they are aligned to an OPERABLE CST. When suppression pool level is < -66 inches, the CS System I is considered OPERABLE only if it can take suction from the CST, and the CST water level is sufficient to provide the required NPSH for the CS pump. Therefore, a verification that either the suppression pool water level is = -66 inches or that CS is aligned to take suction from the CST and the
'[d CST contains a 300.000 gallons of water, equivalent to 19 ft W/ plus margin to preclude vortex formation, ensures that the CS System can supply at least 150,000 gallons of makeup water to the RPV. The CS suction is uncovered at the 150,000 gallon level. However, as noted, only one required CS subsystem may take credit for the CST option during OPDRVs. During OPDRVs. the volume in the CST may not provide adequate makeup if the F.PV were completely drained.
Therefore, only one CS subsystea is allowed to use the CST. This ensures the other required ECCS subsystem has adequate makeup volume. The 12 hour Frequency of these SRs was developed considering operating experience related to suppression pool water level i FERMI UNIT 2 B 3.5.2-4 Revision 7 06/18/99 T
1 I ECCS - Shutdown . B 3.5.2 ) BASES SURVEILLANCE REQUIREMENTS (continued) 1 and CST water level variations and instrument drift during ! the applicable MODES. Furthermore, the 12 hour Frequency is j considered adequate in view of other indications available in the control room including alarms. to alert the operator to an abnormal suppression pool or CST water level , condition. 1 SR 3.5.2.3 i The LPCI System injection valves. recirculation pump discharge valves, and LPCI cross tie valve are powered from the LPCI swing bus, which must remain energized to support , OPERABILITY of any required LPCI subsystem. Therefore. l verification of proper voltage and correct breaker alignment l to the swing bus is made every 7 days. The correct breaker alignment ensures the appropriate electrical power sources are available, and the appropriate voltage is available to the swing bus, including verification that the swing bus is energized from its normal source (bus 72C). The verification of proper voltage availability ensures that the required voltage is readily available for critical system loads connected to this bus. The 7 day Frequency takes into 3 account the redundant capability of the AC. DC. and AC swing j bus electrical power sources, and other indications available in the control room that alert the operator to subsystem malfunctions. l SR '3.5.2.4. SR 3.5.2.6. and SR 3.5.2d I k The Bases provided for SR 3.5.1.3 SR 3.5.1.8. and SR 3.5.1.11 are applicable to SR 3.5.2.4. SR 3.5.2.6. and SR 3.5.2.7. respectively. l l L l l l FERMI UNIT 2 B 3.5.2- 5 Revision 7 06/18/99 L
l l ECCS - Shutdown l B 3.5.2 BASES
-SURVEILLANCE REQUIREMENTS (continued)
- l. ,
SR 3.5.2.5 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides , assurance that the proper flow paths will exist for ECCS ! operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since I these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation: rather. it i involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is appropriate because the valves are operated under procedural control and the probability of their being mispositioned during this time period is low. In H0 DES 4 and 5. the RHR System may operate in the shutdown cooling mode to remove decay heat and sensible heat from the reactor. Therefore RHR valves that are required for LPCI subsystem operation may be aligned for decay heat removal. Therefore, this SR is modified by a Note that allows one or both LPCI subsystems of the RHR System to be considered OPERABLE for the ECCS function if all the required valves in the LPCI flow path can be manually realigned (remote or local) to allow injection into the RPV and the system is not otherwise inoperable. This will ensure adequate core cooling if an inadvertent RPV draindown should o.ccur. REFERENCES 1. UFSAR. Section 6.3.2. I 1 l FERMI UNIT 2 B 3.5.2-6 Revision 7 06/18/99 I
AC Sources-Operating B 3.8.1 BASES ACTIONS (continued) events existing concurrently is acceptable because it
. _ minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown.
'The remaining OPERABLE EDGs and offsite circuits are adequate to supply electrical power to the onsite Class 1E-Distribution System. Thus, on a component basis, single failure protection for the required feature's function may have been lost: however, function has not been lost. The 4 hour Completion Time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required feature. Additionally, the 4 hour Completion Time takes into accoent the capacity and capability of the remaining AC. sources, reasonable time for repairs, and low probability of a DBA occurring during this period.
Al To minimize the impact of operation with an inoperable EDG, it is necessary to periodically ensure the availability of CTG 11-1. The verification of the status of CTG 111 is performed by an administrative check of breaker and line availability, and the CTG 111 ability to supply Division I loads. Since this Required Action or.ly specifies ** verify 6 the status " even when CTG 11 1 is not available it does not l result in this Required Actions being not met. However, upon discovery that CTG 111 is unavailable, the limitations 4 of Required Action A.5 are imposed l A.4.1 and A.4.2 )
.I l Required Action A.4.1 provides an allowance to avoid W
W unnecessary testing of OPERABLE EDGs. If it can be determined that the cause of the inoperable EDG(s) does not exist on the OPERABLE EDGs, SR 3.8.1.2 does not have to be performed. If the cause of inoperability exists on other
. EDG(s), they are declared inomrable upon discovery, and Condition B of LCO 3.8.1 may a entered. Once the failure is repaired, and the common cause failure no longer exists.
l Required Action A.4.1 is satisfied. :If the cause of the initial inoperable EDG cannot be confirmed not to exist on the remaining EDG(s), performance of SR 3.8.1.2 suffices to provide assurance of continued OPERABILITY of those EDGs.
% In the event the inoperable EDG(s) are restored to OPERABLE ,
l ' status prior to completing either A.4.1 or A.4.2, the plant ' l FERMI ' UNIT 2' B 3.8.1- 6 Revision 7 06/18/99
AC Sources-0perating I B 3.8.1 i BASES ACTIONS (continued) corrective action )rogram will continue to evaluate the common cause possi)ility. This continued evaluation. l however, is no longer under the 24 hour constraint imposed
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while in Condition A. l According to Generic Letter 84-15 (Ref. 7), 24 hours is a reasonable time to confirm that the OPERABLE EDGs are not l affected by the same problem as the inoperable EDG. l 4l A.5 and A.6 According to Regulatory Guide 1.93 (Ref. 6), operation may ) continue with no OPERABLE EDGs to one division for a period ' that should not exceed 72 hours. With one or both EDGs in , one division inoperable, the remaining OPERABLE EDGs and ' offsite circuits are adequate to supply electrical power to l
~ the onsite Class 1E Distribution System. Required Action i d A.5 imposes this 72 hour Completion Time from the discovery i Q of the non availability CTG 111. However, if CTG 111 is available to sup)1y Division I loads (determined by administrative cleck of breaker. line availability, and CTG 111 status) Recuired Action A.5 would be met and Required Action A.6 woulc allow the restoration time of 7 days.
The 72 hour Completion Time to restore to at least one EDG in the division in OPERABLE status takes into account the capacity and capability of the remaining AC sources, reasonable time for repairs, and low probability of a DBA yl occurring during this period. The 7 day Completion Time to restore all EDGs to OPERABLE status takes into account the 1 capacity and capability of the remaining AC Sources, as well as the additional reliability afforded by the availability of CTG 11-1. IL1 With one or both EDGs on both divisions inoperable, there may be no remaining standby AC source. Thus, with an assumed loss of offsite electrical power, insufficient standby AC sources are available to power the minimum required ESF functions. Since the offsite electrical power system is the only source of AC Jower for a significant percentage of ESF equipment at t1is level of degradation, the risk associated with continued operation for a very short time could be less than that associated with an immediate controlled shutdown. (The immediate shutdown
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l, FERMI UNIT 2 B 3.8.1 - 7 Revision 7 06/18/99
i-l l l l I AC Sources-Operating B 3.8.1 l BASES ACTIONS (continued) l L could cause grid instability, which could result in a total i loss of AC power.) Since any inadvertent unit generator trip could also result in a total loss of offsite AC power. ! however, the time allowed for continued operation is , severely restricted. The intent here is to avoid the risk l I associated with an immediate controlled shutdown and to minimize the risk associated with this level of degradation. According to Regulatory Guide 1.93 (Ref. 6), with both l divisions with EDGs inoperable, operation may continue for a period that should not exceed 2 hours. l C.1 and C.2 l If the inoperable AC electrical power sources cannot be restored to OPERABLE status within the associated Completion Time. the unit must be brought to a MODE in which the LC0 does not apply. Furthermore, with one or both offsite . circuits inoperable, the Fermi design and subsequent plant response is such that power operation is not justified, and c plant shutdown is required. To achieve this status, the unit must be brought to at least MODE 3 within 12 hours and to MODE 4 within 36 hours. 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. SURVEILLANCE The AC sources are designed to permit inspection and REQUIREMENTS testing of all important areas and features. especially those that have a standby function, in accordance with 10 CFR 50. GDC 18 (Ref. 8). Periodic component tests are supplemented by extensive functional tests during refueling outages (under simulated accident conditions). The SRs for demonstrating the OPERABILITY of the EDGs are based on the recommendations of Regulatory Guide 1.9 (Ref. 3). Regulatory Guide 1.108 (Ref. 9), and Regulatory Guide 1.137 (Ref.10), as addressed in the UFSisR. Where the SRs discussed herein specify voltage and frequency tolerances, the following summary is applicable. The minimum steady state output voltage of 3740 V is 90% of the nominal 4160 V output voltage. This value, which is l l I k l FERMI UNIT 2 B 3.8.1 - 8 Revision 7 06/18/99
AC Sources-Operating ; B 3.8.1
]
BASES SURVEILLANCE. REQUIREMENTS (continued) specified in ANSI C84.1'(Ref.11), allows for voltage drop to the terminals of 4000 V motors whose minimum operating voltage is specified as 90% or 3600 V. It also allows for voltage drops to motors and other equipment down through the 120 V. level where minimum operating voltage is also usually specified as 90% of name I; late rating. The specified
. maximum steady state output. voltage of 4580 V is equal to the maximum operating voltage specified for 4000 V motors.
It ensures that for a lightly loaded distribution system. the voltage at the terminals of 4000 V motors is no more than the maximum rated operating voltages. . The specified minimum and maxhum frequencies of the EDG are 58.8 Hz and 61.2 Hz respectively. These values are equal to
- 2% of the 60 Hz nominal frequency and are derived from the recommendations found in Regulatory Guide 1.9 (Ref. 3).
SR 3.8.1.1 This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite' distribution network and availability of offsite AC electrical power. . The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads
.are connected to their preferred power source and that appropriate independence of offsite circuits is maintained.
The.7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it and because its status is displayed in the control room. SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the . standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown condition. To minimize the mechanical stress and wear on moving parts that do not get lubricated when the engine is not running.
.l.. these SRs have been modified by a Note (Note 1 for SR 3.8.1.2 and Note 1 for SR 3.8.1.7) to indicate that all EDG starts for these Surveillances may be preceded by an ;
g engine prelube period and followed by a warmup prior to j
., loading.
g
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l l FERMI UNIT 2 B 3.8.1- 9 Revision 7 06/18/99
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AC Sources-Operating i B 3.8.1 l BASES !
. SURVEILLANCE REQUIREMENTS (continued)
For the purposes of SR 3.8.1.2 testing, the EDGs are started anywhere from standby to hot conditions by using one of the following signals: Manual. Simulated loss of-offsite power by itself. Simulated loss of offsite power in con,iunction with an ESF actuation test signal, or
- An ESF actuation test signal by itself.
'In order to reduce stress and wear on diesel engines, the EDG manufacturer recommends a modified start in which the starting speed of EDGs is limited, warmup is limited to this lower speed, and the EDGs are gradually accelerated to g synchronous speed prior to loading. These start procedures
.i are the' intent of Note 2, which is only allowed to satisfy
'fl SR 3.8.1.2 but are not applicable when performing SR 3.8.1.7.
SR 3.8.1.7 requires that, at a 184 day Frequency, the EDG starts from standby conditions and achieves required voltage and frequency within 10 seconds. Standby conditions for an EDG mean that the diesel engine coolant and oil are being continuously circulated and temperature is being maintained consistent with manufacturer recommendations. The 10 second start requirement supports the assumptions in the design basis LOCA analysis of UFSAR. Section 6.3 (Ref.12). The 10 second start. requirement is not applicable to SR 3.8.1.2. Since SR 3.8.1.7 does require a 10 second start. it is more
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restrictive than SR 3.8.1.2, and it may be performed in lieu of SR 3.8.1.2. . In addition to the SR requirements, the time for the EDG to reach steady state operation, unless the 9 modified EDG start method is-employed, is periodically
' monitored and the trend evaluated to identify degradation of 4- governor and voltage regulator performance.
!$ -The normal 31 day Frequency for SR 3.8.1.2 is consistent A with Regulatory Guide 1.9.(Ref. 3). The 184 day. Frequency 4 .
-for SR 3.8.1.7 is:a reduction in cold testing consistent with Generic Letter 84 15'(Ref. 7). These Frequencies provide adecuate assurance of EDG OPERABILITY, while
' minimizing cegradation resulting from testing.
'l'-FERMI UNIT 2- ' B 3. 8.1 Revision 7. 06/18/99
o AC Sources'-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) SR 3.8.1.3 This Surveillance provides assurance that the EDGs are capable of synchronizing and accepting greater than or equal to the equivalent of the maximum expected accident loads al
;- without the risk of overloading the EDG. The EDG is tested at approximately 90% of its continuous load rating, which provides margin to excessive EDG loading, while demonstrating the EDG capability to carry loads near the maximum expected accident loads. A minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the EDG is connected to the offsite source.
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Although no power factor requirements are established by this SR, the EDG is normally operated at a power factor between 0.8 lagging and 1.0. The 0.8 value is the design 3 rating of the machine, while 1.0 is an operational limitation to ensure circulating currents are minimized. D Routine overloading may result in more frequent teardown
.L inspections in accordance with vendor recommendations in
& order to maintain EDG OPERABILITY.
The normal 31 day Frequency for this Surveillance is kll consistent with Regulatory Guide 1.9 (Ref. 3). Note 1 modifies this Surveillance tc indicate that diesel engine runs for this Surveillance may include gradual loading. as recommended by the manufacturer, so that mechanical stress and wear on the diesel engine are minimized. Note 2 modifies this Surveillance by stating that momentary transients (e.g., because of changing bus loads) do not invalidate this test. Similarly, momentary power factor transients o.itside the normal range do not invalidate the test. Note 3 indicates that this Surveillance should be conducted on only one EDG at a time in order to avoid common cause failures that might result from offsite circuit or grid perturbations. l I l l FERMI UNIT 2 F, 3.8.1 - 11 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 l BASES SURVEILLANCE REQUIREMENTS (continued) , SR 3.8.1.4 , This SR provides verification that the level of fuel oil in l the day tank is at or above the level at which fuel oil is L ' automatically added. The level is expressed as an l- ecuivalent volume in gallons, and is selected to ensure acequate fuel oil for a minimum of 1 hour of EDG operation at full load.
- The 31 day Frequency is adequate to ensure that a sufficient
! . supply of fuel oil is available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period. l 'SR- 3.8.1.5 Microbiological fouling is a major cause of fuel oil degradation. There are numerous bacteria that can grow in , fuel oil and cause fouling, but all must have a water l environment in order to survive. Reinoval of water from the fuel oil day tanks once every 31 days eliminates the . necessary environment for bacterial survival. _ This is the i most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during EDG operation. Water may come from any of several sources. including condensation, ground water, rain water. contaminated fuel 011. and breakdown of the fuel. oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and . provides data regarding the watertignt integrity of the fuel ' oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref.10). This SR is for preventive i maintenance. The presence of water does not necessarily represent- a failure of this SR providod that accumulated water is removed during performance of this Surveillance. SR 3.8.1.6 This Surveillance demonstrates that each required fuel oil transfer pump operates' and transfers fuel oil from its associated storage tank to its associated day tank. It is required to support continuous operation of standby power sources. This Surveillance provides assurance that the fuel
' oil transfer pump is OPERABLE. the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the l FERMI - UNIT 2 B 3.8.1 - 12 Revision 7 06/18/99 e
c AC Sources-Operating B 3.8.1 BASES ! SURVEILLANCE REQUIREMENTS (continued) ; controls and control systems for automatic fuel transfer systems are OPERABLE. l The design of fuel transfer systems is such that pumps operate automatically in order to maintain an adequate volume of fuel oil in the day tank during or following EDG , testing. As such, a 31 day Frequency is appropriate, since l proper o)eration of fuel transfer systems is an inherent part of EDG OPERABILITY. SR 3.8.1.7 See SR 3.8.1.2. SR 3.8.1.8 Each EDG is provided with an engine overspeed trip to l prevent damage to the engine. Recovery from the transient caused by the loss of a large load could cause diesel engine overspeed, which, if excessive might ' result in a trip of the engine. This Surveillance demonstrates the EDG load response characteristics and capability to reject the largest single load while maintaining a specified margin to the overspeed trip. The largest single load for each EDG is a residual heat removal pump (1684 kW). This Surveillance may be accomplished by:
- a. Tripping the EDG output breaker with the EDG carrying areater than or ecual to its associated single largest
;ost accident loac while paralleled to offsite power, or while solely supplying the bus: or
- b. Tripping its associated single largest )ost accident load with the EDG solely supplying the aus.
As required by IEEE-308 (Ref.14), the load rejection test is acceptable if the increase in diesel s)eed does not exceed 75% of the difference between sync 1ronous speed and the overspeed trip setpoint, or 15% above synchronous speed, whichever is lower. This represents 66.75 Hz, equivalent to 75% of the difference between nominal speed and the overspeed trip setpoint.
- 1. FERMI UNIT 2 B 3.8.1 - 13 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) The frequency tolerances specified in this SR are derived
- from Regulatory Guide 1.9 (Ref. 3) recommendations for j response during load sequence intervals. The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9).
SR '3.8.1.9 This Surveillance demonstrates the EDG capability to reject a full load without overspeed tripping or exceeding the predetermined voltage limits. The EDG full load rejection may occur because of a system fault or inadvestent breaker i tripping. This Surveillance ensures proper engine generator i lead response under the simulated test conditions. This l test simulates the loss of the total connected load that the i EDG ex>eriences following a full load rejection and verifies ; that t7e EDG does not trip upon loss of the load. These I acceptance criteria provide EDG damage 3rotection. While ; the EDG is not expected to experience t11s transient during l an event, and continues to be available, this response ensures that the EDG is not degraded for future application, including reconnection to the bus if the trip initiator can be corrected or isolated. The 18 month Frequency is consistent with the recommendation of Regulatory Guide 1.108 (Ref. 9) and is intended to be consistent with expected fuel cycle lengths. SR 3.8.1.10 As required by Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(1), this Surveillance demonstrates the as designed operation of the standby power sources during loss of the offsite source. This test verifies all actions encountered from the loss of offsite power. including shedding of the nonessential loads and energization of the emergency buses and respective loads from the EDG, including automatic start of the EDG cooling water pump. It further demonstrates the capability of the EDG to automatically achieve the required voltage and frequency within the specified time. The EDG auto start time of 10 seconds is derived from requirements of the accident analysis for responding to a design basis large break LOCA. The Surveillance should be continued for a minimum of 5 minutes in order to demonstrate FERMI UNIT 2 B 3.8.1- 14 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 i BASES l SURVEILLANCE REQUIREMENTS (continued) that all starting transients have decayed and stability has been achieved. The requirement to verify the connection and power supply of permanent and auto-connected loads is intended to i satisfactorily show the relationship of these loads to the EDG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For instance. Emergency Core Cooling Systems (ECCS) injection valves are not desired to be stroked open, or systems are not capable of being operated at full flow, or RHR systems performing a decay heat removal function are not desired to be realigned to the ECCS mode of operation. In lieu of actual demonstration of the connection and loading of these loads, testing that adequately shows the capability of the EDG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified. The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(1), takes into consid2 ration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. This SR is modified by a Note allowing EDG starts to be preceded by an engine prelube period. The reason for the Note is to minimize wear and tear on the EDGs during testing. SR 3.8.1.11 This Surveillance demonstrates that the EDG (including its associated cooling water pump) automatically starts and achieves the required minimum voltage and frequency within the specified time (10 seconds) from the design basis actuation signal (LOCA signal) and operates for a 5 minutes. The 5 minute period provides sufficient time to demonstrate stability. The Frequency of 18 months takes into consideration plant conditions required to perform the Surveillance and is intended to be consistent with the expected fuel cycle lengths. Operating experience has shown that these l FERMI - UNIT 2 B 3.8.1 - 15 Revision 7 06/18/99
l l l AC Sources-Operating B 3.8.1 l BASES SURVEILLANCE REQUIREMENTS (continued) l l components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is acceptable ! from a reliability standpoint. l This SR is modified by a Note allowing EDG starts to be l preceded by an engine prelube period. The reason for the ! l Note is to minimize wear and tear on the EDGs during ) l testing. l i SR 3.8.'1.12 l l This Surveillance demonstrates that EDG non critical l protective functions (e.g. high jacket water temperature) are bypassed on an actual or simulated ECCS initiation signal and critical protective functions (engine overspeed. generator differential current low lubricating oil pressure crankcase overpressure, and failure to start) trip the EDG to avert substantial damage to the EDG unit. The non-critical trips are bypassed during DBAs and provide an alarm ) on an abnormal engine condition. This alarm provides the l l operator with sufficient time to react appropriately. The L EDG availability to mitigate the DBA is more critical than I protecting the engine against minor problems that are not immediately detrimental to emergency operation of the EDG. The 18 month Frecuency is based on engineering judgment, takes into consiceration plant conditions required to l per form the Surveillance, and is intended to be consistent l with ex>ected fuel cycle lengths. Operating experience has shown t1at these components usually pass the SR when 4 performed at the 18 month Frequency. Therefore, the l Frequency was concluded to be acceptable from a reliability j standpoint. ' SR 3.8.1.13 Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(3). requires q l demonstration once per 18 months that the EDGs can start and ! run continuously at full load capability for an interval of ' not less than 24 hours-22 hours of which is at a load equivalent to the continuous rating of the EDG, and 2 hours of which is at a load equivalent to 110% of the continuous duty rating of the EDG, Fermi 2 has taken an exception to ' this requirement and performs the 22 hour run at approximately 90% of the continuous rating (2500 kW-2600.kW), and performs the 2 hour run at approximately the
.y.
l FERMI UNIT.2 B 3.8.1 - 16 Revision 7 06/18/99 L
AC Sources-Operating B 3.8.1 1 BASES SURVEILLANCE REQUIREMENTS (continued) continuous rating (2800 kW 2900 kW). The EDG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for prelube and warmup, discussed in SR 3.8.1.2. and for gradual loading. discussed in SR 3.8.1.3. are applicable to this SR. Although no power factor requirements are established by to this SR, the EDG is normally operated at a power factor i between 0.8 lagging and 1.0. The 0.8 value is the desian R rating of the machine, while the 1.0 is an operational 4t limitation to ensure circulating currents are minimized. A load band is provided to avoid routine overloading of the EDG. Routine overloading may result in more frequent ; teardown inspections in accordance with vendor i recommendations in order to maintain EDG OPERABILITY. The 18 month Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(3); takes into consideration plant conditions required to perform the Surveillance: and is intended to be consistent with expected fuel cycle lengths. This Surveillance has been modified by a Note. The Note states that momentary transients due to changing bus , loads do not invalidate this test. SR 3.8.1.14 This Surveillance demonstrates that the diesel engine can I restart from a hot condition, such as subsequent to shutdown i from normal Surveillances. and achieve the minimum required ! voltage and frequency within 10 seconds and maintain a ' steady state voltage and frequency range. The 10 second time is derived from the requirements of the accident analysis to respond to a design basis large break LOCA. The 18 month Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). paragraph 2.a.(5). This SR is modified by two Notes. Note 1 ensures that the test is performed with the diesel sufficiently hot. The
> requirement that the diesel has operated for at least T 2 hours near full load conditions prior to performance of -5 this Surveillance is based on manufacturer recommendations Vi for achieving hot conditions. Routine overloads may result in more frequent teardown inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY.
n l FERMI UNIT 2 B 3.8.1 - 17 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued) Homentary transients due to changing bus loads do not invalidate this test. Note 2 allows all EDG starts to be preceded by an engine prelube period to minimize wear and tear on the diesel during testing. SR 3.8.1.15 As required by Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(6), this Surveillance ensures that the manual synchronization and load transfer from the EDG to the offsite source can be made and that the EDG can be returned to standby status when offsite power is' restored. It also ensures that the auto start logic is reset to allow the EDG to restart and reload if a subsequent loss of offsite power occurs. The EDG is considered to be in standby status when the EDG is shutdown with the output breaker open, the load sequence timers are reset, and is able to restart and reload on a subsequent bus under voltage. The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(6), and takes into consideration plant conditions desired to perform the Surveillance. SR 3.8.1.16 Under accident conditions with loss of offsite power loads are. sequentially connected to the bus by the automatic load sequencer. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading of the EDGs due to high motor starting currents. The 10% load sequence time interval tolerance' ensures that sufficient time exists for the EDG to restore frequency and voltage ; prior to applying the next load and that safety analysis
. assumptions regarding ESF equipment time delays are not violated. Reference 2 provides a summary of the automatic loading of ESF buses.
The Frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9), paragraph 2.a.(2): takes into consideration plant conditions required to perform the Surveillance: and is intended to be consistent with expected fuel cycle lengths.
~
j FERMI - UNIT 2 B 3.8.1-18 Revision 7 06/18/99
7 . ) AC Sources-Operating B 3.8.1 BASES
-SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.17 l In the event of a DBA coincident with a loss of offsite power, the EDGs are required to supply the necessary power
-to ESF systems so that the fuel, RCS, and containment design limits are not exceeded.
This Surveillance demonstrates EDG operation, as discussed in the Bases for SR 3.8.1.10. during a loss of offsite power
~ actuation test signal in conjunction with an ECCS initiation signal .- In lieu of actual demonstration of connection and '
loading of loads testing that adequately shows the i capability of the EDG system to perform these functions is ) acce table. This testing may include any series of ' seqr 'tial, overlapping, or total steps so that the entire i cor tion and loading sequence is verified. ; Th. ~requency of 18 months takes into consideration plant ' conc..tions required to perform the Surveillance and is ! intended to be consistent with an expected fuel cycle length of 18 months. , This SR is modified by a Note allowing EDG starts to be i preceded by an engine prelube period. The reason for the i Note is to minimize wear and tear on the EDGs during testing. SR 3'.8.1.18 l This Surveillance demonstrates that the EDG starting independence has not been compromised. Also, this Surveillance demonstrates that each engine can achieve proper speed within the specified time when the EDGs are started simultaneously. The 10 year Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9). ' This SR is modified by a Note allowing EDG starts to be
) receded by an engine prelube period. The reason for the ete is to minimize wear on the EDG during testing.
1 [. FERMI UNIT 2 B 3.8.1 -19 Revision 7 06/18/99
AC Sources-Operating B 3.8.1 BASES REFERENCES 1. 10 CFR 50, Appendix A. GDC 17.
- 2. UFSAR. Sections 8.2 and 8.3.
- 3. Regulatory Guide 1.9.
- 4. UFSAR Chapter 6.
- 5. UFSAR, Chapter 15.
- 6. Regulatory Guide 1.93.
- 7. Generic Letter 84-15.
- 8. 10 CFR 50. Appendix A, GDC 18.
- 9. Regulatory Guide 1.108.
- 10. Regulatory Guide 1.137.
- 11. ANSI C84.1. 1982.
- 12. UFSAR. Section 6.3.
- 13. ASME Boiler and Pressure Vessel Code. Section XI.
- 14. IEEE Standard 308.
4 I 4 l' FERMI UNIT 2 B 3.8.1 - 20 Revision 7. 06/18/99 1 L
I l Diesel Fuel Oil and Starting Air B 3.8.3 8 3.8 ELECTRICAL POWER SYSTEMS
}lB3.8.3 Diesel Fuel Oil and Starting Air BASES BACKGROUND Each emergency diesel generator (EDG) is provided with a storage tank having a fuel oil capacity sufficient to operate that EDG for a period of 7 days while the EDG is supplying maximum continuous load discussed in UFSAR.
Section 9.5.4 (Ref. 1). This onsite fuel oil ca)acity is i sufficient to operate the EDGs for longer than tie time to
- replenish the onsite supply from outside sources.
Fuel oil is transferred from storage tank to day tank by either of two transfer pumps associated with each storage i tank. Redundancy of pumps and piping precludes the failure of one pump. or the rupture of any pipe, valve, or tank to result in the loss of more than one EDG. For proper operation of the standby EDGs. it is necessary to ensure the proper quality of the fuel oil. Regulatory Guide 1.137 (Ref. 2) addresses the recommended fuel oil practices as supplemented by ANSI N195 (Ref. 3). The fuel oil properties governed by these SRs are the water and sediment content, the kinematic viscosity, specific gravity (or API gravity), and impurity level. Each EDG has an air start system with adequate capacity for five successive start attempts on the EDG without recharging the air start receiver (s). APPLICABLE The initial conditions of Design Basis Accident '(DBA) and SAFETY ANALYSES transient analyses in UFSAR Chapter 6 (Ref. 4), and Chapter 15 (Ref. 5) assume Engineered Safety Feature (ESF) systems are OPERABLE. The EDGs are designed to provide sufficient capacity, capability. redundancy, and reliability to ensure the availability of necessary power to ESF systems so that fuel Reactor Coolant System, and containment design limits are not exceeded. These limits are discussed in more detail in the Bases for Section 3.2. Power Distribution Limits: Section 3.4, Reactor Coolant System (RCS): and Section 3.6. Containment Systems. l FERMI UNIT 2 B 3.8.3 - 1 Revision 7 06/18/99
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l . l l
@ Diesel Fuel Oil and Starting Air B 3.8.3 l
I BASES APPLICABLE SAFETY ANALYSES (continued) Since diesel fuel oil and starting air subsystem support the hl . operation of the standby AC power sources, they satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). l LC0 Stored diesel fuel oil is required to have sufficient supply l for 7 days of full load operation. It is also required to I gl meet specific standards for quality. This requirement. in conjunction with an ability to obtain replacement supplies within 7 days, supports the availability of EDGs required to , shut down the reactor and to maintain it in a safe condition i for an anticipated operational occurrence (A00) or a postulated DBA with loss of offsite power. EDG day tank l fuel oil requirements, as well as transfer capability from the storage tank to the day tank, are addressed in LC0 3.8.1. "AC Sources-0perating." and LC0 3.8.2. "AC Sources - Shutdown. " l The starting air system is required to have a minimum capacity for five successive EDG start attempts without recharging the air start receivers. l , APPLICABILITY The AC sources (LC0 3.8.1 and LC0 3.8.2) are required to l ensure the availability of the required power to shut down l the reactor and maintain it in a safe shutdown condition l after an A00 or a postulated DBA. Because stored diesel fuel oil and starting air subsystem support LC0 3.8.1 and LC0 3.8.2. stored diesel fuel oil and starting air are required to be within limits when the associated EDG is ; required to be OPERABLE. ACTIONS- The ACTIONS Table is modfied by a Note indicating that separate Condition entry is allowed for each EDG, This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable i EDG subsystem. Complying with the Required Actions for one inoperable EDG subsystem may allow for continued operation, i and subsequent inoperable EDG subsystem (s) governed by l separate Condition entry and application of associated Required Actions. l I l FERMI - UNIT 2 B 3.8.3 - 2 Revision 7 06/18/99 l c
i l l l 1 I I l J j--.j Diesel Fuel Oil and Starting Air B 3.3.3 BASES !
. ACTIONS (continued).
M In'this Condition, the 7 day fuel oil supply for a required ) EDG is not available. However, the Condition is restricted ! , ~to fuel oil level reductions that maintain at least a 6 day i l supply. These circumstances may be caused by events such ' as:
- a. Full load operation required for an inadvertent start ,
- while at minimum required level
- or l l
, b. Feed and bleed operations that may be necessitated by I increasing particulate levels or any number of other l oil quality degradations. ; 1 < This restriction allows sufficient time for obtaining the requisite replacement volume and performing the analyses required prior to addition of the fuel oil to the tank. A i i period of 48 hours is considered sufficient to complete ' restoration of the required level prior to declaring the EDG inoperable. This period is acceptable based on the remaining capacity (> 6 days), the fact that procedures will be initiated to obtain replenishment. and the low i probability of an event during this brief period. l i This Condition is entered as a result of a failure to meet I the acceptance criterion for particulates in one or more required EDG storage tanks. Normally, trending of particulate levels allows sufficient time to correct high particulate levels prior to reaching the limit of acceptability. Poor sample procedures (bottom sampling), i- contaminated sampling equipment, and errors in laboratory I analysis can produce failures that do not follow a trend. Since the presence of particulates does not mean failure of ! the fuel oil to burn properly in-the diesel engine, since , particulate concentration 11 unlikely to change l significantly between Surveillance Frequency intervals, and since proper engine performance has been recently demonstrated (within 31 days). it is' prudent to allow a i brief period prior to-declaring the associated EDG inoperable. The 7 day Completion Time allows for further evaluation. resampling, and re analysis of the EDG fuel oil.
'l~. FERMI UNIT 2 B 3.8.3-3 Revision 7. 06/18/99 L
@ Diesel Fuel Oil and Starting Air B 3.8.3 BASES ACTIONS (continued) h! .
With the new fuel oil pro)erties defined in the Bases for l
$l SR 3.8.3.2 for new fuel t1at has already been added to a required EDG storage tank not within the required limits a l period of 30 days from the time of obtaining new fuel oil I sample results is allowed for restoring the stored fuel oil l properties. This period provides sufficient time to test the stored fuel oil to determine that the new fuel oil, when mixed with previously stored fuel oil, remains acceptable.
or to restore the stored fuel oil properties. This restoration may involve feed and bleed procedures. ; filtering, or combination of these procedures. Even if a. EDG start and load was required during this time interval and the fuel oil properties were outside limits. there is I high likelihood that the EDG would still be capable of
- performing its intended function.
l M A With a Required Action and associated Completion Time not l met, or the stored diesel fuel oil or starting air subsystem not within limits for reasons other than addressed by "l Conditions A through C. the associated EDG may be incapable i of performing its intended function and must be immediately I declared inoperable. SURVEILLANCE SR 3.8.3.1 REQUIREMENTS This SR provides verification that there is an adequate inventory of fuel oil in the storage tanks of each required EDG to support each EDG's operation for 7 days at full load. The 7 day period is sufficient time to place the unit in a safe shutdown condition and to bring in replenishment fuel from an offsite location. The 31 day frequency is adequate to ensure that a sufficient supply of fuel oil is available, since low level alarms are provided and unit operators would be aware of any large uses of fuel oil during this period. v l l FERMI UNIT 2 B 3.8.3 -4 Revision 7 06/18/99 e
l Diesel Fuel Oil and Starting Air
@l B 3.8.3 BASES SURVEILLANCE REQUIREMENTS (continued) gl SR 3.8.3.2 ,
The tests of fuel oil prior to addition to the storage tank l are a means of determining whether new . fuel oil is of the ! appropriate grade and has not been contaminated with ! substances that would have an immediate detrimental impact on diesel engine combustion. If results from these tests are within acceptable limits, the fuel oil may be added to the storage tanks without concern for contaminating the entire volume of fuel oil in the storage tanks. These tests are to be conducted prior to adding the new fuel to the storage tank (s), but in no case is the time between sampling (and associated results) of new fuel and addition of new fuel oil to the storage tank to exceed 31 days. The tests, limits, and applicable ASTM Standards for the new fuel oil tests listed in the Emergency Diesel Generator Fuel Oil Testing Program of Specification 5.5 are as follows:
- a. Sample the new fuel oil in accordance with ASTM D4057 88 (Ref. 6) h b. Verify that the sample has an API Gravity of within 0.3 degrees at 60*F or a specific gravity of within 0.0016 at 60/60*F. when compared to the suppliers certificate, or an absolute specific gravity at 60/60*F of a 0.83 and s 0.89 or an API gravity at 60'F of a 27* and 5 39*. Also, verify in accordance with the tests specified in ASTM D975 91 (Ref. 6) a kinematic viscosity at 40*C of a 1.9 centistokes and s 4.1 centistokes, and a flash point of a 125'F: and
- c. Verify that the new fuel oil has a clear and bright appearance with proper color when tested in accordance with ASTM D4176 86 (Ref. 6).
Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the LC0 since the fuel oil is not added to the storage tanks. Following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in Table 1 of ASTM D975 91 (Ref. 6) are met for new fuel oil when tested in accordance with ASTM D975 91 (Ref. 6), except that the analysis for sulfur may be performed in accordance with ASTM D1552 90 (Ref. 6) or ASTM D2622 87 (Ref. 6). v l FERMI UNIT 2 B 3.8.3 - 5 Revision 7 06/18/99 i
I L
. h' Diesel Fuel Oil and Starting Air B 3.8.3 4
BASES SURVEILLANCE-REQUIREMENTS (continued) These additional analyses are required by Specification !
'5.5.9, " Emergency Diesel Generator Fuel Oil Testing ;
Program " to be performed within 31 days following sampling ) and addition. This 31 days is intended to assure: 1) that
-the sample taken is not more than 31 days old at the time of adding the fuel oil to the storage tank, and 2) that the results of a new fuel oil sample (sample obtained prior to ,
addition but not more than 31 days prior to) are obtained '
-within 31 days after addition. The 31 day period is i acce) table because the fuel oil properties of interest, even if t1ey were not within stated limits, would not have an immediate effect on EDG operation.. This Surveillance ensures the availability of high quality fuel oil for the required EDGs.
Fuel oil degradation during long term storage shows up as an 'l increase in particulate, mostly due to oxidation. The I presence of particulate does not mean that the fuel oil will. not burn properly in a diesel engine. The particulate can cause fouling of filters and fuel 011' injection equipment, however, which can cause engine failure. Particulate concentrations should be determined in , accordance with ASTM D2276 88 (Ref. 6) Method A. This ! method involves a gravimetric determination of total ~ particulate concentration in the fuel oil and has a limit of 10 mg/1. It is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing. The Frequency of this test takes into consideration fuel oil degradation trends that indicate that particulate concentration is unlikely to change significantly between Frequency intervals, h- SR 3.8.3.3 This Surveill'ance ensures that, without the aid of the refill compressor, sufficient air start capacity for each ' EDG is available. The system design requirements provide for a minimum of five engine start cycles without recharging. The pressure specified in this SR is intended to reflect the-lowest-value at which the five starts can be accomplished. The 31 day Frequency takes into account the capacity, capability, redundancy.-and diversity of the AC sources and l c FERMI -' UNIT. '2 - B 3.8.3 - 6 Revision 7.. 06/18/99
l h Diesel Fuel Oil and Starting Air B 3.8.3 BASES > SURVEILLANCE REQUIREMENTS (continued)
< 1 other indications available in the control room, including. )
- alarms, to alert the operator to below normal air start pressure.
h SR' 3.8.3.4-Microbiological fouling is a' major cause of fuel oil i degradation. There are numerous bacteria that can grow in I fuel oil and cause fouling. but all must have a water environment in order to survive. Removal of water from the required EDG fuel storage tanks once every 31 days eliminates the necessary environment for bacterial survival. This is the most effective means of controlling i microbiological fouling. In addition, it eliminates the I potential .for water entrainment in the fuel oil during EDG operation. Water may come from any of several sources. I
-including condensation, ground water, rain water.
contaminated fuel oil, and from breakdown of the fuel oil by bacteria. Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 2). This SR is for preventive maintenance. The presence of water does not necessarily i represent failure of this SR, provided the accumulated water
,. is removed during performance of the Surveillance.
I i REFERENCES 1. UFSAR. Section 9.5.4.-
- 2. Regulatory Guide 1.137.
- 3. ANSI N195. 1976.
- 4. .UFSAR. Chapter 6.
- 5. UFSAR. Chapter 15.
- 6. -ASTM Standards: D4057 88: D975-91: D4176 86: D1552 90:
D2622 87: and D2276 88. l FERMI. - UNIT 2 B 3.8.3 -7 Revision 7 06/18/99 L
DC Sources-Operating B 3.8.4 BASES BACKGROUND (continued) Each DC battery subsystem is separately housed in a
. ventilated room a) art from its charger and distribution cente;rs. Each su) system is located in an physically and electrically from the othe, rarea separated subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels.
The batteries for DC electrical power subsystems are sized 4 to produce required capacity at 80% of nameplate rr.'ing. (n corresponding to warranted capacity at end of life cyt.1es
- a. and the 100% design demand. The minimum design voltage '
{ limit is 105/210 V. Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation. while at the same time maintaining its battery bank fully charged. Each battery charger has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 24 hours while supplyin0 normal steady state loads (Ref.11). APPLICABLE The initial conditions of Design Basis Accident (DBA) and SAFETY ANALYSES transient analyses in the UFSAR. Chapter 6 (Ref. 4) and Chapter 15 (Ref 5). assume that Engineered Safety Feature (ESF) systems are OPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the EDGs, emergency auxiliaries and control and switching during all MODES of operaticr. The OPErJSILITY of the DC subsystems is consistent with the initidi assumptions of the accident analyses and is based upon meeting the design basis of the unit. This includes maintaining sufficient DC sources OPERABl.E during accident conditions in the event of:
- a. An assumed loss of all offsite AC power or all onsite AC power; and
- b. A worst case single failure.
i The DC sources satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). 4 j FERMI -' UNIT 2 B 3.8.4- 2 Revision 7 06/18/99
DC Sources-0perating B 3.8.4 BASES LC0 . The DC electrical power subsystems-with each 'DC subsystem 1
.. consisting of two 130 VDC batteries in series, two battery J charpers,.and the corresponding control equi ment and
. interconnecting cabling supplying power to tw associated bus, are required to be OPERABLE to ensure the-availability 4 of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (A00) or a postubted DBA. Loss of any DC electrical power subsystes does not prevent the minimum safety function from being performed (Ref. 3).
APPLICABILITY The DC electrical power sources are required to be OPERABLE in MODES 1, 2, and 3 to ensure safe unit operation and to ensure that:
- a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of A00s or. abnormal transients: and
- b. Adequate core cooling is provided, and containment integrity and other vital functions are maintained in the event of.a postulated DBA.
The DC electrical power requirements for MODES 4 and 5 are addressed in the Bases for LC0 3.8.5, "DC Sources-Shutdown."
-ACTIONS A.1 and B.1 Conditions A and B represent one division with a loss of ability to completely respond to an event, cnd a potential loss of ability.to remain energized during normal operation.
If one of the re inoperable (e.g. ,quired DC electrical inoperable power subsystems battery, inoperable battery is charger (s), or inoperable battery charger and associated inoperable battery). the remaining DC electrical power subsystems have tne capacity to support a safe shutdown and to mitigate an accident condition. A subsequent worst case single failure could, however. result in the loss of minimum necessary DC electrical subsystems to mitigate a worst case accident. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the hlFERMIUNIT2 B 3.8.4 -3 Revision 7 06/18/99 i )
r ]m DC Sources-0perating B 3.8.4 (- i i BASES
. ACTIONS (continued) .
potential for com)lete loss of DC power to the affected-
. division. The 41our Completion Time (Required Action A.1) for restoration of an inoperable battery charger allows time to replace the inoperable charger with an OPERABLE spare battery charger, if available. The four hour limit is reasonable based on the remaining capability of the battery ,
to carry the loads for this period. The 2 hour limit for l Required Action B.1 is consistent with the allowed time for 1 an inoperable DC Distribution System division. The 2 hour Completion Time is based on Regulatory Guide 1.93 (Ref. 6) and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown. C.1 and C.2 If the station service DC ' electrical power subsystem cannot be restored to OPERABLE status within the required Completion Time.-the unit must be brought to a MODE in which the LC0 doe not apply. To achieve this status, the unit must be brought to at least MODE.3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the l required plant conditions from full power conditions in an j orderly manner and without challenging plant systems. The ' Completion mae to bring the unit to MODE 4 is consistent I with the time required in Regulatory Guide 1.93 (Ref. 6).
. SURVEILLANCE SR- 3.8.4.1 REQUIREMENTS l Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effecti'leness of the ;
charging system and the ability of the batteries to perform their intended function. . Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a batiery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are
. consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with ,
manufacturer recommendations and IEEE 450 (Ref. 7). ;
- gFERMIUNIT2 B 3.8.4 -4 Revision 7, 06/18/99 L _
L i DC Sources-Operating ! B 3.8.4 l i l BASES- . i SURVEILLANCE REQUIREMENTS'(continued) SR 3.8.4.2-Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each
; inter-cell and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.
The connection resistance limits procedurally established , for this SR are no more than 20% above the resistance as l measured during installation and not above the ceiling value established by the manufacturer. This provides conservative measures to assure the Technical ~ Specification limit is not exceeded. The Frequency for these inspections, which can detect conditions that can cause power losses due to resistance heating.- is 92 days. This Frequency is considered acceptable based on operating experience related to detecting corrosion trends. SR 3.8.4.3- . Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.. The presence of physical damage or d deterioraticn does not necessarily represent a failure of J this SR. provided an evaluation determines that the physical 4 , damage or deterioration does not affect the OPERABILITY of the battery (its ability to perform its design function). The 18 month Frequency is based on engineering judgement, taking intn consideration the desired plant conditions to ' perform the Surveillance. -Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency. Therefore, the Frequency is considered acceptable frou a standpoint of maintaining reliability.
.s
- l - FERMI . UNIT _2 B 3.8.4 - 5 Revision 7, 06/18/99
f B tery Cell Parameters B 3.8.6 BASES SURVEILLANCE REQUIREMENTS (continued) Category C defines the limits for each connected cell. These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function and maintain a margin of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and the battery must be declared inoperable. l The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value for voltage is based on IEEE 450 (Ref. 3), which ; states that a cell voltage of 2.07 V or below, under float - conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement. ,' The Category C limit on average specific gravity a 1.190. is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit, it is required that the specific gravity foi each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery. M 4 Footnote (b) to Table 3.8.6-l'is applicable to Category A. Ql B, and C specific gravity. Footnote (b) of Table 3.8.6-1 , i requires the above mntioned correction for electrolyte level and temperature. Because of specific gravity gradients that are produced during the recharging process, delays of several days may occur while waiting for the specific gravity to stabilize. A stabilized charger current is an acceptable alternative to s)ecific gravity measurement for determining the state of n curge of the designated pilot cell. This phenomenon is
,L discussed in IEEE 450 (Ref. 3). Footnote (c) to (l Table 3.8.6 1 is applicable to Category A and C. and allows the float charge current to be used as an alternate to specific gravity.
l FERMI - UNIT 2 B 3.8.6- 6 Revision 7.. 06/18/99 i s .}}