ML20216D576
| ML20216D576 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/12/1998 |
| From: | William Reckley NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216D581 | List: |
| References | |
| NPF-06-A-188 NUDOCS 9803170144 | |
| Download: ML20216D576 (5) | |
Text
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c ut p-UNt(ED STATES s
j NUCLEAR REGULATORY CCMMISSION
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WASHINGTON, D.C. 3000Nm01 ENTERGY OPERATIONS. INC.
DOCKET No,5&365 ARKANSAS NUCLEAR ONE. UNIT NO,2 AMENCWlENT TO FAC)LITY OPERATING LICENSE Amendment No.188 License No. NPF-6 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
I-A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated July 21,1997, complies with the standards and requirements of the Atomic i
Energy Act of 1954, as amended (the Act), and the Commission's rules and i
regulations set forth in 10 CFR Chapter I; 3.
The facility will operate in conformity with the application, the provisions of the
- l Act, and the rules and regulations of the Commission; i
C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfMHl.
1 i
l 9803170144 980312 PDR ADOCK 05000368 P
2 2.
Accordingly, the license is amended by changes to the Technical Specircations as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating Ucense No NPF-6 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.184 are hereby incorporated in the licer.se. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
William Reckley, Project Mana r Project Directorate IV.1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulati>n
Attachment:
Changes to the Technical Specifications
)
Date ofissuance: March 12, 1998
1 ATTACHMENT TO LICENSE AMENDMENT NO.188 FACILITY CPERATING 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 Ame' dment number and contain vertical lines indicating the n
area of change. The corresponding overieaf pages are also provided to maintain document completeness.
REMOVE PA_QE1 INSERT PAGES 3/47-5 3/4 7-5 W474 N474 B 3/4 7-1 B 3/4 7-1 B 3/4 7-2 B 3/4 7-2 i
i i
j
e PLANT SYSTCMS EMERGEg'CY TEEDWATER SYSTEM l
LIMITING CONDITION FOR OP,F 3.7.1.2 Two amargenel 4 and associated flow paths shall be OPERABLE withs a.
One motor driver. pump ca, sie of being powered from an OPERABLE emergency bus, had b.
One turbine driven pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:
NODES 1, 2, and 3 ACTION:
With one emergency feedwater pump inoperable, restore the inoperable pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS I
1 4.7.1.2 Each emergency feedwater pump shall be demonstrated OPERABLE:
j i
a.
At least once per 31 days by:
1.
Verifying that each valve (manual, power operated or l
automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
In accordance with Specification 4.0.5 by:
1.
Verifying the developed head of each EFW pump at the flow test point is greater than or equal to the required developed head.
This surveillance requirement is not required to be performed for the turbine driven EFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding j
700 psia in the steam generators.
ARKANSAS - UNIT 2 3/4 7-5 Amendment No. H,H 4,188
e PIANT SYSTEMS SURVEILIANCE REQUIREMENTS (Continued) c.
At least once per 18 months by:
l 1.
Verifying that each automatic valve in the flow path actuates to its correct position on MSIS or ETAS test signals.
2.
Verifying that the anotor driven punp starts automatically upon receipt of an ETAS test signal.
i 3.
Verifying that the turbine driven pump steam supply MOV l
opens automatically upon receipt of an ETAS test signal.
d.
By verifying proper alignment of the required Erw flow paths by verifying flow from the condensate storage tank to each steam generator. This SR is required to be verified prior to entering MODE 2 whenever plant has been in MODES 4, 5, 6, or defueled for
> 30 days.
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l l
l l
l ARKANSAS - UNIT 2 3/4 7-6 Amendment No. 64,188
3/4.7 PLANT SYSTEMS RASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY CYCLES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% of its design pressure of 1100 psia.during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a turbine trip fram 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. The "as-found" requirements are j
conservative with respect to Section XI of the ASME Boiler and Pressure i
Vessel Code, 1986 Edition, and Addenda through 1987. The total relieving capacity for all MSSVs is 14,804,000 lb/hr. The ANO-2 full power (100%) steam flow plus 2% for conservatism is 12,950,000 lb/hr.
Therefore, the total relieving capacity of the MSSVs is 114.32% of the 1026 power steam flow through each main steam header. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat.
STARTUP and/or POWER OPERATION is allowable ith safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary syster, steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels. The reactor trip setpoint reductions are derived on the following bases:
SP = (X) - (Y) x (114.32%)
X where reduced reactor trip setpoint in percent of RATED SP
=
THERMAL POWER 114. 32 % =
Total maximum safety valve relieving capacity of 102% power steam flow-Total relieving capacity of all safety valves per steam X
=
line in lbs/ hour Total Maximum relieving capacity of the inoperable safety Y
=
valve (s) in lbs/ hour.
In each case, the valves with the greatest relieving capacity were assumed inoperable.
ARKANSAS - UNIT 2 5 3/4 7-1 Amendment No. MG,Me,188
e PLANT SYSTEMS e
EASES 3/4.7.1.2 EMERGENCY TEEDWATER SYSTEM The OPERABILITY of the emergency feedwater (EFW) system ensures that the Reactor Coolant System can be cooled down to Shutdown Cooling (SDC) entry conditions from normal operating conditions in the event of a total loss of off-site power.
The EFW system is designed to supply sufficient water to the steam generator (e) to remove decay heat with steam generator pressure at'the setpoint of the MSSVs. Subsequently, the ErW system supplies sufficient water to cool the unit to SDC entry conditions, and steam is released through the ADVs.
I SR 4.7.1.2.b.1 verifies that each ErW pump's developed head at the flow l
test point is greater than or equal to this required developed head. This test ensures that ErW pump performance has not degraded during the cycle.
Flow and differential head are normal tests of pump performance required by Section XI of the ASME Code.
Because it ja undesirable to introduce cold ErW into the steam generators while they are operating, this testing is performed on recirculation flow. This test confirms one point that is indicative of pump overall performance.
Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance.
Performance of inservice testing, discussed in the ASME Code,Section XI, satisfies this requirement. The SR for the turbine driven EFW pump is allowed to be deferred for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 700 psia in the steam generators. This allowance will ensure the test is completed within a reasonable period of time after establishing sufficient steam pressure to perform the test.
SR 4.7.1.2.c ensures that ErW can be delivered to the appropriate steam generator, in the event of any accident or transient that generates an EEAS signal. This is assured by demonstrating that each automatic valve in the flow path actuates to its correct position on an actual or simulated actuation signal. The 18 month frequency is based on the need to perform the SRs under the conditions that apply during a unit outsge and the potential for an unplanned transient if the SRs were performed with the reactor at power.
SR 4.7.1.2.d ensures that the EFW System is properly aligned by verifying the flow path from the condensate storage tank (CST) to each steam generator prior to entering MODE 2 operation, after more than 30 days below MODE 3.
OPERABILITY of the ErW flow paths must be verified before sufficient core heat is generated that would require the operation of the ErW System during a subsequent shutdown. The Frequency is reasonable, based on engineering judgment, and other administrative controls to ensure that flow paths remain OPERABLE. To further ensure ErW System alignment, the OPERABILITY of the flow paths is verified following extended outages to determine that no misalignment of valves has occurred. This SR ensures that the flow path from the CST to the steam generators is properly aligned.
3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at i
HOT STANDBY conditions for one hour with steam discharge to atmosphere I
with concurrent with total loss of off-site power. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
ARKANSAS - UNIT 2 B 3/4 7-2 Amendment No. MO,188