ML17303B124
| ML17303B124 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/05/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17303B125 | List: |
| References | |
| NUDOCS 8805230265 | |
| Download: ML17303B124 (11) | |
Text
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~pP Rfqg Wp~y4 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.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
31 License No. tIPF-41 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment, dated January 21 and February 2, 1988, 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),
comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of Act, and the regulations of the Comission; 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 Comission'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:
8805230265 880505
'DR ADOCII, 05000528 P
4 (2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
31, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this licer se.
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.
The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time.
The period of time during changeover shall be minimized.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance May 5, 1988 George
. Knight, Director Proje Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
'lay 5, 1.988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Replace the folloviing 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 areas of change.
Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pa es 3/4 4-32 3/4 11-14 B 3/4 11-5 Overleaf Pa es 3/4 4-31 3/4 11-13 B 3/4 11-6
REACTOR COOLANT SYSTEM PRESSURIZER HEATUP/COOLDOWN LIMITS LIMITING CONDITION FOR OPERATION 3.4.8.2 The pressurizer temperature shall be limited to:
a.
A maximum heatup rate of 2004F per hour, and b.
A maximum cooldown rate of 2004F per hour.
APPLICABILITY: At all times.
ACTION:
With the pressurizer.
temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer "emains acceptable for continued operation 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 reduce the pressurizer pressure to less than 500 psig 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 4.4.8.2. 1 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.
4.4.8.2.2 The spray water temperature differential shall be determined for use in Table 5.7-2 for each cycle of main spray with less than four reactor coolant pumps operating and for each cycle of auxiliary spray operation.
PALO VERDE - UNIT '1 3/4 4-31 AMENDMENT NO 27
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.8.3 Both shutdown cooling system (SCS) suction line relief valves with lift settings of less than or equal to 467 psig shall be OPERABLE and aligned to provide overpressure protection for the Reactor Coolant System.
APPLICABILITY:
When the reactor vessel head is installed and the temperature of one or more of the RCS cold legs is less than or equal to:
a.
b.
ACTION:
255 F during cooldown 295'F" during heatup b.
d.
With one SCS relief valve inoperable, restore the inoperable valve to OPERABLE status within seven days 'or reduce T
l to less than 200'F
- and, depressurize and vent the RCS through a greater than or equal.to 16 square inch vent(s) within the next eight hours.
Do not start a
reactor coolant pump if the steam generator secondary water temperature is greater than 100'F above any RCS cold leg temperature.
With both SCS relief valves inoperable, reduce T
ld to less than 200'F cold and, depressurize and vent the RCS through a greater than or equal to 16 square inch vent(s) within eight hours.
Do not start a reactor coolant pump if the steam generator secondary water temperature is greater than 1004F above any RCS cold leg temperature.
In the event either the SCS suction line relief valves or an RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.
The report shall describe the circumstances initiating the transient, the effect of the SCS suction line relief valves or RCS vent(s) on the transient and any corrective action necessary to prevent recurrence.
The provisions of Specification 3.0.4 are not applicable.
"255'F during heatup provided the heatup rate is limited to 10 F/hr or less for.RCS temperature greater than 255'F and less than or equal to 295'F.
PALO VERDE UNIT 1 3/4 4-32 AMENDMENT NO. 31
RADIOACT'IVE EF<LUENTS GASEOUS RAOWASTE TREATHENT L I HI 7 I NG COND I T ION FOR OP ERAT ION
- 3. Il. 2. 4 The GASEOUS RADWASTE SYSTEH and the VENTILATION EXHAUST TREATH.=NT SVSTEH shall be used to reduce radioactive materials in gaseous waste prior tc their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see Figures
- 5. 1-1 and 5, 1-3),
when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The VENTILATION EXHAUST TREATHEN.
SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figures
- 5. 1-1 and
- 5. 1-3) when averaged over 31 days would exceed 0.3 mrem to any organ of a HEHBER OF THE PUBLIC.
APPLICABILITY: At all times.
ACT IO!l:
With radioactive gaseous
~aste being discharged without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action(s) taken to restore the inoperable equipment to OPERABLE
- status, and 3.
Summary description of action(s) taken to prevent a recurrence.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREHENTS
- 4. 11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCH.
PALO VERDE - UNIT 1 3/4 11-13
RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION
- 3. 11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2X by volume whenever the hydrogen concentration exceeds 4X by volume.
APPLICABILITY: At al 1 times.
ACTION:
With the concentration of oxygen in the waste gas holdup system greater than 2X by volume but less than or equal to 4X by volume, reduce the oxygen concentration to the above limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
With the concentration of oxygen in the waste gas holdup system greater than 4X by volume, immediately suspen'd all additions of waste gases to the system and reduce the concentration of oxygen to less than 4X by volume within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.,
C.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS
- 4. 11.2.5 The concentration of hydrogen or oxygen in the waste gas holdup system shall be determined to be within the above limits by monitoring the waste gases in the waste gas holdup system in accordance with Specification 3.3.3.8.
PALO VERDE - UNIT 1 3/4 11"14 AMENDMENT NO.
31
0 RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT (Continued)
This specification applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.
The minimum analysis frequency of 4/M (i.e. at least 4 times per month at intervals no greater than 9 days and a minimum of 48 times a year) is used for certain radioactive gaseous waste sampling in Table 4. 11-2.
This will eliminate taking double samples when quarterly and weekly samples are required at the same time.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.
(Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.
These automatic control features include isolation of the source of hydrogen and/or oxygen, or injection of di lutants to reduce the concentration below the flammability limits.)
Main-taining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A
to 10 CFR Part 50.
3/4. 11. 2. 6 'AS STORAGE TANKS This specification considers postulated radioactive releases due to a waste gas system leak or fai lure, and limits the quantity of radioactivity contained in each pressurized gas storage tank in the GASEOUS RADWASTE SYSTEM to assure that a release would be substantially below the guidelines of 10 CFR Part 100 for a postulated event.
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed
- 0. 5 rem.
This is cons'istent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure,"
in NUREG-0800, July 1981.
3/4. 11. 3 SOLID RADIOACTIVE WASTE This specificatioa addresses the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
The process parameters included
, in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst
- ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.
3/4. 11.4 TOTAL DOSE
. This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.
The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and PALO VERDE - UNIT 1 B 3/4 11-5 AMENDMENT NO.
31
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE (Continued) direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small.
The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.
If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected),
in accordance with the provisions of 40 CFR Part 190. 11 and 10 CFR Part 20.405c,. is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications
- 3. 11. 1. 1 and 3. 11.2. l.
An individual is not con-sidered a
MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
PALO VERDE - UNIT 1 B 3/4 11-6