ML20055G025
| ML20055G025 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/06/1990 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | Entergy Operations |
| Shared Package | |
| ML20055G026 | List: |
| References | |
| DPR-51-A-132, NPF-06-A-107 NUDOCS 9007200068 | |
| Download: ML20055G025 (10) | |
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UNITED STATES l'
NUCLEAR REGULATORY COMMISSION
,l, WASHINGTON, D. C. 70566
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- t E,NTERGY OPERATIONS,,INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE,, UNIT,1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company, dated April 10, 1990, 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 I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health.
4 and 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 cosamn 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.
1 9007200068 900706 PDR ADOCK 05000313 P
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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.132, 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 i
Richard F. Dudley, Acting Director Project Directorate IV-1 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications.
Date of Issuance:
July 6,1990
3TTACHMENT T011CENS!,AMENpMENT,,NO.1.3,1 FACIllTY OPERATING LICENSE NO._DPR;51 DOCKETNO.50-3Q Pavise 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 95 95 97 97 0
4 e
s
- 4.5.2
! Reactor Builatina Ceolina Systems.
l Applicability, Applier to testing of the reactor building cooling systems.
-Ob.iective To verify that the reactor building cooling systems are operable.
-Specification 4.5.2.1 System Tests 4.5.2.1.1 Reactor Buildina Spray System (a) Once every 18 months, a system test shall be conducted to demonstrate proper operation of the system.
A test signal will be applied to demonstrate actuation of the reactor building spray system (except for reactor building inlet valves to prevent water entering nozzles).
(b) Station compressed air or smoke will be introduced into the spray headers to verify the availability of the headers and spray nozzles at least every five years.
(c) The test will be considered satisfactory if visual observation and control board indication verifies that all components have responded to the actuation signal properly.
4.5.2.1.2 Reactor Buildina Coolina System (a) At least once per 14 days, each reactor building cooling group shall be tested to demonstrate proper operation of the system.
The test shall be performed in accordance with the procedure summarized below:
-(1) Verifying a service water flow rate of it 1200 gpm to each group of cooling units.
(2) Addition of a biocide to the service water during the
(
surveillance in 4.5.2.1.2.a.1 above, whenever service water temperature is between 60F and 80F.
(b) At least once per 31 days, each reactor building cooling group shall be tested to demonstrate proper operation of the system.
The test shall be performed in accordance with the procedure summarized below:
(1) Starting (unless already operating) each operational cooling unit from the control room.
Amendment No. 25, 62, 132 95
Addition of a biccide to service watcr is performed during reactor l'
building cooler surveillance to prevent buildup of Asian class-in the coolers when service water is pumped through the cooling coils.
This is performed when service water temperature is between 60F and 80F since in this water temperature range Asian clams can spawn and produce larva which could pass through service water system strainers.
The delivery capability of one reactor building spray pump at a time can be tested by opening the valve in the line from the borated water storage tank, opening the corresponding valve in the test line, and starting the corresponding pump.
Pump discharge pressure and flow indication demonstrate performance.
With the pumps shut down and the borated water storage tank outlet closed, the reactor building spray injection valves can each be opened and closed by operator action. With the reactor building spray inlet valves closed, low pressure air or smoke can be blown through the test connections of the reactor building spray nozzles to demonstrate that the flow paths are open.
The equipment, piping, valves, and instrumentation of the reactor building cooling system are arranged so that they can be visually inspected.
The cooling units and associated piping are located outside the secondary concrete shield.
Personnel can enter the reactor building during power,
operations to inspect and maintain this equipment.
The service water piping and valves outside the reactor building are inspectable at all times.. Operational tests and inspections will tHe performed prior to initial startup.
Two service water pumps are normally operating.
At least once per month operation of one pump is shifted to the third pump, so testing will be unnecessary.
The reactor building fans are normally operating, so testing is unnecessary. -
Reference FSAR, Section 6 q
Amendment No. 25, 52, 132 97 J
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ac 8-UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C 20666 1
ENTERGY OPERATIONS. I.N..C.
ECKETNO.50-368 j
ARKANSAS NUCLEAR ONE. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENS,E Amendnent No.107 License No. NPF-6 1.
The Nuclear Regulatory Conunission (the Consission) has found that:
A.
The application for anendment by Arkansas Power and Light Company, dated April 10, 1990, 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, as amended, the provisions of the Act, and the rules and regulations of the Cosmission; C.
There is reasonable assure.nce:
(1)thattheactivitiesauthorized by this amendment can be conoucted without endangering the health and 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 I
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 i
of the Comission's regulations and all applicable requirements have teen satisfied.
4
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license-amendsent, and Paragraph 2.C.(2) of Facility Operating License 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.107 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 Richard F. Dudley, Acting Director Project Directorate IV-1 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications,
Date of Issuance: July 6,1990 i
)
i'
o,I ATTAC *ENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATIPIG 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 contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document cospleteness.
REMOVE PAGES INSERT PAGES 3/4 6-15 3/4 6-15 B 3/4 6-4 B 3/4 6-4 t
0 4
.