ML20077G600
| ML20077G600 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/24/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20077G599 | List: |
| References | |
| NUDOCS 9107020058 | |
| Download: ML20077G600 (8) | |
Text
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(6) omm mn ouu.1rmicu w m picte tr.c modITh.ations identified in Paragraphs 3.1.1 through 3 @ 35'of i he NRC's'Ng Protection Saf ety Evaluation Repor,$ on'the
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Hrunswick f aciMated November 22, 1977 ard"6~upplements k* j [ g.
Lhereto.
These modilh ations shall tg,comfieted by the dates Ldentified in the Saf ety Ehhatj'srReport or Table 3.1 in g
p j,,D%.A ind is required to cornket'e the modif[htLans identified in supplements thereto.
In addition,'the licensee may proceed witti tection B.2.1 of trfpl emen t I to the Fire PDtstion Safety Cvaluatiojne and any future supplements.
IIihg sodij,Letillotis shall be completed by the dates identifiedMq" d ;
_.2.1
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This license shall be deemed to contain a.3d is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter !
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 708 and is subject to all applicable provisions of the A t and to the rules, regulations, ar'd orders of the Commission now or hereafter in effects and is subject to the additional conditions specified or incorporated belowl (1) Maximum Power Level The licensee is authoriced to operate the facility at steady state reactor core power levels not in excess of 2436 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 152, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
The licen~see will undertake a pr ogram f or seismic monitoring f or a minimum of two years unless termination is earlier approved by the NRC staff. The program and its control will be conducted in general conf ormity with the document " Brunswick Steam Electric Plant Program for Seismic Honitoring" dated June 10, 1975, as revised June 27, 1975.
The program uilt includet (a) not less than ten seismic monitoring stations (seven permanent and three portable), in an array approved by the NRC staff, unless a lesser number is approved by the NRC staf f in writing, and (b) quarterly reports on the monitoring data to be submitted to the NRC.
Should the NRC staff determine that initiation of Phase II as described within the program within the two year monitoring period, or Phase III following iniciation of Phase II, is required, the licensee will either comply with a request to proceed to Phase II (or Phase III) or icanediately request and be granted a hearing on the issue of whether the data on which the staf f's request is based justifies the initiation of Phase II (or 9107020058 910624 FDR ADOCK 05000324 (Fot-t/rij)
P PDR
Replacement for Paragraph.2.B.(6)
The licensee shall itoplement and inaintain in effect all provisions of the approved fire protection prograin as described in the Final Safety Analysis Report for the facility and as approved in the SER, dated Decertber 30, 1986 as st.pplemented on December 6, 1989, subject to the following provision:
s The Itcensee may tenke ebenges te the approved firs prstartion pro 6nu without prict approval of the Com iwaign only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
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2.
Facility Operating License No. DPR-62 is hereby issued to the Carolina Power & Light Company to read as follows:
A.
This license applies to the Brunswick Steam Electric Plant, Unit 2, a boiling water reactor and associated equipment (the facility),
owned by the Carolins Power & Light Company and North Carolina
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Ear.tc7n Xuaicipal Fuar Agu.u.y ar.d upat ateo by C tulina Power ano 1
i Light Company. The facility is located on the Cape fear River, near Southport in Brunswick County, North Carolina, and is described in the " Final Safety Analysis Report' as supplemented and amended (Amendments 1 through 29) and the " Environmental Report" as supplemented and amended (Supplements 1 through 7).
i B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Carolina Power & Light Company (1) Pursuant ta Section 104b of the Act and 10 CFR Part 50,
" Licensing of the Production and Utilization Facilities," to possess, use, and operate the f acility at the designated location in Brunswick County, North Carolina, in accordance with the procedures and limitations set forth in this licenset (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amendedt (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup,_
sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fissio'1 detectors in amounts as requiredt j
(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, i
and special nuclear materials without restriction to chemical or physical form, for sataple analysis or instrument calibration or associated with radioactive apparatus or componental (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)
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- he NRC's Fire Prot afety Evalu port on the N3 trunswick facility dated Nov
-1977'and supplements
. hereto. These mo tons shall be ce by the dates NMCtCO. hied
.dentifi e Safety Evaluation Report or Tab e mg ee=,=u=_,,.__
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C, This lisenec :hsll h-dessed tu. vntain and is subject to tne conditions speci' led 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 701 is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereaf ter in effects and is subject to the additional conditions specified or incorporated belows (1) Maximum Power Level The licensee is authorized to operate the f acility at steady state reactor core power levels not in excess of 2436 n,egawatts
( t he rmal ).
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 182, are hereby incorporated in the license. The licensee shall operrte the f acility in accordance with the lechnical Specifications.
(3) Carolina Power & Light Company will undertake a program for seismic monitoring f or a minimum of two years unless termination is earlier approved by tha NRC staff. The program and its coatrol will be conducted in general conformity with the document " Brunswick Steam Electric Plant Program for Seismic Monitoring" dated June 10, 1975 as revised June 27, 1975 and attached
- hereto as Appendix A.
The program will includet
- 1) not'le'ss than ten seismic monitoring stations (seven permanent and three portable), in an array approved by the NRC staf f, unless a lesser number is approved by the NRC staff in writing, and 2) quarterly reports on the monitoring data to be submitted to the NRC. Should the NRC staf f determine that initiation of Phase II as described within the program within the two year monitoring period, or Phase III f ollowing initiation of Phase II, is required the licensee will either comply with a request to proceed to Phase II (or Phase III) or immediately request and be granted a hearing on the issue of whether the data on which the staff's request is based justifies the initiation of Phase II (or Phase III) under the program for seismic monitoring agreed to by the licensee and the NRC staff.
Nothing herein will be construed as precluding changes in the program by the licensee which do not adversely af f ect the quantity of inf ormation derived from the monitoring program.
NRC will be informed of any such changes in the quarterly report.
(FOL-2/thr)
e Replacement for Paragraph 2.B.(6)
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The licensee 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 SER, dated December 30, 1986 as supplemented on Decernber 6,1989, 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.
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ENC 1/)SURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 I. 50 324 OPERATING LICENSES DPR 71 & DPR.62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT FIRE PROTECTION TECilNICAL SPECIFICATIONS AND LICENSE CONDITION (NRC TAC NOS 79416 and 79417)
Additional Revisions To Technical Specifications 4
4
_____-m.
ADMINISTRATIVE CONTROLS ACTIVITIES 6.5.3.3 The PNSC activities shall include the followingt Review of all procedures required by Specification 6.8 and changes a.
thereto (and any other procedures and changes thereto), any of which constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
b.
Review of all proposed tests or experiments that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
c.
Review of all proposed modifications that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
d.
Review of all proposed changes to the Technical Specifications or Operating License, prior to implementation.
Review of reports on violations of Technical Specifications including e.
reports covering evaluation and recommendations to prevent recurrence to the Manager - Brunswick Nuclear Project and to the Manager -
l Corporate Nuclear Safety Section.
f.
Performance of special reviews, investigations (or analyses), and reports thereon as requested by the Manager - Cot >porate Nuclear Safety Section.
g.
Review of all REPORTABLE EVENTS.
h.
Review of facility operations to detect potential nuclear safety hazards.
i.
Annual review of the Security Plan.
j.
Annual review of the Emergency Plan.
k.
Review of accidental, unplanned, or uncontrolled radioactive release including the preparation of reports cavering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Manager -
l Brunswick Nuclear Project and the Manager - Corporate Nuclear Safety Section.
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
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Review of the Fire Protection Prograts and implementing procedures and the submittal of recommended changes to the Nuclear Assessment t
Department, BRUNSWICK - UNIT 1 6-9 Amendment No. 138
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ADMINISTRATIVE CONTROLS ACTIVITIES 6.5.3.3 The PNSC activities shall include the followings Review of all procedures required by Specification 6.8 and changes a.
thereto (and any other procedures and changes thereto), any of which constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
b.
Review of all proposed tests or experiments that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
c.
Review of all proposed modifications that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
d.
Review of all proposed changes to the Technical Specifications or Operating License, prior to implementation.
Review of reports on violations of Technical Specifications including
{
e.
reports covering evaluation and recommendations to prevent recurrence to the Manager - Brunswick Nuclear Project and to the Manager -
l Corporate Nuclear Safety Section, f.
Perforn.ance of special reviews, investigations (or analyses), and reports thereon as requested by the Manager - Corporate Nuclear Safety Section.
g.
Review of all REPORTABLE EVENTS.
h.
Review of facility operations to detect potential nuclear safety hazards.
i.
Annual revlew of the Security Plan.
j.
Annual review of the Emergency Plan.
k.
Review of accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to. prevent recurrence and the forwarding of these reports to the Manager -
l Brunswick Nuclear Project and the Hanager - Corporate Nuclear Safety Section.
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION KANUAL.
Review of the Fire Protection. Program and implementin5 procedures m.
2()
and the submittal of recommended changes to the Nuclear Assessment Department, i
BRUNSWICK - UNIT 2 6-9 Amendment No. 170
.,-.- -