ML20044G319
| ML20044G319 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/19/1993 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044G320 | List: |
| References | |
| NUDOCS 9306020324 | |
| Download: ML20044G319 (7) | |
Text
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' e na, UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO, 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.163 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated April 23, 1993, as supplemented by letter dated May 7, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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 satisfied.
9306020324 930519 PDR ADOCK 05000298 p
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Accordingly, the license is amended by changes to the Technical Specifi-j cations as indicated in the attachment to this license amendment and -
Paragraph 2.C.(2) of'F).cility Operating License No. DPR-46 is hereby j
amended to read as follows:
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2.
Technical Specifications The Technical Specifications contained in Appendix 4, as revised l
through Amendment No.163, are hereby incorporated in the license.
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 T 'NpCLEARREGULATORY_COMMIS ah" t u.W
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l Te ence L. Chan, Acting Director i
Project Directorate IV-1 Division of-Reactor Projects III/IV/V Office of Nuclear Reactor Regulation-
Attachment:
. Changes to the Technical Specifications Date of Issuance: May 19, 1993 r
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ATTACHMENT TO LICENSE AMENDMENT NO.163 i
FACILITY OPERATING LICENSE NO. DPR-46 i
DOCKET NO. 50-298 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 11 ii 123 123 l
128 128 215b 215b i
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TABLE OF CTUFCS (cont' i)
Pare 'e St.7*.'EI L92:CE
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- EI AND -:'NTA:.'C'ENT COOL; :G SYSTEMS L.E
- 1
- 131 A.
Core Spray and LPCI Systems A
114 B.
RER Service Water System B
116 C.
HPCI System 117
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D.
RCIC System D
118 E.
Automatic Depressurization System E
119 F.
Minimum Low Pressure Cooling System Diesel Generator Availability F
120 G.
Maintenance of Filled Discharge Pipe G
122-3.6 PRIMARY SYSTEM BOUNDARY 4.6 132 - 158 A.
Thermal and Pressurization Limitations A
132 1
S.
Coolant Chemistry B
133a C.
Coolant Leakage C
135 D.
Safety and Relief Valves D
136 E.
Jet Pu=ps E
137 T.
Recirculation Pump Flow Mismatch F
137 G.
Inservice Inspection G
137 H.
Shock Suppressors (Snubbers)
H 137a 3.7 CONTAINMENT SYSTEMS 4.7 159 - 192 A.
159 B.
Standby Cas Treatment System B
165 C.
165a D.
Primary Containment Isolation Yalves D
166 3.B MISCELLANEOUR RADI0 ACTIVE MATERIAL SOURCES 4.8 185 - 186 2.9 AUX;LIARY ELECTRICAL SYSTEMS 4 '. 9 193 - 2d2' A.
Auxiliary Electrical Equipment A
193 B.
Operation with Inoperable Equipment B
195 3.10 CORE ALTERATIONS 4.10 203 - 209 A.
Refueling Interlocks A
203 B.
Core Monitoring B
205 C.
Spent Fuel Fool Water Level C
205 D.
Time Li=itation D
206 E.
Spent Feel Cask Handling E
206 3.11 FUEL RODS 4.11 210 - 214e A.
Average Planar Linear Heat Generation Rate (APLHGR)
A 210 B.
Linear Heat Generation Rate (LHGR)
B 210 i
C.
Minimum Critical Power Ratio (MCPR)
C 212 Amendment No. 95,97.100,154,163 w er
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4 "INTENTIo': Atty try7 n _.3.
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i hendment No. M,163 i
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l 3.5 PASES (cont'd) of service.
Specification 3.5.F.4 provides that should this occur, no work will be performed on the primary system which could lead to draining the vessel. This work vould include work on certain control rod drive components and recirculation system.
s Thus, the specification precludes the events which could require core cooling.
l Specification 3.5.F.5 recognizes that, concurrent with control rod drive maintenance during the refueling outage, it may be necessary to drain the suppression chamber for maintenance or for the inspection required by Specification 4.7sA.2.h. In this case, if excessive control rod housing leakage occurred, three levels of protection against loss of core cooling would exist. First, a special flange would be used to stop the t
leak.
Second, sufficient inventory of water is maintained to provide, under vorst case leak conditions, approximately 60 minutes of core cooling while attempts to secure the leak are made. This inventory includes water in the reactor well, spent j
fuel pool, and condensate storage tank.
If a leak should occur, manually operated valves in the condensate transfer system can be opened to supply either the Core Spray System or the spent fuel pool.
Third, sufficient inventory of water is maintained to permit the water which has drained from the vessel to fill the torus to a level above the Core Spray and LPCI suction strainers. These systems could then recycle the water to the vessel.
Since the system cannot be pressurized during refueling, the potential need for core flooding only exists and the specified combination of the Core Spray or the LPCI subsystems can provide this.
This specification also provides for the highly unlikely case that both diesel generators are found to be inoperable. The reduction of rated power to 25% vill provide a very stable operating condition. The allowable repair time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will provide an opportunity to repair the diesel and thereby prevent the necessity of taking the plant down through the less stable shutdown condition.
If the necessary repairs cannot be made in the allowed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the plant will be shutdown in an orderly fashion. This will be accomplished while the two off-site sources of power required by Specification 3.9.A.1 are available.
G.
liaint en anc e of Filled Direharre Fire x
If the discharge piping of the Core Spray, LPCI, HPCI, and ICIC systems are not filled, a water hammer can develop in this piping when the pump and/or pumps are started.
If a water hammer vere to occur at the time at which the system were repir( d, tr.e system would still perform its design functions. F.ovever, to minimire da= age to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the syste::: is in an operable condition.
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a Amendment No. 57,97,M3,163
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CONDITIONS FOR OPERATION-SURVEILIANCE REOUIREMENTS 3.12 (cont'd) 4.12 (cont'd)
B.
Reactor Ecuirment Cooling (REC)
B.
Resetor Eeulement Cooline (REC)
L System System 1.
Both Reactor Equipment Cooling sub-1.
REC System Testing systems and their associated pumps shall be operable whenever irradiat-Itaa Frecuenev ed fuel is in the vessel or the spent fuel pool, except as specified a.
Pump Operability Once/ Month in 3.12.B.2 and 3.12.B.3 below.
b.
Motor operated Once/ Month Valve Operability c.
Pump flow rate Once/3 months Each pump shall and after pump deliver 1175 gym maintenance at 65 psid.
d.
System head tank Daily level shall be monitored.
"2.
From and after the date that any 2.
When it is determined that'any ac-component that affects operability tive component that affects opera-in one REC subsystem becomes inop-bility of an REC subsystem is inop-erable, continued reactor operation erable, all active components that is permissible during the succeeding affect operability of the operable thirty days provided that during REC subsystem.shall be verified s=h thirty days all the active operable immediately and weekly components that affect operability thereafter.
of the operable REC subsystem, the active components that affect opera-l bility of the Core Standby Cooling i
Systems, the diesel generator asso-ciated with the operable subsystem are eperable.
l The allowable repair time does not apply when the reactor is in the shutdown mode and reactor pressure is less than 75 psig.
l 3.
Both REC subsystems with one pump per subsystem shall be operable as stated in 3.12.B.1 and 3.12.B.2 l
above during reactor head-off opera-l tions requiring LPCI or Core Spray l
system availability or Service Water l
cooling shall be available.
4.
If the requirements of 3.12.B.1 l
through 3.12.B.3 cannot be met, the i
reactor shall be shutdown in ' an orderly manner and in the Cold Shut-down condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or operations requiring LPCI or Core I
Spray system availability shall be halted.
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-215b-Amendment No. S0,1M,152,163
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