ML20058B042
| ML20058B042 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/22/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058B046 | List: |
| References | |
| NUDOCS 9010290369 | |
| Download: ML20058B042 (5) | |
Text
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UNITED STATES NUCLE AR REGULATORY COMMISSION e
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p BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION APENDMENT TO FACILITY OPERATING LICCHSE Amendment No.131 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment fileo by the Boston Edison Company i
(the licensee) deted December 11, 19B9 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 Comission; C.
There is reasonable assurance: (i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted L
in compliance with the Comission's regulations set forth in 10 CFR Chapter I; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as. indicated in the attachment to this license amendment, and.
paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
Technical Specifications TheTechnicalSpecificgp'onscontainedinAppendixA,asrevised through Amendment No, i
, are hereby incorporated in the license.:
The licensee shall operate the facility in accordance with the Technical Specifications.
9010290369 901022
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This licence amendmer.t is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMIS$10N Richard Wessman, Director Proiect Directorate 1-3 DivisionofReactorProjects-1/11 Office of Nuclear Reactor Regulation
Attachment:
t Changes to the Technical Specifications Date of issuance:
October 22, 1990 I
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ATTACHMENT TO LICENSE AMENDMENT NO. I3I
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F#.01LITY OPERATING LICFNSE NO. DPR-35 j,
DOCKET tl0. 50-293 Replace the following sages of the Appendix A Technical Specifications with the attached pages. T1e revised pages are identified by Amendment nunber and c
contain vertical lines indicating the area of change.
Remove Insert 103 103 113 113 s<
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 3.5 CORE AND CONTAINMENT CO3 LING 4.5 CORE AND CONTAINHENT CO3 LING SYSTEMS SYSTEMS Acolicability Acoli cabili_ty Applies to the operational status of Applies to the Surveillance the core and suppression pool cooling Requirements of the core and subsystems.
suppression pool cooling subsystems which are required when the corresponding Limiting Condition for Operation is in effect.
Obiettive Qbiettive To assure the operability of the core To verify the operability of the core and suppression pool cooling and suppression pool cooling subsystems subsystems under all conditions for under all conditions for which this which this cooling capability is an cooling capability is an essential essential response to station response to station abnormalities.
abnormalities.
Soecification Snecification A.
Core Sprav and LPCI Subsystems A.
Core Sorav and LPCI Subsysits 1.
Both core spray subsystems shall 1.
Core Spray Subsystem Testing, be operable whenever irradiated fuel is in the vessel and prior to Ltts Freauency reactor startup from a Cold Condition, except as specified in a.
Simulated Once/ Operating 3.5.A.2 below.
Automatic Cycle Actuation test.
b.
Pump Operability Once/ month c.
Motor Operated Once/ month Valve Operability d.
Pumo flow rate Each pump shall deliver at least 3300 gpm against l
a system head corresponding to a reactor vessel pressure of 104 psig.
e.
Core Spray Header A p Instrumentation l
l Amendment No. 42, 62. Ild' 131 103
EASIS:
3.5.A Core Seray and LPCI Subsystem This specification assures that adequate emergency cooling capability is available whenever irradiated fuel is in the reactor vessel.
Based on the loss of coolant analysis performed by General Electric in accordance with Section 50.46 and Appendix K of 10CFR50, the Pilgrim I Emergency Core Cooling Systems are adequate to provida sufficient cooling to the core to dissipate the energy associated with the loss of coolant accident, to limit calculated fuel clad temperature to less than 2200'F, to limit calculated local metal water reaction to less than or equal to 17%, and to limit calculated core wide metal water reaction to less than or equal to 1%.
General Electric Company Proprietary Report EAS-65-0989 " Safety Evaluation for Interim Operation of Pilgrim Nuclear Power Station with Reduced Core Spray System Flow Rate" (September 1989) calculates a peak fuel clad temperature of less than 2200*F with a Core Spray pump flow of 3240 gallons per minute (gpm). A flow rate of 3300 gpm ensures adequate flow for events involving degraded voltage.
The limiting conditions of operation in Specifications 3.5.A.1 through 3.5.A.6 specify the combinations of operable subsystems to assure the availability of the minimum cooling systems noted above.
No single failure of CSCS equipment occurring during a loss-of-coolant accident under these limiting conditions of operation will result in inadequate cooling of the reactor core.
Core spray distribution has been shown, in full-scale tests of systems similar in design to that of Pilgrim, to exceed the minimum requirements by at least 25%.
In addition, cooling effectiveness has been demonstrated at less than half the rated flow in simulated fuel assemblies with heater rods to duplicate the decay heat characteristics of irradiated fuel.
The accident analysis takes credit for core spray flow into the core at vessel pressure below 205 psig.
However, the analysis is conservative in that no credit is taken for spray cooling heat transfer in the hottest fuel bundle until tne pressure at rated flow for the core spray (104 psig vessel pressure) is reached.
The LPCI subsystem is designed to provide emergency cooling to the core by flooding in the event of a loss-of-coolant accident.
This system functions in combination with the core spray system to prevent excessive fuel clad temperature.
The LPCI subsystem and the core spray subsystem provide adequate cooling for break areas of approximately 0.2 square feet up to and including the double-ended recirculation line break without assistance from the high pressure emergency core cooling subsystems.
The allowable repair times are established so that the average risk rate for repair would be no greater than the basic risk rate.
The method and concept are described in reference (1).
Using the results developed in 113 Amendment No.
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