ML20035C747
| ML20035C747 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/26/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035C751 | List: |
| References | |
| NUDOCS 9304090057 | |
| Download: ML20035C747 (5) | |
Text
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION E
W ASHINGTON, D. C. 20555 o
ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.164 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated September 28, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and tne Commission's rules cnd 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 4
of the Commission's regulations and all applicable requirements hava l
been satisfied, i
0304090057 930326 PDR ADOCK 05000313 P
. 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. DPR-51 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 164, 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 THE NUCLEAR REGULATORY COMMISSION
.pb 77lC' George T. Hubbard, Acting Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1993 6
ATTACHMENT TO LICENSE AMENDMENT NO. 164 i
FACILITY OPERATING LICENSE NO. OPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES P
37 37 39 39 a
1 i
(I) The engineered safety features valves associated with each of the above systems shall be operable or locked in the ES position.
3.3 2 In addition to 3.3.1 above, the following ECCS equipment shall be operable when the reactor coolant system is above 350F and irradiated fuel is in the core:
( A) Two out of three high pressure injection (makeup) pumps shall ba maintained operable, powered from independent essential buses, to provide redundant and independent flow paths.
(B) Engineered safety features valves associated with 3.3.2.a above shall be operable or locked in the ES position.
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall be operable when the reactor coolant system is above 800 psig:
( A) The two core flooding tanks shall each contain an indicated minimum of 1310.4 feet (1040130 ft') of borated water at 600 1 25 psig.
(B) Core flooding tank boron concentration shall not be less than 2270 ppm boron.
(C) The electrically operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged.
(D) One of the two pressure instrument channels and one of the two level instrument channels per core flood tank shall be operable.
3.3.4 The reactor shall not be made critical unless the following equipment in addition to 3.3.1, 3.3.2, and 3.3.3 above is operable.
(A) Two reactor building spray pumps and their associated spray nozzle headers and two trains of reactor building emergency cooling.
The two reactor building spray pumps shall be powered from operable independent emergency buses and the two reactor building emergency cooling trains shall be powered from operable independent emergency buses.
(B) The sodium hydroxide tank shall contain an indicated of18['O wt % s luti n s dium hydroxide.
33.2 1 1.8 ft.
(C) All manual valves in the main discharge lines of the sodium hydroxide tanks shall be locked open.
Amendment No. 2f,17,JJJ J45,164 37
370,100 gallons of boreted wstor cro cupplied for caergency coro cooling cnd reactor building spray in the event of a loss-of-coolant accident. This amount fulfills requirements for energency core cooling. Approximately 16,000 gallons of borated water are required to reach cold shutdown. The original nominal borated water storage tank capacity of 380,000 gallons is based on refueling volume requirements. Heaters maintain the borated water supply at a temperature to prevent crystallization and local freezing of the boric acid. The boron concentration is set at a value that will maintain the core at least 1 percent Ak/k subtritical at 70*F without any control rods in the core. The concentration for 1% ak/k subtriticality is 1609 ppm boron in the core, while the minimum value specified in the borated water storage tank is 2270 ppm boron.
Specification 3.3.2 assures that above 350*F two high pressure injection pumps are also available to provide injection water as the energy of the reactor coolant system is increased.
Specification 3.3.3 assures that above 800 psig both core flooding tanks are operational.
Since their design pressure is 600 1 25 psig, they are not brought into the operational state until 800 psig to prevent spurious injection of borated water. Both core flooding tanks are specified as a single core flood tank has insufficient inventory to reflood the core.(1)
Specification 3.3.4 assures that prior to going critical the redundant train of reactor building emergency cooling and spray train are operable.
The spray system utilizes common suction lines with the low pressure injection system. If a single train of equipment is removed from either system, the other train must be assured to be operable in each system.
Reference 6 provides an assessment of the impact of level indicator instrument error on the allowed NaOH tank level variation. Note that the indicated level variation of 33.2 1.8 feet includes an allowance for instrument loop error.
l When the reactor is critical, maintenance is allowed per Specification 3.3.5.
Operability of the specified components shall be based on the results of testing as required by Technical Specification 4.5.
The maintenance period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is acceptable if the operability of equipment redundant to that removed from service is demonstrated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to removal. Exceptions to specification 3.3.6 permit continued operation for seven days if one of two BWST level instrument channels is operable or if either the pressure or level instrument channel in the CFT instrument channel is operable.
In the event that the need for emergency core cooling should occur, functioning of one train (one high pressure injection pump, one low pressure injection pump, and both core flooding tanks) will protect the core and in the event of a main coolant loop severance, limit the peak clad temperature to less than 2200*F and the metal-water reaction to that representing less than 1 percent of the clad.
The service water system consists of two independent but interconnected, full capacity, 100% redundant systems, to ensure continuous heat removal.(4)
One service water pump is required for normal operation. The normal operating requirements are greater than the emergency requirements following a less-of-coolant accident.
Amendment No. J/0,2/E,164 39 REVISED BY NRC LETTER DATED:
9/31/91; 7/16/92