ML13316A569
| ML13316A569 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/06/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A568 | List: |
| References | |
| DPR-13-A-070, TAC-48753 NUDOCS 8312140190 | |
| Download: ML13316A569 (6) | |
Text
C UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 70 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated August 11, 1982, as modified by letter dated September 13, 1982, 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.
8312140190 831206
- 7.
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No.
DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfiel Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 6, 1983
ATTACHMENT TO LICENSE AMENDMENT NO. 70 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases by removing the following pages and inserting the enclosed pages.
The revised pages contain the captioned amendment number and vertical lines indicating the area of change.
PAGES 8
43 43b
-8 3.1 REACTOR COOLANT SYSTEM 3.1.1 Maximum Reactor Coolant Activity Applicability: Applies to measured maximum activity in the reactor coolant system at any time.
Objective:
To limit the consequences of an accidental release of reactor coolant to the environment.
Specification: A. The specific activity of the reactor coolant shall be limited to:
- 1. < 1.0 pCi/gm dose equivalent 1-131.
- 2. < 100/E pCi/gm, where E is the average (weighted in proportion to the concentration of each radio nuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MEV) for isotopes, other than iodines and tritium, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine and non-tritium activity in the coolant.
B. Action
- 1.
With the specific activity of the coolant determined to be >1.0 IiCi/gm but < 60 pCi/gm dose equivalent 1-131, the reactor may be started up or operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 month period.
Should the total operating time at a reactor coolant specific activity > 1.0 Ci/gram Dose Equivalent 1-131 exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive six month period, the licensee shall report the number of hours of operation above this limit to the NRC within 30 days.
- 2.
With the specific activity of the reactor coolant determined to be > 1 pCi/gm dose equivalent 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or > 60 pCi/gm dose equivalent 1-131 or
> 100/E -jCi/gm, have the reactor subcritical with the average temperature of the reactor coolant (T
av) less than 535 0F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Amendment No.,
38, 70
Table 4.1.2 Minimum Equipment Check and Sampling Frequency Check Frequency la.
Reactor
- 1. Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Required during Coolant Modes 1, 2, 3, 4, 5, and 6.
Samples
- 2. Isotopic Analysis for DOSE 1 per 14 days.
Required only during Mode 1.
EQUIVALENT 1-131 Concentration
- 3. Spectrascopic for 1E Determination 1 per 6 months (2.
Required only during Mode 1.
- 4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, (3) whenever the specific Including 1-131, 1-133, and 1-135.
activity exce Q)1.0 pCi/gram DOSE EQUIVALENT 1-131 or 100/E pCi/gram.
b) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
- 5. Boron concentration Twice/week lb.
Secondary
- 1. Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Required only during Coolant Modes 1, 2, 3, and 4.
Samples
- 2. Isotopic Analysis for DOSE a) 1 per 31 days, whenever the gross activity EQUIVALENT 1-131 Concentration determination indicatesiodine concentrations greater than 10% of the allowable limit.
Required only during Modes 1, 2, 3, and 4.
b) 1 per 6 months, whenever the gross activity determination indicates iodine concentrations below 10% of the allowable limit. Required only during Modes 1, 2, 3, and 4.
(1) E is defined in Section 3.1.1.A.2.
(2) Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
(3) Until the specific activity of the reactor coolant system is restored within its limits.
T'abl e 4%,Y.2 (contd.)
43b Check Frequency
- a. Pressure Setpoint At each refueling shutdown
- 7. Main Steam Power
- a. Test for Operability At each refueling shutdown Operated Relief Valves
- 8. Thisodium Phosphate
- a. Check for system At each refueling shutdown Additive availability as delineated in Technical Specifi cation 4.2
- 9. Hydrazine Tank
- a. Hydrazine concen-Once every six months when the Water Samples tration reactor is critical and prior to return of criticality when a period of subcritical extends the test interval beyond six months.
- 10.
Transfer Switch No. 7
- a. Verify that the fuse Monthly, when the reactor is block for breaker critical and prior to returning 8-1181 to MCC 1 is reactor to critical when period removed of sub-criticality extended the test interval beyond one month.
- 11.
MOV/LCV-1100 C Transfer
- a. Verify that the-fuse Same as Item 10 above.
Switch block for either breaker 8-1198 to MCC 1 or breaker 42-12A76 to MCC 2A is removed.
- 12.
Emergency Siren Transfer
- a. Verify that the fuse Same as Item 10 above.
Switch block for either breaker 8-1145 to MCC 1 or breaker 8-1293A to MCC 2 is removed.
- 13.
Communication Power Panel
- a. Verify that the fuse Same as Item 10 above.
Transfer Switch block for either breaker 8-1195 to MCC 1 or breaker 8-1293B to MCC 2 is removed.
14a. Spent fuel pool water Verify water level per
- a. Once every seven days level Technical Specification 3.8.
when spent fuel is being stored in the pool.
- b. Refueling pool water
- b. Within two hours prior level to start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during move ment of fuel assemblies or RCCos.
Amendment No.tCr, 70