ML20034E530
| ML20034E530 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/23/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034E529 | List: |
| References | |
| NUDOCS 9302260292 | |
| Download: ML20034E530 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION
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MAINE YANKEE ATOMIC POWER COMPANY QOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-36 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Maine Yankee Atomic Power Company (the licensee) dated December 15, 1992, 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 set forth in 10 CFR Chapter I; D.
The issuance e-f-this 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.B.6.(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:
9302260292 930223 PDR ADOCK 05000309 p
. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 137, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 6
Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 23, 1993
ATTACHMENT TO LICENSE AMENDMENT NO.137 FACILITY OPERATING LICENSE NO. OPR-36 DOCKET NO. 50-309 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 Insert 3.19-2 3.19-2 4.6-1 4.6-1 4.6-2 4.6-2 4.6-3 4.6-3 4.6-5 4.6-5
4 Remedial Action: If any of the ECCS check valve barriers specified above do not meet the acceptance criteria of Technical Specification 4.6.A.2.f, the reactor shall not remain critical for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or shall not be made critical if subcritical.
1Luit:
The position restrictions on the loop isolation valves, safety injection header isolation valves, and the safety injection tank isolation valves are necessary to assure that plant operation is restricted to conditions considered in the loss-of-coolant accident analysis.
The three check valves in the ECCS line to each loop provides assurance that a valve failure will not result in unrestricted flow of pressurized reactor coolant into lower pressure connecting p'iping outside the containment.
The valve integrity testing required by Technical Specification 4.6.A.2.f assures that the rate of flow under a valve failure condition will not exceed the pressure relief capacity of the line.
It further provides periodic assurance that the check valves are intact.
The two check valves closest to the loop are grouped together as a single check valve barrier for test purposes.
The first valve provides a thermal barrier preventing thermal distortion from affecting the tightness of the second valve.
The third valve alone constitutes a check valve barrier.
The remedial action permits time to correct check valve leakage and/or schedule an orderly shutdown.
1 Amendment No. 56, 58, 65,137 3.19-2
4.6 PERIODIC TESTING SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS STEAM GENERATOR EMERGENCY FEED PUMPS MAIN STEAM EXCESS FLOW CHECK VALVES FEEDWATER TRIP SYSTEM REACTOR COOLANT SYSTEM EMERGENCY VENT SYSTEM Aeolicability Applies to the safety injection system, the containment spray system, chemical injection systes, the containment cooling system, the emergency feedwater system, the main steam ercess fia check valves, the feedwater trip system, and the reactor coolant system emerge 1cy vent system.
Ob_iective To verify that the subject systems will respond promptly and perfona their intended functions, if required.
Specification A.
SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS 1.
The following tests will be performed whenever plant conditions are as defined in Section 3.6.A of these Specifications.
a.
Emergency Core Cooling System (ECCS) Pumps:
Both operable high pressure safety injection (HPSI) pumps shall be tested quarterly in accordance with Specification 4.7 by operating in the charging mode.
Both operable low pressure safety injection (LPSI) pumps and both operable containment spray (CS) pumps shall be tested quarterly in accordance with Specification 4.7 by operating in the recirculation mode.
b.
ECCS Valves:
All automatically operated valves that are required to operate to assure core flooding, or containment spray shall be exercised monthly.
The volume control tank (VCT) outlet to charging pump suction valves shall be exercised through part travel and all other valves shall be visually checked to verify proper operating position.
4.6-1 Amendment No. A$, 58, 62, 87, 100, 111, 137
2.
The following tests will be performed at each refueling interval or as otherwise stated:
a.
ECCS Pumps:
One HPSI pump shall be flow tested at 1000 psig discharge head.
One LPSI pump and one CS pump shall be flow tested at 100 psi discharge head.
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During these tests flow distribution through the HPSI and LPSI flow orifices will be checked.
Acceptance performance shall be that the pumps and orifices attain flow values used in the safety analysis.
l Alternate pumps will be tested at each refueling interval, so that all pumps will be tested within any five year period.
b.
ECCS Valves:
All automatically operated valves and the motor operated fill header root valves shall be exercised through their full travel in conjunction 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 position of each electrical and mechanical position stop for the following throttle 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 whren the HPSI system is required to be operable.
2)
At least once per 4 months Yalve Numbers i
HSI-M-11 HSI-N-21 HSI-M-31 HSI-M-12 HSI-M-22 HSI-M-32 e.
A flow balance test, as described in 4.6.A.2 above, shall be performed l
during shutdown to confirm the injection flow rates assumed in the i
Safety Analysis following completion of HPSI or LPSI system j
modifications that alter system flow characteristics.
l Amendment No. If, A5, 55, 58, S E l, 137 4.6-2 9
i f.
The check valve barriers defined in Technical Specification 3.19.A.4 shall be determined to be intact by leak testing.
Check valve barriers shall be detemined to be intact if each barrier (a) leakage is less than 15 gpa And each barrier (b) leakage is.less than 5 gps.
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 i
valves that cannot be tested without possible adverse effects during plant operation shall be tested during each cold shutdown if not tested during the previous three months.
I B.
EMERGENCY FEEDWATER PUMPS Prior to plant startup following an extended cold shutdown, a flow test will be performed to verify the nomal flow path from the domineralized water storage tank to the steam generators.
The flow test will be conducted with the emergency feedwater system valves in their normal alignment.
Amendment No. 45, 55, 58, M,137 4.6-3
tests performed during refueling shutdowns and inservice testiry of active system components (pumps and va' ves) which can be perfomed durnng reactor operation. The test interval is based on the judgement that more frequent testing would not significantly increase the reliability (i.e.,
the probability that the com>onent would operate when required), yet more frequent tests would resu' t in increased wear over a long period of time.
The monthly part travel exercising of the VCT outlet to charting pump suction valves, in lieu of the full travel exercise, is concucted to
)reclude an interruption of nomal plant operations. Redundant valves have
>een used to assure proper lineup in the event of ECCS actuation.
Other ECCS valves whose o>eration is not required to assure core flooding or containment spray shal' be tested during each refueling shutdown period in accordance with 2.b.
The three check valves-in the ECCS line to each loop provide suurance that a valve failure will not result in unrestricted flow of pressurized reactor coolant into lower pressure connecting piping outside the containment. The valve integrity testing required by Technical Specification 4.6.A.2.f assures that the rate of flow under a valve-failure condition will not exceed the pressure relief capacity of the line.
It further provides periodic assurance that the check valves are intact.
The two check valves closest to the loop are grouped together as a single check valve barrier for test purposes. The first valve provides a thermal barrier preventing thermal distortion from affecting the tightness of the second valve. The third valve alone constitutes a check valve barrier.
The check valves are hard seated swing checks designed to withstand the rigors of long tem RHR operation without damage and the greatest assurance of integrity and dependability.
The leakage criteria provide an acceptable balance between the need to maintain a degree of tightness as a criterion of integrity and ALARA on one hand and power dependability considerations on the other. This criteria gives due credit to the design of, and protection provided by, the three check valves in series.
Verification that the spray piping and nozzles are open will be made initially by a suitabl sensitive method, and at least every five years thereafter. Since all iping material is all stainless steel, nomally in a dry condition and wit no plugging mechanism available, the rttest 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 water system. The SI tanks are a passive safety feature.
In accordance with Specification 4.1 (Table 4.1-2, Ites 11), the water volume and pressure in the SI tanks Amendment No. $$, 57, J)), JJ),137 4.6-5
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