ML13316A757
| ML13316A757 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/26/1984 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A755 | List: |
| References | |
| DPR-13-A-086 NUDOCS 8411270278 | |
| Download: ML13316A757 (5) | |
Text
S UNITED STATES 2
-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. 86 License No. DPR-13 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 June 8, 1984, 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.
9 8411270278 84126 41 PDR ADOCK 05000206 PPDR
-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.
86, 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 T NUCLEARREGULATORY COMMISSION John
. Zwolinski, Chief Opera 'ng Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 26, 1984
ATTACHMENT TO LICENSE AMENDMENT No.
86 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise,tppendix 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 Pages Insert Pages 21 21 22a 22a
3.3 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS 3.3.1 Operating Status Applicability:
Applies to the operating status of the Safety Injection and Containment Spray Systems.
Objective:
To define those conditions necessary to ensure availability of the Safety Injection and Containment Spray Systems.
Specification:
A. The reactor shall not be made or maintained critical unless the following conditions are met.
In addition, the.reactor coolant system temperature shall not be increased above 2000 F unless the containment spray system, the refueling water storage tank and the associated valves and interlocks are operable.
(1) Safety Injection Systems
- a. Refueling tank water storage and boron concentration comply with Specification 3.3.3.
- b.
Two safety injection pumps are operable.
- c.
Two feed water pumps are operable.
- d. Two recirculation pumps are operable,'except as indicated in item D below.
- e. The recirculation heat exchancer is operable.
Two charging pumps are operable.
- g. Two component cooling water pumps are operable.
- h. Two saltwater cooling pumps are operable. The reactor may be maintained critical with one saltwater cooling pump provided the auxiliary saltwater cooling pump or t~o screen wash pumps are available as backup. Return the inoperable pump to operable-status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 in Cold Shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The backup pump(s) shall be demonstrated operable by test within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring the saltwater cooling pump inoperable.
- i.
A minimum of 5400 pounds of anhydrous trisodium phosphate is stored in the containment sump in racks provided.
Amendment No. ?A,34, 86
-22a (4) One charging pump for a period of time not longer than 72 consecutive hours.
(5) One of the two required component coolinge water purps for a period of.time not longer than 72 consecutive hours.
(6) One of the two saltwater cooling pumps with the auxiliary saltwater cooling pump or the screen wash pumps available as backup.for a period of-time not longer than 72 consecutive hours. The oackup pump(s) shall be demonstrated operable by test within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of declaring the saltwater pump inoperable.
C. Prior to initiating maintenance on any of the components, the duplicate (redundant) component shall be tested to demonstrate availability.
D. In the event of a failure of a recirculation pump, plant operation may continue provided operability of the remaining pump and its associated motive and control power are satisfactorily demonstrated on a daily basis, including verification that the containment spray bypass valves (CV517 and 518) are closed.
Basis:
The requirements of Specification A assure that, before the reactor can be made critical, or before the reactor coolant system heatup is initiated, adequate engineered safeguards are operabld. The limit of 625 cc/hr for the recirculation loop leakage ensures that the combined 0-2 hr. EAB thyroid dose due to recirculation loop leakage and containment leakage will not exceed the limits of 10 CFR 100.
The formula for determining the leakage incorporates consideration of the significance of leakage in different Dlant areas, The iodine release factor adjusts actual oump or valve leakage to account for the fraction of the iodine in the leakage which would actually be released to the atmosphere. The iodine release factors in the auxiliary building sump, the auxiliary building and doghouse, and outside are 0.05, 0.5 and 1.0, respectively.
When the reactor is critical or the reactor coolant system temperature is above 2000 F, maintenance is allowed per Specifications B and C providing requirements in Specification C are met which assure operability of the redundant component.
The specified maintenance times are a maximum, and maintenance work will proceed with diligence to return the equipment to an operable condition as promptly as possible.
Operability of the specified components shall be based on the results of Surveillance Standard No. 4.2.
The allowable maintenance periods are based uoon the rerair of certain suecific items.
Based on the demonstraticn that e'upent re cd:nc nt to that re-oved from service is C:era it is reasonable to mainrain
-he reactor at powcr ov:er ths
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