ML20059J765
| ML20059J765 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/12/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059J764 | List: |
| References | |
| NUDOCS 9009200167 | |
| Download: ML20059J765 (5) | |
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< UNITED STATES p
'g NUCLEAR REGULATORY COMMISSION-r,,
j-WASHINGTON, D. C. 20555
'%..... pl NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245-MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1-l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. DPR-21
' 1.
The Nuclear Regulatory Commission (the. Commission) has. found that:
A.
The application for amendment by Northeast Nuclear Energy Company.-
l (the licensee), dated June.'18,.1990, complies with the standards 1
and requirements of theiAtomic 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
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this amendment ~can be conducted without endangering the health and l
safety..of.the.public, and (ii)-that such activities will.be-conducted in compliance with the Commission's1 regulations; D.
The issuance of.this amendment will not beLinimical to the common-
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defense:and security or to the health and safety of-the public;-and -
1 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.
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p0?2llOCK05000245 167 900912 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. OPR-21~is hereby amended to read as follows:.
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(2) Technical Specifications I
)
The Technical Specifications contained in Appendix'A, as revised through Amendment No.; 45, are hereby incorporated.in the license.
The licensee shall _ operate the facility in accordance'with the Technical Specifications.
i 3.
This license' amendment is effective as of the date of issuance, to be~
-implemented within 30 days of-issuance.
FOR THE NUCLEAR REGULATORY COMISSION
'j r
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oh 'Pr Stolz, irector.
I r ect Directorate I Di ision of Reactor P jects - I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance:
September 12, 1990 i
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 45 FACILITY OPERATING LICENSE NO. DPR,21 _
DOCKET NO. 50-245 i
Replace the following pages of the Appendix "A" Technical-Specifications with l
the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 5-5 3/4 5-5
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B 3/4 5-2 B 3/4 5-2 4
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LIMITING CONDITION FOR OPERATION
,7 3.5= CORE AND CONTAINMENT COOLING SYSTEMS-C.
FWCI Subsystem 1..
Except as specified in.3.5.C.5 below,.the FWCI subsystem'shall be operable whenever the reactor coolant temperature is greater than j'
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330'F and irradiated fuel:is in' the reactor vessel.
2.
The trip on high Gas Turbine Exhaust Temperature of the 14A to 14G:
l tie breaker shall be operable whenever the Gas Turbine is operable -
and FWCI is capable of auto initiation of the Reactor Feedwater Pumps.
3.
There shall be a minimum of 250,000 gallons of useable water ik the-I condensate storage tank for operation of the FWCI.
4.
From and after the date that.the 14A to.14G tie breaker trip on Gas:
Turbine High Exhaust Temperature is found to be inoperable, the FWCI selected feedwater pump auto start shall be inhibited from its-emergency power source or the Gas Turbine Generator shall be declared inoperable.
i 5.
From and after the date that the FWCI subsystem is'.made or found to I
be inoperable for any reason, reactor operation is permissible only during the succeeding seven days, unless such subsystem is sooner made operable, provided that during such seven days all active i
components of the Automatic Pressure Relief Subsystem, the core.
spray subsystems, LPCI subsystem, and-isolation condenser system are
- operable, j
6.
. If the requirements of 3.5.C.cannot be met, an orderly shutdown l
shall' be initiated 'and the. reactor coolant; temperature shall be less :
than 330*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
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SURVEILLANCE REQUIREMENT 4.5 C0RE AND CONTAINMENT COOLING SYSTEMS-C.
Surveillance of FWCI Subsystems shall'be performed as follows:
1.
112m Freauency a.
Pump and valve
.Per Su'rveillance operability
- Requirement 4.13 b.
Simulated Automatic-Every refueling I
Actuation Test-outage' c.
14A to 14G Tie Every refueling Test Trip outage.
2.
Once a week-the quantity of water in the condensate-storage tank shall be logged.
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Millstone Unit 1 3/4 5-5 Amendment No. J, JE. 45
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3.5 CORE'AND CONTAINMENT COOLING SYSTEMS BASES Shoul'd one core spray subsystem become inoperable, the remaining core spray and the entire LPCI system are available should the need for core cooling arise.
Should the. loss of one LPCI pump occur, a nearly full complement of core-and containment cooling equipment is' available. Three LPCI pumps in conjunction with one core-spray subsystem will perform the core cooling-furction. Because of-the availability of the majority-of the core cooling i
equipment, which ;;ill be demonstrated to be operable, a 30-day repair period 13 Justified.
If more than one LPCI pump is inoperable, the repair t sme 13 set considering the containment cooling function of the LPCI.
humps.
l B.-
ContainmLqi Coolina Subsystems t
The two containment subsystems 'are provided to emcve heat energy from the-containment in-the, event of a loss-of-coolant accident.
Each single containment. cooling'sabsysteminclugestwoservicewaterpumps,_ associated valves, one heat exchanger-(40 x 10.BTV/hr), two LPCI-pumps and necessary instrumentation, control and power equipment. With two heat exchangers (1.e.,bothloops)o to one LPCI and one.perable, it is possible to degrade system performance-service water pump operating per loop and still_ not exceed significantly the equipment design temperatures and not rely-i ccmpletely. on containment pressure'for net positive suction head (NPSH).
.An interlock to prevent containment spray actuation is included:in the-design of-engineered safety features to' prevent inadvertent pressure reductior below-that required for NPSH. ' The heat removal capacity of_ a single cooling loop is adequate to prevent the' torus water temperature 4
from exceeding the. equipment temperature capability which is specified to be 203*F.
It also provides sufficient: subcooling so that adequate NPSH could be assured without-reliance on containment pressure except for short intervals during the postulated accident. :In'the event that only one; heat removal loop is operable. station operation will be' permitted'for-four.
days unless necessary repairs'are made to make-the other loop operable. A four-day period is selected to permit reasonable time for operator action and_maintennce operations.
C.-
Feedwater Coolant In.iection Subsystem The feedwater coolant injection subsystem is provided ~ to adequately cool'
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the core for all pipe breaks smaller than_ -those for which the. LPCI or core spray subsystems. can protect thev core. ;The FWCI. meets this requirement without the us~e of off-site electrical' power.
The 14A-to 14G' tie. breaker trip protects the Gas Turbine-Generator from being overloaded during a design. basis event.
For the pipe creaks for which.the FWCI' is -
intended to function, the core never' uncovers and is continuously ccoled, thus no clad damage occurs..The repair times for the limiting conditions
.of. operation were set considering the use of the FWCI as part of the -
emergency core cooling system and isolation cooling system.
l Millstone Unit 1-B 3/4 5-2 Amendment No. 45
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