ML13316A949

Amend 96 to License DPR-13,revising Requirements on Primary Coolant Iodine Spiking & Deleting Requirement for Primary Coolant Activity Sampling in Modes 5 & 6 (Cold Shutdown & Refueling)

ML13316A949
Person / Time
Site:	San Onofre
Issue date:	03/05/1987
From:	Dudley R Office of Nuclear Reactor Regulation
To:
Shared Package
ML13316A948	List: ML13316A947 ML13316A949 ML13316A951
References
DPR-13-A-096, TAC-61453 NUDOCS 8703160358
Download: ML13316A949 (14)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 5, 1987 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. 96 License No. DPR-13

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The applications for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated November 7, 1985 and April 7, 1986, comply 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 applications, 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.

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 Provisiond1 Operating License No. DPR-13 is hereby amended to read as follows:

87031 O

870~305 PDR ADOCK 0o5000206 P

PDR

-2 B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, 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 Richard F. Dudley, Project Manager Project Directorate #1 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 5, 1987

ATTACHMENT TO LICENSE AMENDMENT NO. 96 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT ic ic 1d 1d 8

8 9

9 9a 9a*

43 43 43a 43a*

6-23 6-23 6-24 6-24*

6-25 6-25*

6-26 6-26*

• No changes made on these pages; repagination only.

-ic RATED THERMAL POWER 1.19 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 1347 Mwt.

REPORTABLE EVENT 1.20 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

RESIDUAL HEAT REMOVAL (RHR) TRAIN 1.21 An RHR TRAIN shall be a train of components that includes:

one RHR pump aligned with one RHR heat exchanger; one component cooling water pump aligned with the same RHR heat exchanger and with one component cooling water heat exchanger; and one salt water pump aligned with the same component cooling water heat exchanger.

SHUTDOWN MARGIN 1.22 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.23 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SOLIDIFICATION 1.24 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK 1.25 A SOURCE CHECK is the qualitative assessment of a channel response when the channel sensor is exposed to a radioactive source.

STAGGERED TEST BASIS, 1.26 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals.

b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

Amendment No.

77, 70, OZ, 96

-id THERMAL POWER 1.27 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.28 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TESTshall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required setpoint within the required accuracy.

UNRESTRICTED AREA 1.29 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, commercial, institutional and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.30 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atomspheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.31 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentra tion or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

E - AVERAGE DISINTEGRATION ENERGY 1.32 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 gamma energies per disintegration (in MeV) for isotopes, other than lodines 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.

Amendment No. 79, W, 96

• 9 3.1 REACTOR COOLANT SYSTEM 7 3.1.1 MAXIMUM REACTOR COOLANf 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:

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.

ACTION:

A. With the specific activity of the reactor coolant determined to be >1 uCi/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 vCi/gm DOSE EQUIVALENT 1-131 or >100/f Ci/gm, be in at least HOT STANDBY with the average temperature of the reactor coolant (Tavg) 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 />.

B. With the specific activity of the reactor coolant >1.0 vCi/gm DOSE EQUIVALENT 1-131 or >l00/E 1Ci/gm, perform the sampling and analysis requirements of item la.4.a of Table 4.1.2 until the specific activity of the reactor coolant is restored to within its limits.

C. The provisions of Specification 3.0.4 are not applicable.

Amendment No. 7p, N, 9, 96

9-9 Specific Activity BASIS:

The limitations on the specific activity of the reactor coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed the guidelines of 10 CFR Part 100 following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the reactor coolant's specific activity > 1.0 v Ci/gm DOSE EQUIVALENT 1-131, accommodates possible iodine spiking phenomena which may occur following changes in THERMAL POWER.

Reducing T to < 535 0F prevents the release of activity should a stem generator tube rupture since the saturation pressure of the reactor coolant is below the lift pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

Increased surveillance for performing isotopic analyses for iodine is required whenever the DOSE EQUIVALENT 1-131 exceeds 1.0 v Cl/gram and following a significant change in power level to monitor possible iodine spiking phenomena to assure the activity remains < 60 v Ci/gm DOSE EQUIVALENT 1-131.

The assumptions and results of these calculations are documented in "Safety Evaluation by the Office of Nuclear Reactor Regulation," Docket No. 50-206, dated April 1, 1977.

Amendment No.

96

-9a (This Page Left Intentionally Blank)

Amendment No.

Jg(, g'/, 96

-43 TABLE 4.1.2 MINIMUM EQUIPMENT CHECK AND SAMPLING FREQUENCY Check Frequency la. Reactor Coolant 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 />.

Samples Determination Required during Modes 1, 2, 3, and 4.

2.

Isotopic Analysis 1 per 14 days.

Required for DOSE EQUIVALENT only during Mode 1.

1-131 Concentration

3.

Spectrascopic 1 per 6 months (2) for E (1)

Required only during Determination Mode 1.

4.

Isotopic Analy-a)

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, (3) sis for Iodine whenever the specific Including 1-131, activity exceeds 1-133, and 1-135.

1.0 P Ci/gram DOSE EQUIVALENT 1-131 or 100/ E (1) V Ci/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 (1) E is defined in Section 1.32.

(2) Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was las't 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.

Amendment No. 2. 70, 96

-43a TABLE 4.1.2 (continued)

Check Frequency 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 />.

Coolant Determination Required only during Samples Modes 1, 2, 3 and 4.

2. Isotopic Analy-a) 1 per 31 days, whenever sis for DOSE the gross activity EQUIVALENT 1-131 determination indicates Concentration 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 gross activity determination indicates iodine concentrations below 10% of the allow able limit. Required only during Modes 1, 2, 3, and 4.

2. Safety

a. Boron Concentration Monthly when the Injection reactor is critical Water Samples and prior to return of criticality when a period of subcriti cality extends the test interval beyond 1 month.

3. Control Rod

a. Verify that all rods At each refueling Drop move from full out to shutdown full in, in less than 2.7 seconds

4. (Deleted)

5. Pressurizer

a. Pressure Setpoint At each refueling Safety Valves shutdown Amendment No.

, U0, 70, 96

routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling). The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

In the aggregate, at least 80 percent of the total whole body dose received from external sources shall be assigned to specific major work functions.

Reports required on an annual basis shall include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.1.1.

The following information shall be included in these reports: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radiolodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.1.7 The annual radiological enviromental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 3.18.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results, in the format of Regulatory Guide 4.8, December 1975, of all radiological A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SAN ONOFRE - UNIT 1 6-23 Amendment No. 70, 07, 96

environmental samples/4aken during the report period. In the event that some results are,"not available for inclusion with the report, the report shall be sibmitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map for all sampling locations keyed to a table giving distances and directions from the site reference point; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.18.3.

(Note:

Information which may be required by Specifications 3.18.1.8.1, 2, 3.18.3.8.1 and the Basis of 4.18.1 should be included.)

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report to be submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This same report shall include an assessment of the radiation doses due to the radioactive liquid and A single submittal may be made for multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

SAN ONOFRE - UNIT 1 6-24 Amendment No. 70, 07, 96

gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).

The radioactive effluent release report to be submitted 60 days after January 1 of each year shall.,also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods-for calculating the dose contribution from liquid and gaseous effluents are given in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The radioactive effluent release reports shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume,

b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottom),

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f.

Solidification agent (e.g., cement, urea formaldehyde).

The radioactive release reports shall include unplanned releases from the site to UNRESTRICTED'AREAS of radioactive material in gaseous and liquid effluents n a quarterly basis.

The Radioactive Effluent Release Reports shall include any changes made to the PROCESS CONTROL PROGRAM (PCP), to the OFFSITE DOSE CALCULATION MANUAL (ODCM), or major changes to radioactive waste treatment systems during the reporting period.

SAN ONOFRE - UNIT 1 6-25 Amendment No. 79, NJ, 96

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to pressurizer safety and relief valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C., 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC Regional Administrator, unless otherwise indicated, within the time period specified for each report.

SAN ONOFRE -

UNIT 1 6-26 Amendment No.

96, 0, 9, 96