ML17299A540
| ML17299A540 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/05/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17299A541 | List: |
| References | |
| TAC-59245, NUDOCS 8508290200 | |
| Download: ML17299A540 (8) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHWGTON, O. C. 20555 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
1 License No. NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated July 12, 1985,, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Pt object Agricultural Improvement and Power District, El Paso Elect~ic
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority {licensees),
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 Act, and the rules and regulations of the CoIIIIission; 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.
I.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:
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Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as, revised through Amendment No. 1, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of July 12, 1985.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
AUG 5
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Knigh on, Chief Licensing Branch No.
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AVG 5 1985 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.
1 TO FACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number.
and contain vertical lines indicating the area of change.
Also to,be replaced are the following overleaf pages to the amended pages.
Remove Old Pa es 3/4 4-19 3/4 4-20 Insert New Pa es 3/4 4-19 3/4 4-20
REACTOR COOLANT-. SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION
. 3.4.5.2 Reactor Coolant System leakage shall be limited to:
a.
,b.
1 gpm UNIDENTIFIED LEAKAGE,
- c. " 1'pm total primary-to-secondary'eakage through all steam generators, and 720 gallons per day through any one steam generator, d.
10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and e.
1 gpm leakage at a Reactor Coolant System pressure of 2250 a 20 psia from any Reactor Coolant System pressure.isolation,valve specified in'able 3.4-1.
APPLICABILITY: MODES 1, 2, 3, and 4
. ~
h ACTION:
a.
With any
- PRESSURE, BOUNDARY LEAKAGE,,be.in at least-HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,and in COLD SHUTDOWN'within'the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.*
With any Reactor Coolant System leakage greater than any one of the I limits,'xcluding'PRESSURE BOUNDARY LEAKAGE,and leakage from Reactor Coolant System pressure isolation valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least,HOT STANDBY within
. 'he next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With any Reactor Coolant System pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual or deactivated automatic valve, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d.
With RCS leakage alarmed and confirmed in a flow path with no flow rate indicators, commence an RCS water inventory balance within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to determine the leak rate.
SURVEILLANCE RE UIREMENTS
'.4.5.2.
1 Reactor Coolant System leakages shall be demonstrated to be within each of'the 'above limits'y:.,
I a.
Monitoring the containment atmosphere, gaseous.
and particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
"As a one time only extension during the power ascension
- program, an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is granted to cold shutdown.
During this 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the unidentified leakage exceeds 2;0 gpm, an immediate cooldown will be initiated.
The RCS leakage (Surveillance Requirement 4.4.5.2. l.c) will be calculated at least once per eight hours during this. 72-hour extension.
PALO VERDE " UNIT 1 3/4 4"19 Amendment No.
1
REACTOR COOLANT TEM If SURVEILLANCE RE UIREMENTS Continued b.
Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Performa'nce of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
d.
Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ff 4.4.5.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:
a.
At least once per 18 months, b.*
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed'in the previous 9 months, c.
Prior to. returning the valve to service following maintenance,'epair or replacement work on the valve, d."
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve,.
e."
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a system response to an Engineered Safety Feature actuation signal.'he provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
"The provisions of Specifications 4.4.5.2.2.b, 4.4.5.2.2.d, and 4.4.5.2.2.e are not applicable for valves UV 651, UV 652, UV 653 and UV 654 due to-position indication of valves in the control room.
PALO VERDE "" UNIT 1 3/4 4"20 Amendment No.
1