ML17299A720
| ML17299A720 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/31/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17299A721 | List: |
| References | |
| TAC-59189, NUDOCS 8511070342 | |
| Download: ML17299A720 (13) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
2 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated August 5, 19S5, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water 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 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; 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 enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-41 is hereby amended to read as follows:
851 1070342 851031 PDR ADQCK 05000M8 P
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
October 31, 1985 George W
- nighton, ef Licensing Branch No.
3 Division of Licensing
October 31, 1985 ENCLOSURE TO LICENSE AMENDMENT NO.
2 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.
Amendment Pa es 3/4 4-2 3/4 4-3 3/4 7-10 3/4 10-9 Overleaf Pa es 3/4 4-1 3/4 4-4 3/4 7-9
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III 3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4. 1. 1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.
APPLICABILITY: MODES 1 and 2."
ACTjON:
With less than the above required reactor coa1ant pumps in operation, be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SURVEILLANCE REOUIREMENTS 4.4. 1. 1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
See Special Test Exception 3. 10.3.
PALO VERDE " UNIT 1 3/4 4"1
REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4. 1.2 The reactor coolant loops listed below shall be OPERABLE and at least one of these reactor coolant loops shall be in operation.*
a.
Reactor Coolant Loop 1 and its associated steam generator and at least one associated reactor coolant pump.
b.
Reactor Coolant Laop 2 and its associated steam generator and at least one associated reactor coolant pump.
APPLICABILITY:
MODE 3.¹ ACTION:
a 0 With less than the above required reactor coolant loops
- OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required reactor coolant loop to operation.
SURVEILLANCE RE UIREMENTS
- 4. 4. l. 2. 1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4. 1.2. 2 At least one reactor coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4. 1.2.3 The required steam generator(s) shall be determined OPERABLE verifying the secondary side water level to be > 25K indicated wide range level at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
"All reactor coolant pumps may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10~F below saturation temperature.
¹See Special Test Exception 3. 10.9.
PALO VERDE - UNIT 1 3/4 4-2 Amendment No.
2
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REACTOR COOLANT SYSTEM HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4. 1.3 At least two of the loop(s)/train(s) listed below shall be OPERABLE and at least one reactor coolant and/or shutdown cooling loops shall be in operation.
a.
Reactor Coolant Loop 1 and its associated steam generator and at least one associated reactor coolant pump,""
b.
Reactor Coolant Loop 2 and its associated steam generator and at least one associated reactor coolant pump,""
c.
Shutdown Cooling Train A, d.
Shutdown Cooling Train B.
APPLICABILITY:
MODE 4. ¹ ACTION:
ar With less than the above required reactor coolant and/or shutdown cooling loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining OPERABLE loop is a shutdown cooling loop, be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With no reactor coolant or shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required'coolant loop to operation.
"All reactor coolant pumps and shutdown cooling pumps may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.
~"A reactor coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 255'F during cooldown, or 2954F during heatup, unless the secondary water temperature (saturation temperature corresponding to steam generator pressure) of each steam generator is less than 1004F above each of the Reactor Coolant System cold leg temperatures.
¹See Special Test Exception
- 3. 10.9.
PALO VERDE - UNIT 1 3/4 4-3 Amendment No.
2
REACTOR COOLANT SYSTEM HOT SMUTDOW SURVEILLANCE RE UIREMENTS 4.4. 1.3.
1 The required reactor coolant pump(s), if not in operation, shall be determined to be OPERABLE once per
? days by verifying correct breaker alignments and indicated power availability.
4.4. 1.3.2 The required steam generator(s) shall be determined OPERABLE by verifying the secondary side water level to be
> 25K indicated wide range level at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4. 1.3.3 At least one reactor coolant or shutdown cooling loop shall be verified to be in operation and circulating reactor coolant at a flow rate greater than or equal to 4000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
PALO VERDE - UNIT 1 3/4
PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
MODE 1:
With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in at least MODE 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 2, 3, and 4:
With one main steam line isolation valve inoperable, subsequent operation in MODE 2, 3, or 4 may proceed provided:
a.
The isolation valve is maintained closed.
b.
The provisions of Specification 3.0 '
are not applicable.
Otherwise, 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 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 />.
SURVEILLANCE RE UIREMENTS 4.7. 1.5. 1 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 4.6 seconds when tested pursuant to Specification 4.0.5.
- 4. 7. 1. 5. 2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or MODE 4 to perform the surveillance testing of Specification 4.7. 1.5. 1 provided the testing is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving normal operating steam pressure and normal operating temperature for the secondary side to perform the test.
PALO VERDE - UNIT 1 3/4 7"9
PLANT SYSTEMS ATMOSPHERE DUMP VALVES LIMITING CONDITION FOR OPERATION 3.7. 1.6 The atmospheric dump valves shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4."¹ ACTION:
With less than one atmospheric dump valve per steam generator OPERABLE, restore the required atmospheric dump valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; 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 />.
SURVEILLANCE RE UIREMENTS 4.7. 1.6 Each atmospheric dump valve shall be demonstrated OPERABLE:
a 0 b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the nitrogen accumulator tank is at a pressure
> 400 PSIG.
Prior to startup following any refueling shutdown or cold shutdown of 30 days or longer, verify that all valves will open and close fully.
~When steam generators are being used for decay heat removal.
¹See Special Test Exception 3. 10.9.
PALO VERDE " UNIT 1 3/4 7"10 Amendment No.
2 A '
SPECIAL TEST EXCEPTIONS 3/4. 10. 9 NATURAL CIRCULATION TESTING PROGRAM LIMITING CONDITION FOR OPERATION 3.10.9 The limitations of Specifications 3.4.1.2, 3.4.1.3, and 3.7.1.6 may be suspended during the performance of the Startup Natural Circulation Testing Program" provided:
a.
Operations involving a reduction in boron concentration of the Reactor Coolant System are suspended.
b.
Core outlet temperature is maintained at least lO~F below Saturation temperature.
C.
A reactor coolant pump shall not be started with one or more of Reactor Coolant System cold leg temperatures less than or equal to 255 F during cooldown, or 295 F during heatup, unless the secondary water temperature (saturation temperature corresponding to steam generator pressure) of each steam generator is less than l00'F above each of the Reactor Coolant System cold leg temperatures.
APPLICABILITY:
MODES 3 and 4 during Natural Circulation Testing..
ACTION:
Mith the Reactor Coolant System saturation margin less than 10'F, place at least one reactor coolant loop in operation, with at least one reactor coolant pump.
SURVEILLANCE RE UIREMENTS
- 4. 10.9. 1 The saturation margin shall be determined to be within the above limits by continuous monitoring with the saturation margin monitors required by Table 3.3-10 or, by calculating the saturation margin at least once per 30 minutes.
"Startup Natural Circulation Testing Program:
Natural Circulation Cooldown Test at SO% power.
PALO VERDE " UNIT 1 3/4 10-9 Amendment No.
2