ML17053C175
| ML17053C175 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/12/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17053C177 | List: |
| References | |
| NUDOCS 8012300647 | |
| Download: ML17053C175 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POMER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY'OPERATING LICENSE Amendment No. 38 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 1tcensee) dated October 29, 1980, complies with the standards and requi'rements 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; E.
The facility will operate in conformity with the application, the provisi'ons 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 publi'c, and (ii) that such activities will be conducted in compliance with the Commtssion'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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Factlity Operating License No.
DPR-63 is hereby amended to read as follows:
(2) Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 38, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This li'cense amendment ts effecttye as.. of the date of its issuance.
fOR THE NUCLEAR REGULATORY COMMISSION Thomas
. Ippolito, Chief Operating Reactors Branch 82 Di'vision of Licensi'ng
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 12, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 38 FACILITYOPERATING LICENSE NO.
DPR-63 DOCKET NQ; 50-'220 Revise Appendix A as follows:
Remove Insert 166 168 166 168 168a
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SECTION DESCRIPT ION PAGE
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- 6. ll Radiation Protection'Program 260 6.12.
6.13 6.14 6.15 Del eted High Radiation Area
'ire Protection InsPection Environmenta1 gualification 263 265 Amendment No. 22, 38
LIHITlNG CONDITIONS FOR OPERATION SURVEILLANCE RE VIREHENTS 3.4.1 LEAKAGE RATE 4.4 '
'EAKAGE RATE Applies to the leakage rate of the secondary containment.
Applies to the periodic testing requirements of the secondary containment leakage rate.
~ob ective:
~ob'ective:
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.
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 2000 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.
- 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 />'nce durin each o eratin c cle 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 3.4.1 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.
Amendment No. 38 166
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BASES FOR 3.4.1 AND 4.4.1 LEAKAGE RATE In the answers to Questions II-3 and IV-5 of t)ie 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.
I If the 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 reactor building }.eakage is greater than if wind direction were accounted for. If wind direction were accounted for, another pressure curve could be used wh'ich was less negative.
This would mean that less fan flow (or measured leakage) would be required to establish building pressure.
))owever, for simplicity it is assumed that the test is conducted during conditi:ons 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'han 2000 cfm, exfiltration would be prevented.
This would assure that the leakage from the primary containment is directed through the filter system and discharged from the 350-foot stack.
Secondary Containment may be broken at one penetration for up to four hours to allow work to proceed on modifications which will enhance the overall safety of the plant.
While the secondary containment is open, administrative controls will be in place to assure integrity can be restored immediately, if necessary.
Typically, existing penetrations will be opened in the Reactor Building walls to allow for cable installation for various plant modifications.
Preoperational reactor building capabi).ity tests sha).l be conducted after isolating the reactor building and placing either branch of the emergency ventilation system in operation.
The tests shall be performed under a
number of different environmental Qind conditions, i.e. wind speed and direction.
- FsAR Effective after Haunch 31, 1981 Amendment Ho.
38 168
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BASES FOR 3.4.1 AND 4.4.1 LEAKAGE RATE In 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.
If the 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, ta reduce pressureq the fan flow'rate would have to be increased.
This erroneously indicates that reactor building leakage~is greater than if wind
.direction were accounted for. If wind direction were accounted for, another pressure curve could be 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 conditi'ons 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'eferenced 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
'emains 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 2000 cfm, exfiltration would be. prevented.
This would assure that the leakage from the pr'imary containment is directed through the filter system and discharged from the 350-foot stack.
Secondary Containment, may be broken at one penetration for up to four hours to allow work to proceed on modifications which wilL enhance the overall safety of the plant.
While the sec'ondary containment is open, administrative controls will be in place to assure integrity can be restored immediately, if necessary.
Typically, existing penetrations will be opened in the Reactor'Building walls to allow for cable installation for various plant modifications.
Preoperational reactor building capability tests shall be conducted after isolating the reactor building and placing either branch of the emergency ventilation system in operation.
The testa shall be performed under a
number of different environmental Qind conditions, i.e. wind speed and direction.
r Amendment No. 38
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