ML13326A607
| ML13326A607 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/29/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A606 | List: |
| References | |
| DPR-13-A-049 NUDOCS 8007100102 | |
| Download: ML13326A607 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 0X SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT-1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 49 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 February 8, 1980 (Proposed Change No. 88), 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.
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-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. 49, 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. Crutchfield, C ef Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 29, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 49 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise the Appendix A Technical Specification Bases by removing the following pages and inserting the enclosed pages. The revised pages include the captioned amendment number and vertical lines reflecting the area of change.
PAGES 32 32a
-32
- 1. The initial des gn maximum value of specific power is 15 kW/ft.
The values of FAH and FQ total associated with this specific power are 1.75 and 3.23, respectively.
A more restrictivm limit on the design maximum value of specific power, FAH and FQ is applied to operation in accordance with the current safety analysis including fuel densification and ECCS performance. The values of the specific power, FNH and Fg are 13.97 kW/ft., 1.55 and 2.95, respectively. The control group insertion limits in conjunction with Specification B prevent exceeding these values even assuming the most adverse Xe distribution.
- 2. The minimum shutdown capability required is 1.25% Ap at BOL, 1.9% Ap at BOL and defined linearly between these values for intermediate cycle lifetimes.
The rod insertion limits ensure that the available shutdown margin is greater than the above values.
- 3. The worst case ejected rod accident (8) covering HFP-BOL, HZP-BOL, HFP-EOL and HZP-EOL shall satisfy the following accident safety criteria:
a) Average fuel pellet enthalpy at the hot spot below 225 cal/gm for nonirradiated fuel and 200 cal/gm for irradiated fuel.
b) Fuel melting is limited to less than the innermost 10%
of the fuel pellet at the hot spot.
Low power physics tests are conducted approximately one to four times during the core cycle at or below 10% power. During such tests, rod configurations different from those specified in Figure 3.5.2.1 may be employed.
It is understood that other rod configurations may be used during physics tests.
Such configurations are permissible based on the low probability of occurrence of steam line break or rod ejection during such rod configurations.
Operation of the reactor during cycle stretch out is conservative relative to the safety considerations of the control rod insertion limits, since the positioning of the rods during stretch out results in an increasing net available shutdown.
Compliance with Specification B prevents unfavorable axial power distributions due to operation for long intervals at deep control rod insertions.
Amendment No.
?,F3, 35, F, 49,
-32a The presence of a dropped rod leads to abnormal power distribution in the core. The location of the rod and its worth in reactivity determines its effect on the temperatures of nearby fuel.
Under certain conditions continued operation could result in fuel damage, and it is the intent of Specification C to avoid such damage.
Specification D provides that the control rod system will always be capable of shutting down the reactor.
Reference:
(1) Final Engineering Report and Safety Analysis, revised July 28, 1970.
(2) Amendment No. 18 to Docket No. 50-206.
(3) Amendment No. 22 to Docket No. 50-206.
(4) Amendment No. 23 to Docket No. 50-206.
(5) Description and Safety Analysis, Proposed Change No. 7, dated October 22, 1971.
(6) Description and Safety Analysis Including Fuel Densification, San Onofre Nuclear Generating Station, Unit 1, Cycle 4, WCAP-8131, May, 1973.
(7) Description and Safety Analysis Including Fuel Densification, San Onofre Nuclear Generating Station, Unit 1, Cycle 5, January, 1975, Westinghouse Non-Proprietary Class 3.
(8) An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods, WCAP-7588, Revision 1-A, January, 1975.
Amendment No. XA, 49