ML20205N233
| ML20205N233 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/09/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205N235 | List: |
| References | |
| NUDOCS 9904160198 | |
| Download: ML20205N233 (11) | |
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION
'C WASHINGTON, D.C. 2055M)001 DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413
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CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.178 License No. NPF-35
- 1. 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 Energy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated February 18,1999, 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 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.
9904160198 990409 PDR ADOCK 05000413 P
. 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.178, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Richard L. Emch, Jr, Chief, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
April 9, 1999
C arov ye 4
UNITED STATES j
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON D.C. 2055M001
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DUKE ENERGY CORPORATION 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.170 License No. NPF-52
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
l A. The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility)
Facility Operating License No. NPF-52 filed by the Duke Energy Corporation, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated February 18,1999, 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; J
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 act'vities 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 witn 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 51 of the Commission's regulations and all applicable requirements have been satisfied.
. 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.170, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
Richard L. Emch, Jr., Chief, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: April 9,1999 1
ATTACHMENT TO LICENSE AMENDMENT NO.178 TO FACILITY OPERATING LICENSE NO. NPF-35 AND LICENSE AMENDMENT NO. 170 TO FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NOS. 50-413 AND 50-414 Replace the following pages of the joint Technical Specifications (Appendix A of the Operating Licenses) with the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.
Remove insert 3.6.16-1 3.6.16.1 3.6.16-2 3.6.16-2 5.5-1 5.5-1 Replace the following pages of the Technical Specifications Bases with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert B 3.6.16-1 B 3.6.16-1 B 3.6.16-2 B 3.6.16-2 B 3.6.16-3 B 3.6.16-3
R: actor Building 3.6.16 3.6 CONTAINMENT SYSTEMS 3.6.16 Reactor Building LCO 3.6.16 The reactor building shall be OPERABLE.
APPLICABILITY:
MODES 1,2,3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Reactor building A.1 Restore reactor building to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable.
OPERABLE status.
B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
AND B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.16.1 Verify the door in each access opening is closed, except 31 days l
when the access opening is being used for normal transit entry and exit.
l (continued)
Catawba Units 1 and 2 3.6.16-1 Amendment Nos.178 (Unit 1 170 (Unit 2
Reactor Building 3.6.16 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.16.2 Verify each Annulus Ventilation System train produces a 18 months on a pressure equal to or more negative than -0.5 inch water STAGGERED gauge in the annulus within 1 minute after a start signal.
TEST BASIS SR 3.6.16.3 Verify reactor building structuralintegrity by performing a 3 times every 10 visualinspection of the exposed interior and exterior years, coinciding surfaces of the reactor building.
with containment visual examinations required by SR 3.6.1.1 Catawba Units 1 and 2 3.6.16-2 Amendrnent Nos.178 (Unit 1) 170 (Unit.2)
Programs and Manuals 4
5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
5.5.1 Offsite Dose Calculation Manual (ODCM)
The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.
Licensee initiated changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained.
This documentation shall contain:
j 1.
sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s), and 2.
a determination that the change (s) do not adversely 'mpact the accuracy or reliability of effluent, dose, or setpoint canulations; b.
Shall become effective after the approval of the Station Manatsr; and c.
Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, for Type A testing, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163,
" Performance-Based Containment Leak-Test Program," dated September 1995, except that the containment visual examinations required by Regulatory Position C.3 shall be conducted 3 times every 10 years, including during each shutdown for SR 3.6.1.1 Type A test, prior to initiating the Type A test.
(continued)
Catawba Units 1 and 2 5.5-1 Amendment Nos.178 (Unit 1) 170 (Unit 2)
R:rctor Building B 3.6.16 B 3.6 CONTAINMENT SYSTEMS B 3.6.16 Reactor Building BASES BACKG70UND The reactor building is a concrete structure that surrounds the steel containment vessel. Between the containment vessel and the reactor building inner wall is an annular space that collects containment leakage that may occur following a loss of coolant accident (LOCA). This space also allows for periodic inspection of the outer surface of the steel containment vessel.
J The Annulus Ventilation System (AVS) establishes a negative pressure in the annulus between the reactor building and the steel containment vessel under post-accident conditions. Filters in the system then control the release of radioactive contaminants to the environment. The reactor building is required to be OPERABLE to ensure retention of containment leakage and proper operation of the AVS. To ensure the retention of containment leakage within the reactor building:
a.
The door in each access opening is closed except when the access opening is being used for normal transit entry and exit, and b.
The sealing mechanism associated with each penetration (e.g.,
welds, beilows, or 0-rings) is OPERABLE.
i APPLICABLE The design basis for reactor building OPERABILITY is a LOCA.
SAFETY ANALYSES Maintaining reactor building OPERABILITY ensures that the release of radioactive material from the containment atmosphere is restricted to those leakage paths and associated leakage rates assumed in the accident analyses.
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The reactor building satisfies Criterion 3 of 10 CFR 50.36 (Ref.1).
LCO Reactor building OPERABILITY must be maintained to ensure proper operation of the AVS and to limit radioactive leakage from the containment to those paths and leakage rates assumed in the accident analyses.
Catawba Units 1 and 2 83.6.161 Revision No.1 l
Reactor Building B 3.6.16 1
BASES APPLICABILITY Maintaining reactor building OPERABILITY prevents leakage of radioactive material from the reactor building. Radioactive material may enter the reactor building from the containment following a LOCA.
Therefore, reactor building OPERABILITY is required in MODES 1,2,3, and 4 when a steam line break, LOCA, or rod ejection accident could release radioactive m9terial to the containment atmosphere.
In MODES 5 and 6, the probability and consequences of these events are low due to the Reactor Coolant System temperature and pressure limitations in these MODES. Therefore, reactor building OPERABILITY is not required in MODE 5 or 6.
O ACTIONS 6.1 In the event reactor building OPERABILITY is not maintained, reactor building OPERABILITY must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours is a reasonable Completion Time considering the limited leakage design of containment and the low probability of a Design Basis Accident occurring during this time period.
B.1 and B.2 if the reactor building cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the p! ant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on
{
operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.16.1 REQUIREMENTS Maintaining reactor building OPERABILITY requires maintaining the door in each access opening closed, except when the access opening is being used for normal transit entry and exit. The 31 day Frequency of this SR is based on engineering judgment and is considered adequate in view of the other indications of door status that are available.
l Catawba Units 1 and 2 B 3.6.16-2 Revision No.1
Reactor Building B 3.6.16 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.16.2 The abi'ity of a AVS train to produce the required negative pressure 2 0.5 inch water gauge during the test operation within 1 minute provides asst:rance that the building is adequately sealed. The neg6tive pressure prevents leakage from the building, since outside air will be drawn in by the low pressure. The negative pressure must be established within the time limit to ensure that no significant quantity of radioactive material leaks from the reactor building prior to developing the negative pressure.
The AVS trains are tested every 18 months on a STAGGERED TEST BASIS to ensure that in addition to the requirements of LCO 3.6.10
" Annulus Ventilation System," either AVS train will perform this test. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage.
SR 3.6.16.3 Tht SR would give advance indication of gross deterioration of the concrete structuralintegrity of tha reactor building. The Frequency is based on engineering judgmen. ad is the same as that for containment visual inspections performed in accordance with SR 3.6.1.1.
REFERENCES 1.
10 CFR 50.36, Technical Specifications, (c)(2)(ii).
Catawba Units 1 and 2 B 3.6.16 3 Revision No.1
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