ML17059A228
| ML17059A228 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/07/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A229 | List: |
| References | |
| GL-91-08, GL-91-8, NUDOCS 9403140212 | |
| Download: ML17059A228 (18) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-000I NIAGARA MOHAWK POW R CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENS Amendment No. 145 License No.
DPR-63 J
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated December 27,
- 1993, 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 Commission'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:
9403140212 940307 PDR DR ADOC'K 05000220 PDR P
, J' ls I
(2)
Technica S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 145, 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 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, i994 Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
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TTACHMENT TO LICENSE AMENDMENT AM NDMENT NO. 145 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 108 110 111 112 113 114 115 143 145 146 147 148 149 150 Insert Pa es 108 110 Deleted Deleted Deleted Deleted 115 143 145 Deleted Deleted Deleted Deleted 150
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LIMITINGCONDITION FOR OPERATION SURVEILLANCEREQUIREMENT 3.2.7 L
NV LVE 4.2.7 E
Sgolli Applies to the operating status of the system of isolation valves on lines connected to the reactor coolant system.
Applies to the periodic testing requirement for the reactor coolant system isolation valves.
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To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear steam supply system.
To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear steam supply system.
UdlilSlhL:
a.
During power operating conditions whenever the reactor head is on, all reactor coolant system isolation valves on lines connected to the reactor coolant system shall be operable except as specified in "b" below.
b.
In the event any isolation valve becomes inoperable the system shall be considered operable provided at least one valve in each line having an inoperable valve is in the mode corresponding to the isolated condition, except as noted in Specification 3.1.1.e.
The reactor coolant system isolation valves surveillance shall be performed as indicated below.
I I
i the operable automatically initiated power-operated isolation valves shall be tested for automatic initiation and closure times.
a.
b.
A I
all normally open power-operated isolation valves (except the feedwater and main-steam-line power-operated isolation valves) shall be fully closed and reopened.
AMENDMENTNO. f6145 108
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PAGES 110 THROUGH 114 ARE NOT USED AMENDMENTNO. QE "45
1
BASES FOR 3.2.7 AND 4.2.7 REACTOR COOLANT SYSTEM ISOLATIONVALVES The list of reactor coolant isolation valves is contained in the procedure governing controlled lists and have been removed from the Technical Specifications per Generic Letter 91-08.
Revisions will be processed in accordance with Section 6.0, "Administrative Controls.".
Double isolation valves are. provided in lines which connect to the reactor coolant system to assure isolation and minimize reactor coolant loss in the event of a line rupture.
The specified valve requirements=assure that isolation is already accomplished with one valve shut or provide redundancy in an open line with two operative valves.
Except where Check valves are used as one or both of a set of double isolation valves, the isolation valves shall be capable of automatic initiation. Valve closure times are selected to minimize coolant losses in the event of the specific line rupturing and are procedurally controlled.
Using the longest closure time on the main-steam-line valves following a main-steam-line break (Section XVC.1.0), the core is still covered by the time the valves close.
Following a specific system line break, the cleanup and shutdown cooling closing times will upon initiation from a low-low level signal limitcoolant loss such that the core is not uncovered.
Feedwater flow would quickly restore coolant levels to prevent clad damage.
Closure times are discussed in Section VI-D.1A)(").
The valve operability test intervals are based on periods not likelyto significantly affect operations, and are consistent with testing of other systems.
Results obtained during closure testing are not expected to differ appreciably from closure times under accident conditions as in most cases, flow helps to seal the valve.
The test interval of once per operating cycle for automatic initiation results in a failure probability of 1.1 x 10 (Fifth Supplement,
- p. 115) that a line willnot isolate.
More frequent testing for valve operability results in a more reliable system.
(1)
(2)
UFSAR FSAR AMENDMENTNO. QE 145 115
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LIMITINGCONDITION FOR OPERATION SURVEILLANCEREQUIREMENT 3.3.4 N Al NV V
4.3.4 P
A SESshll'IE SIUIII Applies to the operating status of the system of isolation valves on lines open to the free space of the primary containment.
Applies to the periodic testing requirements of the primary containment isolation valve system.
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To assure that potential leakage paths from the primary containment in the event of a loss-of-coolant accident are minimized.
To assure the operability of the primary containment isolation valves to limit potential leakage paths from the containment in the event of a loss-of-coolant accident.
a.
Whenever the reactor coolant system tempera-ture is greater than 215'F, all containment isolation valves on lines open to the free space of the primary containment shall be operable except as specified in 3.3.4b below.
b.
In the event any isolation valve becomes inoperable the system shall be considered operable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one valve in each line having an inoperable valve is in the mode corresponding to the isolated condition.
The primary containment isolation valves surveillance shall be performed as indicated below.
I a.
At least once per operating cycle the operable isolation valves that are power operated and automatically initiated shall be tested for automatic initiation and closure times.
b.
At least once per quarter all normally open power operated isolation valves shall be fully closed and reopened.
AMENDMENTNO. Qk "45 143
PAGES 145 THROUGH 149 ARE NOT USED AMENDMENTNO. QE
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145
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BASES FOR 3.3.4 AND 4.3A PRIIVIARYCONTAINMENTISOLATIONVALVES The list of primary containment isolation valves is contained in the procedure governing controlled lists have been removed from the Technical Specifications per Generic Letter 91-08.
Revisions will be processed in accordance with Section 6.0, "Administrative Controls."
Double isolation valves are provided on lines penetrating the primary containment and open to the free space of the containment.
Closure of one of the valves in each line would be sufficient to maintain the integrity of the pressure suppression system.
Except where check valves are used as one or both of a set of double isolation valves, the isolation valves shall be capable of automatic initiation. Automatic initiation is required to minimize the potential leakage paths from the containment in the event of a loss-of-coolant accident.
Details of the isolation valves are discussed in Section Vl-D.
) For allowable leakage rate specification, see Section 3.3.3/4.3.3.
For the design basis loss-of-coolant accident fuel rod perforation would not occur until the fuel temperature reached 1700'F which occurs in approximately 100 seconds.(
) The required closing times for all primary containment isolation valves are established to prevent fission I
product release through lines connecting to the primary containment.
For reactor coolant system temperatures less than 215'F, the containment could not become pressurized due to a loss-of-coolant accident.
The 215'F limitis based on preventing pressurization of the reactor building and rupture of the blowout panels.
The test interval of once per operating cycle for automatic initiation results in a failure probability of 1.1 x 10 7 that a line will not isolate (Fifth Supplement,
- p. 115).
More frequent testing for valve operability results in a more reliable system.
In addition to routine surveillance as outlined in Section VI-D.1.0 each instrument-line flow check valve will be tested for operability. All instruments on a given line will be isolated at each instrument.
The line will be purged by isolating the flow check valve, opening the bypass valves, and opening the drain valve to the equipment drain tank. When purging is sufficient to clear the line of non-condensibles and crud the flow-check valve will be cut into service and the bypass valve closed.
The main valve willagain be opened and the flow-check valve allowed to close.
The flow-check valve will be reset by closing the drain valve and opening the bypass valve depressurizing part of the system.
Instruments will be cut into service after closing the bypass valve.
Repressurizing of the individual instruments assures that flow-check valves have reset to the open position.
(1)
(2)
(3)
UFSAR Nine Mile Point Nuclear Generation Station Unit 1 Safer/Corecool/GESTR-LOCA Loss of Coo'lant Accident Analysis, NEDC-31446P, Supplement 3, September, 1990.
FSAR AMENDMENTNO. Qg 145 150
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