ML20035F950
| ML20035F950 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/16/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035F951 | List: |
| References | |
| NPF-06-A-146 NUDOCS 9304230117 | |
| Download: ML20035F950 (8) | |
Text
p.
i
. +# 's* **n i.
'e, UNITED STATES 1,
NUCLEAR REGULATORY COMMISSION
, y, o,i wassiwarow. o. c.rosss
\\....+/
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.146 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the I
licensee) dated June 27, 1991, as suppplemented April 29, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended-(the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter.1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (i) that the activities' authorized by this amendment can be conducted without endangering the health and l
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of.the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9304230117 930416 PDR ADOCK 05000368 P
l.
l i
l l
1 i 2.
Accordingly, the license is amended by changes.to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.146, are hereby incorporated.in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
The license amendment is effective as of 30 days from its date of issuance.
1 I
FOR THE NUCLEAR REGULATORY COMMISSION i
/g,.s (
W j
s George T. Hubbard, Acting Director!
Projact Directorate IV-1 Division of Reactor Projects - III/IV/V i
Office of Nuclear Reactor Regulation-
Attachment:
Changes to the Technical l
Specifications Date of Issuance: April 16, 1993-I f
.}
I b
k i
1
ATTACHMENT TO LICENSE AMENDMENT NO. 146 FACILITY OPERATING LICENSE NO. NPF-6
)
DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and
.i contain vertical lines indicating the area of change. The corresponding i
overleaf pages are also provided to maintain document completeness.
j l
REMOVE PAGES INSERT PAGES 3/4 8-11 3/4 8-11 I
3/4 8-12 3/4 8-12 3/4 8-17a 3/4 8-17a B 3/4 8-1 B 3/4 8-1 B 3/4 8-2 i
d 1
.n j
L ELECTRICAL POWER SYSTEMS CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES i
LIMITING CONDITION FOR OPERATION 3.8.2.5 All containment peretration conductor overcurrent protective devices j
shown in Table 3.8-1 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the containment penetration conductor overcurrent I
protective devices shown in Table 3.8-1 inoperable:
f De-energire the circult(s) by tripping the associated backup circuit a.
breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verifying the backup circuit breaker to be tripped at least once per 7 days thereafter, or
[
b.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD j
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l ERVEILLANCE_ REQUIREMENTS 4.8.2.5 All containment penetration conductor overcurrent protective devices shown in Table 3.8-1 shall be demonstrated OPERABLE in accordance with the manufacturers' recommendations:
l a.
At least once per 18 months 1.
For at least one 6.9 kv reactor coolant pump circuit, such that all reactor coolant pump circuits and their associated backup j
circuits are demonstrated OPERABLE at least each 72 months, by performance of:
(a) A CHANNEL CALIBRATION of the associated protective I
relays, and (b) An integrated system functional test which includes simulated.utomatic actuation of the system and verifying that each relay and associated cir:uit breakers and control circuits function as designed.
2.
For each type of 480 volt air frame protective device, such
-that all 480 volt air frame protective devices are demonstrated OPERABLE at least once each N x 18 months, where N is the j
number of devices of each type, by performance of:
i l
(a) A calibration of the protective relays for devices that
[
are actuated by protective relays which includes verification of the range, accuracy, and alarm / trip l
capability, and j
I ARKANSAS - UNIT 2 3/4 8-11 Amendment No. 75,Z24,146 i
1 f
s.
4 ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
(b) A functional test of protective devices that are actuated i
by protective relays which verifies that the protective device trips when its associated protective relays actuate, and (c) A functional test which consists of injecting primary t
current in each overcurrent element mounted on the i
protective device at the specified setpoint and verifying that the protective device trips when each overcurrent element actuates.
If any protective device fails to function as designed, all other protective devices of the same type shall be tested.
3.
For molded case protective devices, such that all protective devices of each type are demonstrated OPERABLE at least once each N x 18 months, where N is th9 number of devices of each i
type, by performance of:
(a) A functional test of at least one protective device of each type which consists of injection of primary current at the specified setpoint to the protective device and t
verifying that the protective device trips when the overcurrent elements are actuated.
If any protective device fails to function as designed, all other protective devices of the same type shall be tested.
b.
At least once per 60 months, by performing inspections and preventive maintenance on each protective device in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
ARKANSAS - UNIT 2 3/4 8-12 Amendment No. 55,146
I s-i i
TABLE 3.8-1 (Continued)
CONTAINMENT P,ENE1 RATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES Primary Backup Location j
Device Device
-of System Number Number Devices Powered 52-54G2 52-54C5 MCC 2B54 Hz Purge Containment Iso. Valve i
2CV-8233 i i
52-54G3 52-54B4 MCC 2B54 Hz Purge l
Containment Iso. Valve 2CV-8259-2 t
52-54J2 52-54J3' MCC 2854 Containment i
Elevator i
Motor 2MM6 I
f 52-54K2 52-54J4 MCC 2854 Containment Building Lighting i
Pane) 27 LA
-l
~
52-54K3 52-54JB MCC 2854 RCP 2P3A 011 j
Lift Pumps-2P63Al & A2-i 52-54K4 52-54F3 MCC 2854 RCP 2P328 011 b
Lift Pumps l
2P63B1 & B2 l
t 52'61A4 52-C1H3 MCC 2B61 Reactor. Cavity Cooling Fan i
2VSF348-2 l
l 52-61D3 52-61H4 MCC 2861 Containment l
Recircu1ating I
Fan 2VSF318-2:
l 52-61D4 52-61H5 MCC 2B61 Containment Recirculating Fan 2VSF310-2 l
ARKANSAS - UNIT 2 3/4 8-17 Amendment No. 35, 69 l
l
~l
a 4
I l
TABLE 3. 8-1 (Continued) r CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTICTIVE DEVICES Primary Backup Location i
Device Device of System Number Number Devices Powered 52-61F2 52-61H6 MCC 2B61 Safety Inject.
Tank 2T2C i
Discharge MOV 2CV-5043-2.
l 52-61G2 52-61K8 MCC 2B61 Check Valve
[
Leakage Drain Valve 2CV-5106-2 J
52-31G1 52-31G2 MCC 2B31 Pzr Spray
[
Isolation Valve 2CV-4654 52-41F4 42-41F5 MCC 2B41 Pzr Spray Isolation Valve 2CV-4656 i
I l
ARKANSAS - UNIT 2 3/4 6-17a Amendment No. 75, 67, 146
3/4.B rLECTRICAL POWER EYSTEME I
i RAFTF The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be -
~
available to supply the safety-related equipment required for 1) the safe i
shutdewn of the facility and 2) the sitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systans satisfy the requirenants of General Design Criteria 17 of Appendiz "A" to 10 CFR 50.
i The ACY10N requirements specified for the levels of degradation of the i
power sources provide restriction upon continued facility operation corrensurate with the level of degradation. The OPERABILITY of the power i
sources are consistent with the initial condition assumptions of the accident analyses and are based upon saintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systear OPERABLE during accident conditions coincident with an assumed loss of I
offsite power and single failure of the other onsite A.C. source. ACTION requirenents are consistant with Generic Letter 84-15, " Proposed Staff Actions to Irprove and Maintain Diesel Generstor Reliability."
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling i
condition for extended tire periods ar' 2) sufficient instrumentation and control espability is available for moi.noring and maintaining the unit status.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory i
Guides 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies", March lo,1971, and 1.108 " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power systems at Nuclear Power Plants".'od in Revision 1, August 1977 and Generic Letter 84-15. Load Ranges provid i
surveillances are allowed to avoid routine overloading of diesel generators.
Load in excess of these lead ranges for special testing, momentary variation f
due to chergir.g bus leads, or short term variations shall not invalidate l
survelliance tests. For the purpose of surveillance testing, the ters
" standby condition" is defined as the approximate terperature range of the i
jacket cooling water and engine lobe oil susp morsally maintained by the j
engine keep ware systers. An exception to this definition is the engine
~
conditions that exist when performing the bot restart test following the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ED3 endurance run. When performing this test, the engine is maar normal operating tenperature when in a " standby condition". Additionally, this definition includes the allowance to perform engine prelubrication prior to all planned test starts.
r The Diesel Generator Test Schedule. Table 5.8-1 has been developed for the purpose of determining testing requirements based on the number of failures and valid tests using the example provided in Generic Letter 84-15 using a per diesel generator unit basis..The criteria of R.G.I.108 position C.2.s is used for criteria determination.
f i
ARKANSAS - UNIT 2 B 3/4 8-1 Amendment No. Mbr 140 f
^
~
4 3/4.8 ELECTRICAL POWER SYSTEMS BASES Containment electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance. The 480 volt air frame protective devices utilize electro-mechanical overcurrent elements which are mounted on the protective device and, in some instances, l
protective relays to trip the protective device. Actuation of the overcurrent element or relay will trip the protective device. The molded case protective devices utilize magnetic or thermal-magnetic overcurrent elements which are contained in the protective device. Actuation of each overcurrent element will trip the protective device.
t i
ARKANSAS - UNIT 2 B 3/4 8-2 Amendment No.
146 O