ML20140C882

Amend 88 to License DPR-36,requiring Operability of Three Independent Steam Generator Auxiliary or Emergency Feedwater Pumps to Supply Emergency Feedwater to All Three Steam Generators

ML20140C882
Person / Time
Site:	Maine Yankee
Issue date:	03/17/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20140C865	List: ML20140C861 ML20140C882 ML20140C909
References
NUDOCS 8603250522
Download: ML20140C882 (5)

Text

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UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION l g E WASHINGTON D. C. 20555 )

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET N0. 50-309 MAINE YANKEE ATOMIC' POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-36

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Maine Yankee Atomic Power Company, (the licensee) dated September 6, 1985 as supplemented October 3, and December 16, 1985, 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, the provisions of the Act, and the rules and regulations of the Com7.ission; C. Thereisreasonableasurance(1)thattheactivities'Iuthorized 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 regulations; D. The issuance of 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 Comission's regulations and all applicable requirements have been satisfied.

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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.B(6)(b) of Facility Operating License ho. DPR-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. 88 , are hereby

- incorporated in the license. The licensee shall c,serate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE 'UCLEAR REGULATORY COMMISSION Asho hh #F' C. Thadant, Director PWR lroject Directorate #8 DiviJion of PWR Licensing-B

Attachment:

Changes to the Technical

. Specifications Date of Issuance: March 17, 1986 f

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ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. OPR-36 4

DOCKET N0. 50-309

, Revise Appendix A as follows:

Remove Pages Insert Pages 3.8-2 3.8-2 3.8-3 3.8-3 l

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Remedial Actions (Continued)

2. With no cooling mechanisms operable, suspend all operations involving positive reactivity changes, continuously monitor reactor coolant temperature, and restore one cooling mechanism to operation within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or notify the NRC (using the Emergency Notification System) within the next hour of plans to restore decay heat removal.

B. The following conditions must be met for a steam generator to be considered operable for decay heat removal.

1. .The reactor coolant system must be closed and pressurized to 100 psi above saturation pressure.

2. The steam generator must have both the cold and hot leg stop valves fully open.

3. The steam generator water level must be above the top of the tube bundle.

4. An inventory of over 100,000 gallons of primary grade feedwater must be available.

5. A feed pc c must be operating or available for operation.

C. The steam generd ars shall be demonstrated operable in accordance with specification 4.10 before the reactor coolant system T avg can be increased above 210*F.

D. The reactor shall not be in a power operation condition which generates steam at a rate in excess of the on-line steam generator relieving capacity in accordance with Figure 3.8-1.

E. The reactor shall not be maintained in a power operation condition unless at least three independent steam generator auxiliary or emergency feedwater pumps and associated flow paths are OPERABLE to supply emergency feedwater to all three steam generators with:

1. Two emergency feedwater pumps, each capable of being automatically powered from separate OPERABLE emergency busses, and

2. One auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system, and

3. An inventory of over 100,000 gallons of primary grade feedwater.

REMEDIAL ACTION:

a. With one auxiliary or emergency feedwater pump inoperable, restore the required feedwater pumps to OPERABLE status within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />'and in HOT SHUTDOWN within the followirtg 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With one emergency feedwater and one auxiliary feedwater pump inoperable, be in HOT STANDBY in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. l

c. With two emergency feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

d. With all three auxiliary and emergency feedwater pumps inoperable, immediately l initiate corrective action to restore at least one pump to OPERABLE status as '

soon as possible.

3.8-2 Amendment No. 54,65,79,88 l

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"R Remedial. Action (Continued)

e. With the emergeny; feedwater flow path to a steam generator out of service,

return the flow path to service within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, or be in HOT STANDBY l

! within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. f BASIS:

Specifications A and E assure that decay heat removal capability is always available. l

[ A single steam generator is capable of removing core decay heat by natural or forced l circulation provided the conditions specified in B are met.

A single cooling mechanism is sufficient to remove decay heat but single. failure ,

considerations require that two mechanisms be operable.  !

1 J Specification C assures the structural integrity of the steam generator tubes which

are a fission product barrier.

Specification D assures sufficient relieving capacity during power operation. l l Specification E assures sufficient feedwater to maintain an adequate heat sink following a loss of main feedwater. The emergency feed system, including both motor driven pumps, piping, valves, and supply tanks are designed to be safety class, seismic and meet applicable NRC requirements. Each pump is powe:Ed from a separate

, emergency power bus and is capable of supplying the total emergency feedwater flow following a complete loss of main feedwater or any other design basis accident coincident with a loss of all off-site power. An emergency feed pump may be out of service for up to 7 days because of the extremely low probability of a design basis accident occurring coincident with a failure of the other emergency feed pump and a complete loss of main feedwater system capability.

The remaining portions of the auxiliary feed system, including the turbine driven

auxiliary feed pump, are not designed to NRC requirements applicable to emergency

. feed systems and not required to meet design basis events. However, the turbine

! driven auxiliary feed pump is capable of providing the required feedwater flow to the steam generator following even lower probability events such as a failure of all main feedwater and emergency feedwater capability. Such an event may be postulated to occur as a result of a loss of all off-site and on-site emergency '

power sources. This pump may be out of service for up to 7 days because of the extremely low probability of such an event.

A reactor shutdown from power requires removal of core decay heat. Imediate decay heat removal requirements are normally satisfied by the steam bypass to the con-denser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as long as feedwater to the steam generators is available.

Normally, the capability to supply feedwater to the steam generators is provided by operation of the feedwater system.

In the unlikely event of complete loss of electrical power to the station, decay heat removal is by steam discharge to the atmosphere via the main steam safety valves or the atmospheric steam dump valve. Either of the two steam generator 3 emergency feed pumps or the auxiliary feed pump can supply sufficient feedwater for removal of decay heat from the plant.

3.8-3 Amendment No. 55,79,78, 88 1

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