ML13326A690
| ML13326A690 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/11/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A689 | List: |
| References | |
| DPR-13-A-061 NUDOCS 8208170256 | |
| Download: ML13326A690 (7) | |
Text
pR ~REG u 0 oUNITED STATES 4 a NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY DOCKET NO. 50-206 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 61 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 April 22, 1982, complies with the standards and require ments 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.
8208170256 820811 PDR ADOCK 05000206 P
-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. 61, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifi cations.
- 3. This license amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 11, 1982
ATTACHMENT TO LICENSE AMENDMENT NO. 61 PROVISIONAL OPERATING LICENSE NO, DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases by removing the following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
REMOVE INSERT 88 88*
89 89 90 91*
These pages are included for pagination purposes only; there are no changes to the provisions contained thereon.
-88
- f. Records of in-service inspection performed pursuant to these Technical Specifications.
- g. Records of Quality Assurance activities as required by the QA Manual.
- h. Records of reviews performed for changes made to procedures or equipmnt or reviews or tests and experiments pursuant to 10 CFR 50.59.
- i. Records of meetings of the OSRC and the NARC.
- j. Records for.Environmental Qualification which are covered under the provisions of paragraph 6.12.
6.10.3 The following records shall be retained for two years:
- a. Records of facility radiation and contamination surveys.
- b. Records of training of facility personnel.
Amendment No. 61
-89 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.11.1 High Radiation Area (Radiation level between 100 mrem/hr and 1,000 mrem/hr.)
In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10CFR20, each high radiation area in which the intensity of, radiation is greater than 100 mrem/hr but less than 1,000 mrem/hr shall be barricaded and conspicuously posted as a high radiation.area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP).*
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
- c.
An individua4 qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.
TiHealth Physics personnel or personnel escorted by Health Physics personnel shall -be exempt from the REP issuance requirement during the performance of-their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.
Amendment No. 61
-90 6.11.2 High Radiation Area (Radiation level above 1,000 mrem/hr)
In addition to the requirements of 6.11.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1,000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained u nder the administrative control of the Watch Engineer on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1,000 mrem* that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and unless a health physics technician is in continuous attendance, a flashing light shall be activated as a warning device. In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
- Measurement made at 18" from source of radioactivity.
Amendment No. 61
-91 6.12 ENVIRONMENTAL QUALIFICATIONS A. By no later than June 20, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:
Division of Operating Reactors "Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 "Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment", December 1979.
Copies of these documents are attached to Order for Modification of License DPR-13 dated October 24, 1980.
B. By no later than December 1, 1980, complete and auditible records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
5.13 -SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
This program shall include the following:
- 1. Provisions establisbing preventative maintenance and periodic visual inspection requirements, and
- 2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
6.14 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
- 1. Training of personnel,
- 2. Procedures for monitoring7, and
- 3. Provisions for maintenance of sampling and analysis equipment.
6.15 BACKUP METHOD FOR DETERMINING SUBCOOLING MARGIN The licensee shall implement a program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.
This pro gram shall include the following:
- 1. Training of personnel, and
- 2. Procedures for monitoring.
Amendment No.
d, 61