ML17056A786
| ML17056A786 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/25/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A787 | List: |
| References | |
| NUDOCS 9004300019 | |
| Download: ML17056A786 (12) | |
Text
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1 UNITED STATES I UCLEAR REGULATORY COMMISSI IV WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No.
DPR-63 1.
The Nuclear Reaulatory Commission (the Commission) has found that:
A.
B.
The application for amendment by Niagara Mohawk Power Corporation (the licensee}
dated December 8, 1989, 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; I
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; D.
The issuance of this amendment will not be inimical to'he 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.
Accordinaly, 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.
DPR-63 is hereby amended to read as follows:
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 11', 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 25, 1990
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 115 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Apperdix A as follows:
Pemove Pa es 126'27
!nsert Pa es 126 127 128
LIHITING CONDITION FOR OPERATION SURVEILLANCE BC(PIHENEN1 3.3.1 OXYGEN CONCENTRATION 4.3. I OXYGEN CONCENTRA I ION Applies to the limit on oxygen concentra-tion within the primary containment system.
~A plicabil~it Applies to the pei ludiv testing requii ement for the primary containment system oxygen concentration.
O~tt ective:
To assure that in the event of a loss-of-coolant accident any hydrogen generation will not result in a combustible mixture within the primary containment system.
e f
a.
The primary containment atmosphere shall be reduced to less than four percent by volume oxygen concentration with nitrogen gas whenever the reactor coolant pressure is greater than 110 psig and the reactor is in the power operating condition, except as specified in "b" below.
O~b ective:
To assure that the oxygen concentration within the primary containment system is within required limits.
Amendment No. 115
LIMITING CONDITION FOR OPERATION SURVEILLANCE REIEUIRERERI b.
Hithin the 24-hour period subsequent to the reactor being placed in the run mode for the power operating condition, the containment atmosphere oxygen concentration shall be reduced to less than four percent by volume, and maintained in this condition.
Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a major refueling outage or other scheduled shutdown.
c.
If Specifications "a" or "b" above are not met, the reactor coolant pressure shall be reduced to 110 psig or less within ten hours.
Amendment No.
115
BASES fOR 3.3.1 AND 4.3.
I OXYGEN CONCENRAI ION The four percent by volume oxygen concentration eliminates the possibility of hydrogen combustion following a loss-of-coolant accident (Section VII-G.2.0 and Appendix E-11.5.2)".
The only way that significant quantities of hydrogen could be generated would be if all core spray systems failed to sufficiently cool the core.
As discussed in Section VII-A.2.0 and illustrated in Figure VII-2,"
spray system is capable of design flow of 3400 gpm at a reactor pressure of 113 psig.
In addition to hydrogen generated by metal-water reaction, significant quantities can be generated by radio)ysis.
(Technical Specification tu Petition for Conversion from Provisional Operating License tu Full Term Operating License).
At reactor pressures of 110 psig or less, the reactor will have been shutdown for more than an hour and the decay heat will be at sufficiently low values so that fuel rods will be completely wetted by cor<<
spray.
The fuel clad temperatures would not exceed the core spray water saturation temperature of about 344F.
The occurrence of primary system leakage following a major refueling outage or other scheduled shutdown is much more probable than the occurrence of the loss-of-coolant accident upon which the specified oxyg<<n concentration limit is based.
Permitting access to the drywell for leak inspections during a styli tup is judged prudent in terms of the added plant safety offered without significantly reducing the margin of safety.
Thus to preclude the possibility of starting the reactor and operating lor extend<<d peiiuds ut time with significant leaks in the primary system, leak inspections are scheduled dui ing startup period>
when the primary system is at or near rated operating temperature and pressure.
The 24-hour period to provide inerting is judged to be reasonable to perform the leak inspection and establish the required oxygen concentration.
The primary containment is normally slightly pressurized during periods of reactor operation.
Nitrogen used for inerting could leak out of the containment but air could not leak in to increas<<
the oxygen concentration.
Once the containment is filled with nitrogen to the required concentration, no monitoring of oxygen concentration is necessary.
However, at least once a week, the oxygen concentration will be determined as added assurance that Specification 3.3.1 is being met.
AFSAR Amendment No. gag 1213