ML19347F153
| ML19347F153 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 04/30/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347F150 | List: |
| References | |
| NUDOCS 8105150340 | |
| Download: ML19347F153 (6) | |
Text
,
f
(.)
+p ' *
- 0 ss 09
- c UNITED STATES E 'y;> -r c (',)
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20065
- j. ;
\\; s j MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. OPR-36 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Maine Yankee Atcmic Power Cogany,
,(the licensee) dated February 22, 1980, complies with the standards and requirements of the Atomic Enerm Act of 1954, as amended (the Act) and the Comission's rules and r_gulations 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 Comission; C.
There is reasonable assurance (i) that tne activities authdrized 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 Comission's regulaticns; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the pubit::;
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.
81051so3YO
t 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operating License No. OPR-36 is hereby amended to read as follows:
(b) Technical Specifications The Technical. Specifications contained in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the license.
The licensee shall operate the facility in accedance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Speci fic;.tions Date cf Issuance: April 30, 1981
ATTACHMENT TO LICENSE AMENDMENT N0. 55 TO FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:
Remove Page Insert Page 4.6-2 4.6-2 4.6-3 4.6-3 4.6-4 e
b 4
b.
ECCS Valves:
All automatically operated valves and the motor operated fill header root valves shall be exercised through their full travel in conjunc-tion with the actuation signal testing set forth in Table 4.1-2 of Technical Specifications.
c.
Safety Injection Tanks:
Each safety injection tank will be flow tested by opening the tank isolation valve sufficient to verify check valve operation.
d.
The correct positien of each electrical and mechanical position step for the following :hrottle valves shall be verified:
- 1) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of maintenance on the valve when the HPSI system is required to be operable.
- 2) At least once per 4 months Valve Numbers HSI-M-11 HSI-M-12 HSI-M-21 HEI-M-22 HSI-M-31 HSI-M-32 e.
A flow balance test, as described in 4.6.A.2 above, shall be performed during shutdown to confirm the injection flow rates assumed in the Safety Analysis following completion of HPSI or LPSI system g
modifications that alter system flow characteristics.
3.
The containment spray flow nozzles will be tested every five years. The test will consist of pressurizing the headers with air and verifying that the nozzles are free of obstruction.
4.
Containment Isolation Valves:
Where practicable, each containment isolation valve shall be stroked to the position required to fulfill its safety function every three months.
Those valves that cannot be tested without possible adverse effcces during plant operation shall be tested during each cold shutdown if not tested during the previous three months.
B.
STEAM GENERATOR AUXILIARY FEED PUMPS Prior to plant startup following an extended cold shutdown, a flow test will be performed to verify the normal flow path from the demineralized water storage tank to the steam generators. The flow test will be conducted with the AFW system valves in their normal alignment.
Amend ent No. 19, /$. 55 4.6-2
-i
Monthly inspections snall be performed to verify that all manut' valves in the AFW system necessary to assure flow from the primary water source to the steam generators are locked in the proper position.
During normal plant operation, each auxiliary feed pump shall be testei at quarterly intervals to demonstrate operability of pumps, system valves and instrumentation.
C.
MAIN STEAM EXCESS FLOW CHECK VALVES The main steam excess flow check valves shall be tested once every 6 weeks for movement of the valve dise through a distance of approximately one and one-half inches. These valves will be tested through full travel distance during each refueling interval.
Basis The safety injection system and the containment spray system are principal plant safeguards systems that are normally operable during reactor operation.
Cc=plete system tests canrot be performed when the reacto '= sperating because of their inter-re.ation with operating systems.
The method of assuring operability of these systems is a combination of complete system tests performed during refueling shutdowns and monthly tests of active system components (pumps and valves) which can be performed during reactor operation.
The test interval is based on the judgment that more frequent testing would not significantly increase the reliability (i.e., the probability that the component would operate when required), yet more f requent tests would result in increased wear over a long period of time.
The monthly part travel exercising of the VCT outlet to charging pump suction valves, in lieu of the full travel exercise, is conducted to preclude an
'.nterruption of normal plant operations.
Redundant valves have been used to assure proper lineup in the event of ECCS actuation. Other ECCS valves wlose operation is not required to assure core flooding or containment spray si all be tested during each refueling shutdown period in accordance with 2.b.
Verification that the spray piping and nozzles are open will be made initially by a suitably sensitive method, and at least every five years thereafter.
Since all piping material is all etainless steel, normally in a dry condition, and with no plugging mechanism available, the retest every five years is considered to be more than adequate.
Other systems that are important to the emergency cooling function are the SI tanks, the component cooling system and the service wster system. The SI tanks are a passive safety feature. In accordance with the Specification 4.1 (Table 4.1-2, Item 11), the water volume and pressure in the SI tanks are checked periodically. The component cooling and service water systems operate when the reactor is in operation and are continuously monitored for satisfactory performance.
The three month testing interval of the steam generator suxiliary f eed pumps verifies their operability by recirculating water to the demineralized water tank.
Anendment No. 43,55 4.6-3
Prior to plant'startup following an extended cold shutdown, a flow test is
= performed on the Auxiliary Feedwater System to functionally verify the system alignment from the domineralized water storage tank to the steam generators.
Monthly inspections are performed to verify that all manual valves in the Auxiliary Feedwater System from the primary water source to the steam generators are locked in the proper position.
Proper functioning of the steam turbine admission valve and starting of the auxiliary feed pump will demonstrate the operability of the steam driven Verification of correct operation will be made both from instrumenta-pump.
tion with the main control room and direct visual observation of the pumps.
The main steam, excess flow check valves serve to limit an excessive reactor coolant system cooldown rate and resultant teactivity insertion following a main steam break incident.
Their freedom to move will be verified periodically.
Amendment No. 45, 55 4.6-4