ML20217D721
| ML20217D721 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-62-A-236, DPR-71-A-206) |
| Issue date: | 10/05/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217D725 | List: |
| References | |
| NUDOCS 9910180105 | |
| Download: ML20217D721 (12) | |
Text
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-e t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555 6 1
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CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 206 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated October 27,1998, 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.
2.
Accordingly, the Operating License is amended as indicated in the attachment to this license amendment.
4 1
1 9910100105 991005 yDR ADOCK 05000324 PDR
{
- . 3.
This license amendment is effective as of the date of its issuance and shall be
- implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION b
b^-
~
Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License
- Date of Issuance: October 5,1999
F e
y, ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of Operating License No. DPR-71 with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating _
. the areas of change.
Remove Paaes insert Paaes 3
3 3a 4
4 4a 0
5 Sa Sb l
i 4
(4) Pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess and use in amounts as required any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated'with radioactive apparatus or components; (5). Pursuant to the Act and 10 CFR Parts 30 and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Brunswick Steam Electric Plant, Unit Nos.1 and 2, and H. B. Robinson Steam Electric Plant, Unit No. 2.
(6) Carolins Power and Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report, dated November 22,1977, as supplemented April 1979, June 11,1980, December 30,1986, December 6,1989, July 28,1993, and February 10,1994, respectively, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
C.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level
-)
(
The licensee is authorized to operate the facility at steady state reactor core power
)
levels not in excess of 2558 megawatts thermal.
(2) Technical Specifications -
The Technical Specifications contained in Appendices A and B, ac revised through Amendment No. 206, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 203 to Facility Operating License DPR-71, the first performance is due at the end 1
of the first surveillance interval that begins at implementation of Amendment 203. For SRs that existed prior to Amendment 203, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 203.
2 Amendment No. 206 2.C.(2)(a)
Effective June 30,1982, the surveillance requirements listed below need not be completed until July 15,1982. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.
Specification 4.3.3.1, Table 4.3.3-1, items 5.a and 5.b 2.C.(2)(b)
Effective July 1,1982, through July 8,1982, Action statement "a" of Technical Specification 3.8.1.1 shall read as follows:
ACTION:
a.
With either one offsite circuit or one diesel generator of the above required A.C.
electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within two hours and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter; restore at least two offsite circuits and four diesel generators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.C.(3) Deleted by Amendment No. 206.
l 2.D.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 10 CFR 73.21 are entitled:
" Brunswick Steam Electric Plant Industrial Security Plan," with revisions submitted through September 23,1987; " Brunswick Steam Electric Plant Security Personnel Training and Qualification Plan," with revisions through January 20,1987; and " Brunswick Steam Electric Plant Safeguards Contingency Plan," with revisions submitted through March 27, 1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
2.E.
This license is subject to the following additional conditions for the protection of the environment:
{
- a. Deleted per Amendment 54,3-11-83
- b. Deleted per Amendment 54,3-11-83
- c. The licensee shall comply with the effluent limitations contained in National Pollutant l
Discharge Elimination System Permit No. NC0007064 issued pursuant to Section 402 of the Federal Water Pollution Control Act, as amended.
2.F.
In accordance with the requirement imposed by the October 8,1976, order of the United States Court Appeals for the District of Columbia Circuit in Natural Resources Defense I
Council v. Nuclear Reoulatory Commission, No. 74-1385 and 74-1586, that the Nuclear j
Regulatory Commission "shall make any licenses granted between July 21,1976 and such time when the mandate is issued subject to the outcome of the proceedings herein,"
the license issued herein shall be subject to the outcome of such proceedings.
2.G.
Deleted by Amendment No. 206 l
2.H.
This license is effective as of the date of issuance and shall expire at midnight on September 8,2016.
Amendment No. 206
. 2.1.
Deleted per Amendment No. 70 dated 5-25-84.
l l
2.J.
Deleted per Amendment No. 70 dated 5-25-84.
2.K.
Deleted by Amendment No. 206 l
2.L.
Power Uorate License Amendment imolementation The licensee shall complete the following actions as a condition of the approval of the power uprate license amendment (Amendment No.183):
(1) Deleted by Amendment No. 206 l
(2)' Deleted by Amendment No. 206 l
(3) Fuel Pool Decav Heat Evaluation The decay heat loads and the decay heat removal systems available for each refueling outage shall be evaluated, and bounding or outage specific analyses shall be used for various refueling sequences. Where a bounding engineering evaluation is in place, a refueling specific assessment shall be made to ensure that the bounding case encompasses the specific refueling sequence. In both cases (i.e.,
bounding or outage specific evaluations), compliance with design basis assumptions shall be verified.
(4) Deleted by Amendment No. 206 l
(5) Deleted by Amendment No. 206 3.
Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.
203, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Additional Conditions.
FOR THE NUCLEAR REGULATORY COMMISSION Original signed by R. C. DeYoung Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation Attachments:
Appendices A, Technical Specifications, and B -
Additional Conditions Date of issuance:
l September 8,1976 Amendment No. 206 i
kB RfC i
y-UNITED STATES j.
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-0001 49.....,o CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET N0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 236 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated October 27,1998, 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 Commissien; 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.
2.
Accordingly, the Operating License is amended as indicated in the attachment to this license amendment.
I l
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORV COMMISSION Y Q.
Sheri R. Peterson, Chief, Section 2 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License Date of Issuance:
October 5, 1999 l
ATTACHMENT TO LICENSE AMENDMENT NO. 236 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of Operating License No. DPR-62 with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Paaes Insert Paaes 3a
-3b 4
4 4a 4b 5
l l-6 l
i
F' 4
(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 236, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 233 to Facility Operating License DPR-62, the first performance is due at the end of the first surveillance interval that begins at implementation of I
Amendment 233. For SRs that existed prior to Amendment 233, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 233.
(a) The end of the current surveillance period for the surveillance requirements listed below may be extended beyond the time limit specified by Technical Specification 4.0.2a. After May 1,1982, the plant s%Il not be operated in Conditions 1,2, or 3 until the surveillance requirements listed below have been completed. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2a shall apply.
Specification 4.3.1.1; Table 4.3.1-1, items 9 & 10 4.3.1.2 4.3.1.3; Table 3.3.1-2, item 10 4.3.2.1; Table 4.3.2-1, items 1.d & 1.f 4.3.2.3; Table 3.3.2-3, itema 1.a.1 4.3.3.2; Table 4.3.3-1, items 4.c & 4.f 4.5.2.a 4.8:1.1.2.d.2 4.8.1.1.2.d.3 4.8.1.1.2.d.6 4.8.1.1.2.d.7 (b) Effective June 30,1982, the surveillance requirements listed below need not be completed until restart for Cycle 5 or July 15,1982, whichever occurs first. The unit shall not be operated in Conditions 1,2 or 3 until the surveillance requirements listed below have been completed. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.
Specification 4.3.3.1, Table 4.3.3-1, items 5.a and 5.b.
(
2.C.(2)(c)
Effective July 1,1982, through July 8,1982, Action statement "a" of Technical Specification 3.8.1.1 shall read as follows:
i ACTION: a.
With either one offsite circuit or one diesel generator of the above required A.C.
electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within two hours and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter; restore at least two offsite circuits and four diesel generators to OPERABLE status within j
7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. 236
]
I
. h 2.C.(3)
Deleted by Amendment No. 236 2.C.(4)
Eaualizer Valve Restriction The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation, except for one bypass valve which is left open to prevent pressure build-up due to ambient and conduction heating of the water between the equalizer valves.
l 2.C.(5)
Deleted by Amendment No. 233.
2.C.(6)
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualificatio.n, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21 are entitled: " Brunswick Steam Electric Plant Industrial Security Plan," with revisions submitted through September 23,1987; " Brunswick Steam Electric Plant Security Personnel Training and Qualification Flan," with revisions through January 20,1987; and
" Brunswick Steam Electric Plant Safeguards Contingency Plan," with revisions submitted through March 27,1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
2.D.
This license is subject to the following additional conditions for the protection of the environment:
- a. Deleted per Amendment 79,3-11-83
- b. Deleted per Amendment 79,3-11-83
- c. Deleted per Amendment 79,3-11-83 d The licensee shall comply with the effluent limitations contained in National Pollutant Discharge Elimination System Permit No. NC0007064 issued pursuant to Section 402 of the Fedcral Water Pollution Control Act, as amended.
2.E.
This license is effective as of the date of issuance and shall expire at midnight on December 27, 2014.
2.F.
Deleted per Amendment No. 98 dated 5-25-84.
2 G.
Deleted per Amendment No. 98 dated 5-25-84.
i 2.H.
Deleted by Amendment No. 236 f
Amendment No. 236 l
N.
n 6
2.1.
Power Ucrate License Amendment imolementation
~ The licensee shall complete the following actions as a condition of the approval of the power uprate license amendment (Amendment No. 214):
I (1) Deleted by Amendment No. 236.
l (2) Deleted by Amendment No. 236.
(3) Fuel Pool Decay Heat Evaluation The decay heat loads and the decay heat removal systems available for each refueling outage shall be evaluated, and bovading or outage specific analyses shall be used for various refueling sequene..v'nere a bounding engineering evaluation -
is in place, a refueling specific assessmer.t shall be made to ensure that the bounding l
case encompasses the specific refueling sequence. In both cases (i.e., bounding or outage specific evaluations), compliance with design basis assumptions shall be verified.
(4) Deleted by Amendment No. 236 l
(5) Deleted by Amendment No. 236 l
3.
Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.
233, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Additional Conditions.
Original signed by:
A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
Appendices A, Technical Specifications, and B -
Additional Conditions Date of issuance: Dec. 27,1974 Amendment No. 236
-