ML20147H881
| ML20147H881 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center |
| Issue date: | 12/14/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147H825 | List: |
| References | |
| R-033-A-013, R-33-A-13, NUDOCS 7812270409 | |
| Download: ML20147H881 (5) | |
Text
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j *e UNITED $TATES
'4 NUCLEAR REGULATORY COMMISSION j
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WASHINGTON, D. C. 20555
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l GENERAL ELECTRIC COMPANY DOCKET NO. 50-73 l
AMENDMENT TO FACILITY LICENSE l
1 Amendment No. 13 License No. R-33
- 1. The Nuclear Regulatory Comission (the Commission) has found that:
1 A. The appitcation for amendment by the General Electric Company 1
(_the licenseel dated August 11, 1976, complies with the standards !
and requirements of the Atomic Energy Act of 1954, as amended l
(_the Actl and the Commission's rules and regulations set forth in !
10 CFR Chapter I; l
l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1
, C. There is reasonable assurance (1) that the activities authorized !
i by this amendment can be conducted without endangering the health '
and safety of the public, and (ii) that such activities will be I conducted in compliance with the Comission's regulations; i D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and
, F. Publication of notice of this amendment is not required since l it does not involve a significant hazards consideration nor l amendment of a license of the type described in 10 CFR Section 2.106 (a)(2), i l
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- 2. . Accordingly,-the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph.2.C.(2) of Facility License No. R-33 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendi,x A,- as revised through Amendment No.13, are hereby incorporated in the license. The licensee .
shall operate the facility in accordance with the I Technical Specifications.
- 3. This license amendment is effective as of the date of its .
issuance.
FORTHENUCLEARREGULATORYCOMM[SSION qcdC d l obert W. Reid, Chief h ' Operating Reactors Branch #4 C
I l
Division of Operating Reactors i
Attachment:
Changes to the Technical .
Specifications ,
l Date of Issuance: December 14, 1978 l l
to 4 O l
'T w 199 r4 y
i 9.6 RADIATION PP.0 TECTI 0t1 PROGP.AM Procedures for personnel radiation protection shall be preccred 00nsisten:
with the requirements of 10 CFR Part 20 and shall 'ae appro <ed, maintainscd and adhered to for all operations involving persennel radiaticn exposure.
i i
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i 9a Amendment No. ' c ,13 I
.3 SURVCILLi"CE REOUIn:ME:ITS ;
10.1 Before each day's operation, the set points, specified by written proceduros approved by the facility manager or his dcaignated alternate, and the ceram capability of the safety system shall be checked.
10.2 Safety rod scram times shal. be measured at least four times a year at approximately three -month intervals except during ,
periods when the reactor is in a defueled condition. p rior to the first startup after the reactor has been refueled the safety rod scram times shall be measured and the normal safety rod surveillance schedule shall be resumod, 10.3 TSc direction of air flow while the ventilation system is in oper.-
ation shall be checked at approximately six-month intervals to ensur2 cir flow is toward the reactor cell.
10.4 Radiation monitoring instrumentation shall be checked for operability and proper set points at intervals of approximately four wecks.
10.5 All instruments required by these Specifications shall be calibrated at least four times a year at approximately three-month intervals except duriag periods when the reactor is in a defueled condition.
Prior to refueling of the reactor, the instrumentation shall be calibrated and the normal calibration schedule shall be resumed.
However, the calibration schedule shall be maintained for the instrumentation specified in Technical Specification 6.1.3 and for instrumentation used to measure stack effluent releases (except those for noble gases) whether the reactor is fueled or not.
10.6 No instrument required by these Specifications which has been removed from service for espair shall be placed in service unless it has been checked for operability and proper set point if applicab!c.
11.0 REPORTS In additien to reports otherwise required under this license and applicab'.3 regulations: -
(1) The licensee shall inform the Commission of any incident or condition relating to the operation of the reactor which pre-vented or could have prevented a safety system frem perform! ;
its safe.ty function as described in the Technical Specificcti: u or in the hazards summary report. For cach cuch occurrence, the licensee shall promptly notify by colophene and telc3rc;h the Director of the appropriate regional Nuclear Regulatory i Commission Office of Inspection and Enforcement listed in Appendix D of 10 CFR 20 and shall submit within ten (10) days a report in writing to the appropriate regional USNRC Office of Inspection and Enforcement with copies to the Director, Office of Inspection and Enforcement. USNRC, Washington, D.C.
20555, and to the Director, Office of Management Planning and Analysis, USNRC, Washington, D.C. 20555.
'[,13 Amendment No. t
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(2) The licensee shall report to the appropriate regional USNRC Office of Inspection and Enforcement, in writing within 30 days of 'its observed occurrence cny substantial variance disclosed by operction of the reactor from performance specifications contained in the hazards summcry report or the Technical Specificacions.
(3) The licensee shall report to the appropriate regional USNRC Office of Inspection and Enforcement, in writing within 30 days of its occurrence any significant change in transient or accident analysis, as described in the hazards summary report.
l (4) The licensee shall report to the appropriate regional USNRC Office of I Inspection and Enforcement, inwritingwitnin30daysofitsoccurrencef '
of any accidental release of radioactivity above permissibla l limits , whe ther or.not the releasa results in property damage, personal injury or exposure.
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Amendment No. 13