ML17059A639
| ML17059A639 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/25/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A640 | List: |
| References | |
| NUDOCS 9501310154 | |
| Download: ML17059A639 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 N NE OINT UCLEAR STATION UNIT NO.
1 E
DM NT TO FACILITY OPE TI G LICENS Amendment No.
152 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 July 21, 1994, 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:
9501310154 950125 PDR ADOCK 05000220 P
PDRt
(2) c f
tions The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 152, 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
/8 Ledyard B. Harsh, 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:
january 25, 1995
0
ACHMENT TO LICENSE AMENDMENT AM NDMENT NO.
152 0 FACILITY OPERATING LICENSE NO.
DPR 63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 23 25 118 119 Insert P
es 23 25 118 119
0
SAFETY LIMIT LIMITINGSAFETY SYSTEM SETTING 2.2.1 REA T R
LANT Y TEM 2.2.2 REA T R
LANT Y TEM Applies to the limit on reactor coolant system pressure.
a.
The settings on the safety valves of the pressure vessel shall be as shown below. The allowable initial set point error on each setting will be a1 percent.
Qggg~iv:
Set Point
~p<~i Number of af V Iv To define those values of process variables which shall assure the integrity of the reactor coolant system to prevent an uncontrolled release of radioactivity.
The reactor vessel or reactor coolant system pressure shall not exceed 1375 psig at any time with fuel in the vessel.
1218 1227 1236 1245 1254 3
2 2
3.
9 b.
The reactor high-pressure scram trip setting shall be c1080 psig.
c.
The flow biased APRM scram trip settings shall be in accordance with Specification 2.1.2a.
AMENDMENTNO. iQI, Ok,152 23
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BASES FOR 2.2.2 REACTOR COt)LANTSYSTEIVI - LIIVIITINGSAFETY SYSTEIVI SETTING a.
The range of set points for a safety valve actuation is selected in accordance with code requirements.
The safety valves are sized according to the code for a condition of main steam isolation valve closure while operating at 1850 Mwt, followed by a reactor scram on high neutron flux. Under these conditions, a total of nine (9) safety valves are required to limit reactor pressure below the safety limit of 1375 psig.
In addition to the safety valves, the solenoid-actuated relief valves are used to prevent safety valve liftduring rapid reactor isolation at power coupled with failure of the bypass system.
Any five of these valves opening at 1090 psig to 1100 psig will keep the maximum vessel pressure below the lowest safety valve setting, as demonstrated in Appendix E-I.3.11 (p. E-35)".
(The Technical Supplement to Petition to Increase Power Level, and letter from T. J. Brosnan, Niagara Mohawk Power Corporation, to Peter A. Morris, Division of Reactor Licensing, USAEC, dated February 28, 1972).
Subsequently, six valves were provided due to the blowdown requirements, following a small line break.
b.
The reactor high pressure scram setting is relied upon to terminate rapid pressure transients if other scrams, which would normally occur first, fail to function. As demonstrated in Appendix E-I of the FSAR and the Technical Supplement to Petition to Increase Power Level, Page ll-12, the reactor high pressure scram is a backup to the neutron flux scram, generator load rejection scram, and main steam isolation-valve closure scram for various reactor isolation incidents.
However, rapid isolation at lower power levels generally results in high pressure scram preceding other scrams because the transients are slower and those trips associated with the turbine-generator are bypassed.
The operator willset the trip setting at 1080 psig or lower. However, the actual set point can be as much as 15.8 psi above the 1080 psig indicated set point due to the deviations discussed above.
"FSAR AMENDMENTNO. i(D, 152 25
LllNITINGCONDITION FOR OPERATION SURVEILLANCEREQUIREMENT 3.2.8 PRE RE RELIEF Y TEM - AF VAL E 4.2.8 PRE RE RELIEF Y TEM - AFETY VALVE Applies to the operational status of the safety valves.
Applies to the periodic testing requirements for the safety valves.
Qbhm~iv:
To assure the capability of the safety valves to limit reactor overpressure below the safety limit in the event of rapid reactor isolation and failure of all pressure relieving devices.
To assure the capability of the safety valves to limit reactor overpressure to below the safety limit.
a.
During power operating conditions and whenever the reactor coolant pressure is greater than 110 psig and temperature greater than saturation temperature all nine of the safety valves shall be operable.
At least once during each operating cycle, the number of safety valves as determined by the IST Program Plan shall be removed, tested for set point and partial lift, and then returned to operation or replaced.
b.
If specification 3.2.8a is not met, the reactor coolant pressure and temperature shall be reduced to 110 psig or less and saturation temperature or less, respectively, within ten hours.
AMENDMENTNO. 745,152
BASES FOR 3.2.8 AND 4.2.8 PRESSURE RELIEF SYSTEM-SAFETY VALVES The required number of operable safety valves is based on a condition of main steam isolation valve closure while operating at 1850 Mwt, followed by a reactor scram on high neutron flux. Operation of all 9 safety valves willlimitreactor pressure below the safety limitof 1375 psig.
The safety valve testing and intervals between tests are based on manufacturer's recommendations and past experience with spring actuated safety valves.
AMENDMENTNO. iQ5,152'19