ML13310A741
| ML13310A741 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/13/1982 |
| From: | Baskin K Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TAC-48753 NUDOCS 8209150216 | |
| Download: ML13310A741 (4) | |
Text
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, September 13, 1982 (213) 572-1401 SAFETY, ANO LICENSING Director, Office of Nuclear Reactor Regulation Attention:
D. M. Crutchfield, Chief Operating Reactors Branch No.
5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No.
50-206 Amendment No. 108 San Onofre Nuclear Generating Station Unit 1
Reference:
Letter Robert Dietch (SCE) to H. R. Denton (NRC), August 11, 1982, Amendment No. 108, Docket 50-206 This letter is in regard to further changes that are proposed to proposed Amendment No. 108, which was transmitted to you by the referenced letter. These new changes were discussed with Mr. Walter Paulson of your staff in a telephone conversation on September 2, 1982, and are enclosed herewith as a markup to the proposed text of Amendment No. 108. Two points will clarify the bases for these changes.
- 1) The specific activity limit of 100/.uCi/gm is already part of the limiting Conditions for Operation, per Section 3.1.1 of the Technical Specifications. This limit should be added in Table 4.1.2 for completeness.
- 2) The exclusion of tritium from the definition of E is suggested for the following reasons:
- 1) Tritium emits very low energy beta particles and no gammas. It is of less serious concern in site boundary dose analysis than the gamma emitters. 2) Since most of Adoo/
6209150216 620913 PDR ADOCK 05000206 P
Mr. D.
September 13, 1982 the tritium is generated from radioactive transformations within the coolant, inclusion of tritium does not furnish useful information as to the fuel clad integrity. We feel that exclusion of tritium will provide a definition of E which is more consistent with the intent of the periodic sampling, and is more sensitive to changes in the fuel integrity. Such a definition is also consistent with current industry practice.
Should you have any questions regarding the above, please contact me.
Very truly yours, Enclosure
3.1 REACTOR COOLANT SYSTEM 3.1.1 aximum Reactor Coolant Activity A.plicability:
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 V Ci/gm dose equivalent 1-131.
- 2.
< 100/E v Ci/gm, where E is the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and game energies per disinte gration (in EV) for isotopes, other than r---
lmodines, with half lives greater than 15 minutes, making up at least 952 of the total non-iodiea actvity in the coolant.--
- 3.
Action 38 12/20/77 I. With the specific activity of the coolant determined to be >1.0 v Ci/gn but <60 P Ci/gm dose equivalent 1-131, the reactor may be started up or operation ay 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 v 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 P Ci/g 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 v Ci/ga 3-1 Revised:
1/9/78
ENCLOSURE TABLE 4.1.2 MINIMUM EQUIPMENT CHECK AND SAMPLING FREQUENCY Check Frequency la.
Reactor
- 1. Gross Activity 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 Coolant Determination during Modes 1, 2, 3, 4, 5 and 6.
- 2.
Isotopic Analysis 1 per 14 days. Required only during for DOSE EQUIVALENT Mode 1.
1-131 Concentration
- 3. Spectroscopic for 1 per 6 months( 2). Required only E1l) Determination during Mode 1.
- 4. Isotopic Analysis a) 1 per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,(3) whenever for Iodine Including the 1-131, 1-133, and exceeds 1.OJA Ci/graM 1-135
/Y b) 1 sample between 2 and 6 h rs following a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
- 5.
Boron Concentration 2/week lb.
Secondary 1.
Gross Activity 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 Coolant Determination only during Modes 1, 2, 3 and 4.
- 2. Isotopic Analysis a) 1 per 31 days, whenever the for DOSE EQUIVALENT secondary coolant gross activity 1-131 concentration determination indicates iodine concentrations greater than 10%
of the allowable limit. Required only during Modes 1, 2, 3 and 4.
b) 1 per 6 months, whenever the secondary coolant gross activity determination indicates iodine concentrations below 10% of the allowable limit. Required only during Modes 1, 2, 3 and 4.
(1) E is definedas-P(pgt44 poeit-----th eemei
-'F aaglh rpXdior'clid in thp reartnr ofl~ S*tP Hug t;. 1 of:ml f
the -uMo the ave-r&9 bota am en ei d i 9n i~gz mz J;t e vti a
(4 9 4 +im ffiiftV up -at 1-085 06% zf tk total rFzrAid4in activity in t*e-ru.Jen (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.
4-5 3909N