ML20069K668
| ML20069K668 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 06/02/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069K671 | List: |
| References | |
| GL-83-28, NUDOCS 9406160252 | |
| Download: ML20069K668 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 l
AMEN 0 MENT TO FACILITY OPERATING LICENSE j
Amendment No. 119 License No. NPF-35 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated April 29, 1993, as supplemented May 16, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 3
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 i
51 of the Commission's regulations and all applicable requirements have been satisfied.
9406160252 940602 PDR ADOCK 05000413 P
.. 1 2.
Accordingly, Facility Operating License No. NPF-35 is hereby amended by deletion of License Condition 2.C.(20), "Transamerica Delaval, Inc.
(TDI) Diesel Generators (Section 8.3.1 SSER #4, NUREG-1216)," and Attachment I to read as follows:
2.C.(20) Deleted 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
yd n
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
License Condition change Date of Issuance:
June 2,1994 l
l
.. (iv) Additional containment response sensitivity analyses to investigate the effect of drain water temperature and flow rate, and uncertainties in parameters determined by test.
(vl Scaled tests or detailed mass transport analyses for a spectrum of break locations to quantify the impact of break conditions on thermal gradients and non-condensible gas distribution in containment and on ice condenser perfomance.
(b) During the interim period of operation, Duke Power Company shall submit to the NRC staff bimonthly reports on the prog-ress of the above confirmatory research program of tests and analyses regarding containment response for MSLB accidents. __.
(18) Residual Heat Removal System (Section 5.4.4 SER, SSER #2; Section 15.4.4, SSER #3, SSER #4)*
Prior to startup following the first refueling outage, Duke Power Company shall u valves (PORVs) pgrade the pressurizer power operated relief and the steam generator PORVs to safety related.
(19) Seismic Equipment Oualification (Section 3.10, SSER f2, SSER #3, 55ER #4)
A seismic test will be perfomed utilizing a generic mounting scheme with a GLASTIC pad and fiberglass bushing for electrical isolation to verify the acceptability of the existing mounting.
This test will be completed by July 1985.
2.C.(20) Deleted (21) Eeneric Letter 83-28 (Section 15.6. SSER #4,**)
Duke Power Company shall submit responses to and implement the requirements of Generic Letter 83-28 on a schedule which is con-sistent with that given in its November 2, and December 31, 1984, letters.
- Requires exemption; see paragraph 2.D
- Safety evaluation attached to D. Eisenhut letter dated January 17,1985.
To be incorporated in SSER #5.
Amendment No. 119
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WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.113 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated April 29, 1993, as supplemented May 16, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common i
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, Facility Operating License No. NPF-52 is hereby amended by
~
1 deletion of License Condition 2.C.(11), "Transamerica Delaval, Inc.
(TDI) Diesel Generators (Section 8.3.1 SSER#5, SSER#6, NUREG-1216)," and Attachment I to read as follows:
(11)
Deleted 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION uf David B. Matthews, Director Project Directorate 11-3
~ ~ ~ '
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
License Condition change j
t Date of Issuance: June 2, 1994
)
i
(8)
Emeraency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737).
(a) Deleted (b)
Safety Parameter Disolav System (SPDS) (Section 18. SSER #5)
Prior to December 8,1989, Duke Power Company shall add to the existing SPDS and have operational the following SPDS parameters:
(a) residual heat removal flow, (b) containment isolation status, (c) stack radiation measurements, and (d) steam generator or steamline radiation. The actual value of these and all other SPDS variables should be displayed for operator viewing in easily and rapidly accessible display formats.
(9)
Anticioatory Reactor Trio. II.K.3.10 (Section 5.2.2, SER)
Prior to exceeding 70% power, Duke Power Company shall complete the described turbine trip tests to verify that PORVs will not be challenged when the anticipatory trip bypass is in effect.
(10) Steam Generator Tube Ruoture (Section 15.4.4,SER,SSER #2)
Prior to startup following the first refueling outage of Catawba Unit 2, Duke Power Company shall submit for NRC staff review and approval an analysis which demonstrates that the steam generator single-tube rupture analysis presented in the FSAR is the most severe case with respect to the release of fission products and calculated doses. Consistent with the analytical assumptions, Duke Power Company shall propose any necessary changes to Appendix A to this license.
(11)
Deleted i
Amendment No.113
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