ML17059B037
| ML17059B037 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/22/1996 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059B038 | List: |
| References | |
| NUDOCS 9601300040 | |
| Download: ML17059B037 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NI G
RA MOHAWK POWER COR ORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated January 24,
- 1995, 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; 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 Commissi'on's regulations and all applicable requirements have been satisfied.
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.
DPR-63 is hereby amended to read as follows:
9601300040 960122 PDR 'DOCK 05000220 P
(2)
Tech'nica ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 156, 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 to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COHHISSION
Attachment:
Changes to the Technical Specifications
~Ledyard B. Harsh, Director Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
January 22, 1996
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
156 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 165 167 Insert Pa es 165 167
LIMITINGCONDITION FOR OPERATION SURVEILLANCE REQUIREIVIENT 3.. ~**
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~Alic ili Applies to the leakage rate of the secondary containment.
Applies to the periodic testing requirements of the secondary containment leakage rate.
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To specify the requirements necessary to limit exfiltration of fission products released to the secondary containment as a result of an accident.
To assure the capability of the secondary containment to maintain leakage within allowable limits.
UICRilSE:
Whenever the reactor is in the refueling or power operating condition, the reactor building leakage rate as determined by Specification 4.4.1 shall not exceed 1600 cfm.
If this cannot be met after a routine surveillance check, then the. actions listed below shall be taken:
a.
Suspend immediately irradiated fuel handling, fuel pool and reactor cavity activities, and irradiated fuel cask handling operations in the reactor building.
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- isolate the reactor building and start emergency ventilation system fan to demonstrate negative pressure in the building relative to external static pressure.
The fan flow rate shall be varied so that the building internal differential pressure is at least as negative as that on Figure 3A.1 for the wind speed at which the test is conducted.
The fan flow rate represents the reactor building leakage referenced to zero mph with building internal pressure at least 0.25 inch of water less than atmospheric pressure.
The test shall be done at wind speeds less than 20 miles per hour.
b.
Restore the reactor building leakage rates to within specified limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or initiate normal orderly shutdown and be in a cold shutdown condition within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
AMENDMENTNO. Ak, 156 165
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BASES FOR 3.4.1 AND 4.4.1 LEAKAGERATE ln the answers to Questions II-3 and IV-5 of the Second Supplement and also in the Fifth Supplement", the relationships among wind speed, direction, pressure distribution outside the building, building internal pressure, and reactor building leakage are discussed.
The curve of pressure in Figure 3.4.1 represents the wind direction which results in the least building leakage.
It is assumed that when the test is performed, the wind direction is that which gives the least leakage.
Ifthe wind direction was not from the direction which gave the least reactor building leakage, building internal pressure would not be as negative as Figure 3.4.1 indicates.
Therefore, to reduce pressure, the fan flow rate would have to be increased.
This erroneously indicates that reacto" building leakage is greater than if wind direction were accounted for. If wind direction were accounted for, another pressure curve could used which was less negative.
This would mean that less fan flow (or measured leakage) would be required to establish building pressure.
However, for simplicity it is assumed that the test is conducted during-conditions leading to the least leakage while the accident is assumed to occur during conditions leading to the greatest reactor building leakage.
As discussed in the Second Supplement and Fifth Supplement, the pressure for Figure 3.4.1 is independent of the reactor building leakage rate referenced to zero mph wind speed at a negative differential pressure of 0,25 inch of water.
Regardless of the leakage rate at these design conditions, the pressure versus wind speed relationship remains unchanged for any given wind direction.
By requiring the reactor building pressure to remain within the limits presented in Figure 3.4.1 and a reactor building leakage rate of less than 1600 cfm, exfiltration would be prevented.
This would assure that the leakage from the primary containment is directed through the filter
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system and discharged from the 350-foot stack.
NFSAR AMENDMENTNO. 4/9, 15<
167
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