ML19312C501
| ML19312C501 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/20/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C499 | List: |
| References | |
| NUDOCS 7912160063 | |
| Download: ML19312C501 (9) | |
Text
-.
m
~s UNITED STATES 3"
NUCLEAH REGULATORY COMMISSION j
j, WASHINGTON, D. C. 20646 s
gs j
DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACIILTY OPERATING LICENSE Amendment No. 40 License No. OPR-38 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated May 6,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendnent will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-38 is A.reby amended to read as follows:
7912160063 w^
m G
)
- "(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
3.
This license amendn?nt is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION cLit <'k, A Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 20, 1977 i
l l
s
/
%g UNITED STATES y*
NUCLEAR REGULATORY COMMISSION 3
j WASHINGTON, D. C. 20656 k,
af
%, '..... at DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-47 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated May 6,1977, 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, nad (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 3.8 of Facility License No. DPR-47 is hereby amended to read as follows:
i asee-w
~m os
-no
..m ownr
=es-
--e
~~~mn
- - *-~
~*=om--
me-~
- a--~ee~m-.---
e---,,em
q N.
2-
"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendrnent No. 40, are hereby incorporated in the license.
The licensee 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 COPNISSION
/
MAW: -
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 20, 1977 t
]
.n
..... m o s-
,*~~~"as"***'H*'=~*
- ""W"
- ' ~ ~ ~ ~ * ' ~ ~ ' '
/
Ng' UNITEJ STATES y*
NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 20665 s.....,
DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. DPR-55 1.
The Nuclear Regulatory Comission (the Commission) has found tnat:
A.
The ecplication for amendment by Duke Power Company (the licensee) dated May 6,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 ccnducted in compliance with the Comission's regulations; 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; and 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.
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 Facility License No. DPR-SS is hereby amended to read as follows:
~
~ =. =
-2
"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
hl'.44%W!
'i A.'Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: May 20, 1977
-. _. _ - _._.~
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 40 TO DPR-38 AMENDMENT NO. 40 TO DPR-47 AMENDMENT NO. 37 TO DPR-55 DOCKET NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove page 4.18.1 and insert r: vised pages 4.18.1 and 4.18.la.
I l
l l
l j.
. - =..
4.18 HYDRAULIC SH SUPPRESSORS (SNUBBERS)
Applicability Applies to hydraulic shock suppressors used to protect the Reactor Coolant System or other safety-related systems.
Objective To verify that required hydraulic shock suppressors are c']erable.
Specification 4.18.1 All hydraulic snubbers listed in Table 4.18-1 whose seal material has.
been demonstrated by operating experience, lab testing or analysis to be compatible with the operating environment shall be visually inspected.
This inspection shall include as a minimum hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify suppressor operability in accordance with the following schedule:
Number of Suppressors Found Next Required Inocerable During Last Inspection Inspection Interval 0
18 months + 25%
1 12 months T 25%
2 6 months T 25%
3,4 4monthsi25%
5,6,7 2 months 1 25%
>8 1 month 1 25%
Note:
(1)
The required inspection interval shall not be lengthened more than one step per inspection.
Note:
(2)
Suppressors may be categorized in two groups, " accessible" or
" inaccessible", based on their accessibility during recctor operation.
These two groups may be inspected independently according to the above schedule.
'( 3) The inspection interval including the + 25% margin, for Oconee Unit No. 2 which ends on May 22, 1977, may be extended to not l
longer than June 4, 1977.
(4) A total maximum combined interval time for any 3 consecutive tests shall not exceed 3.25 times the specified surveillance interval.
4.18.2 All hydraulic snubbers whose seal materials are other than ethylene propylene or other material that has been demonstrated to be compati-ble with the operating environment shall be visually inspected for operability once every iTenth.
l 4.18.3 A representative sample of 10 hydraulic shock suppressors or approxi-.
mately 10 percent of the suppressors installed whichever is less, I
shall be functionally tested for operability each refueling outage.
This test shall include verification of proper piston movement, lockup and bleed.
For each suppressor determined to inoperable, an additional 4.18-1 Amendment Nn.40, 40 & 37
m m
]
10 percent or 10 suppressors, whichever is less, shall be tested until no more failures are found or all suppressors have been testad.
Suppressors with a rated capacity greater than 50,000 lbs., are exempted from this requirement.
4.18.4 The initial inspection shall be perforned within 6 months from the date of issuance of these specifications.
For the purpose of entering the schedule of Specification 4.18.1, it shall be assumed that the facilities had been on a 6 month inspection interval.
l i
A:nendment Nos. 40, 40 & 37 _
4.18-la
__