ML20107B909
| ML20107B909 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/12/1996 |
| From: | Russell W NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20107B912 | List: |
| References | |
| NUDOCS 9604170140 | |
| Download: ML20107B909 (9) | |
Text
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4 UNITED STATES j
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NUCLEAR REGULATORY COMMISSION i
e WASHINGTON, D.C. 3068H001
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SOUTH CAROLINA ELECTRIC & GAS COMPANY.
SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. NPF-12 1
1.-
The Nuclear Regulatory Comission-(the Comission) has found that:
A. 'The application for. amendment by South Carolina Electric & Gas Company (the licensee), dated August 18, 1995, as supplemented on November 1, 1995, February 14, (there are two supplemental letters with this date), and March 25, 1996, 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 Comission;
-There is reasonable assurance.(i) that the activities authorized by C. -
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 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, Facility Operating License No. NPF-12 condition 2.C(1) is hereby amended to read as follows:
(1) Maximum Power level SCE&G is authorized-to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal in accordance with 9604170140 960412 PDR ADOCK 05000395 P
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4 i the conditions specified herein and in Attachment I to this license.
The preoperational tests, startup tests and other items identified in Attachment 1 to this license shall. be completed-as specified.
, is hereby incorporated into this license.
3.
Further, the license is amended by changes to.the Technical i
Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2).of Facility O NPF-12 is hereby amended to readlas follows: perating License No.
E (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in. Appendix A, as revised '
through Amendment No.133
, and the Environmental Protection Plan a
contained in Appendix B, are hereby incorporated in the license.
g South Carolina Electric & Gas Conpany shall operate the facilityLin
'accordance with the Technica1' Specifications and the Environmental Protection Plan.
'4.,
This amendment is effective as of its date of issuance.and shall be implemented within 90 days of issuance.
L-FOR THE NUCLEAR REGULATORY COMMISSION
,(s)W William T. Russell, Director Office of Nuclear Reactor Regulation Attachments:
1.
Page 3 of Facility.0perating' License (included for convenience) 2.
Changes to the Technical-
. Specifications
.Date of~ Issuance: April 12, 1996 1-e h
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3-(4).SCE&G, pursuant to<the:Act and 10 CFR Parts 30, 40 and'70 to receive,. possess and.use at any time any byproduct, source and 1special nuclear material as sealed neutron sources for~ reactor-startup, sealed neutron sources for. reactor instrumentation and '
. radiation monitoring ' equipment calibration, and as fission detectors in. amounts as required; (5) SCE&G,. pursuant.to the Act and 10 CFR. Parts 30, 40 and 70, to-
_ receive, possess and use:in amounts as. required-any byproduct, i
source or special nuclear material without restriction to chemical
'or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and~
(6) SCE&G,l pursuant to.the Act and.10 CFR Parts 30, 40, and 70, to possess, but not separate,-such byproduct and special nuclear materials as may be produced by the operation of the facility.
7 i
C.'
This license shall be deemed to contain, andLis subject to, the conditions specified in the Commission's regulations: set 'forth.in 10 CFR Chapter I and. is subject to. all^ applicable. provisions of the Act and'to 4
the rules,Eregulations, 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-
~
SCE&G:is authorized to. operate the-facility at reactor core power, l
levels not in excess of 2900 megawatts thermal in accordance with-the conditions specified herein and in Attachment 1 to this license.-
The preoperational tests, startup tests and other items identified
. In Attachment 1 to this license shall be-completed as specified..is hereby incorporated into this license.
1 i
(2) Technical ~ Soecifications' and Environmental Protection'PlanL The Technical Specifications contained in Appendix A, as revised
~
. through Amendment No. ~133, and the. Environmental-Protection Plan contained in Appendix'B, are hereby incorporated-in~the. license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical. Specifications and the Environmental Protection Plan.
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-ATTACHMENT TO LICENSE AMENDMENT NO.133 T0' FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revisions are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 1-5 3/4 1-5 3/4 4-31 3/4 4-31 3/4 4-32 3/4 4-32 3/4 11-5 3/4 11-5 1
6-16a 6-16a' d
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DEFINITIONS PURGE - PURGING.
[
11.23 PURGE or PURGING is the controlled process ofdischarging air or gas from a confinement to maintain temperature pressure, humidity, concentration or other operating condition, in such a manne,r that replacement air or gas is
. required to purify the confinement.
QUADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shallbe the ratio of the maximum upper excore detector calibrated output to the avarage of the upper escore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated '
output to t se average of the lower excore detector calibrated outputs whichever is greater. With one excore detector inoperable, the ra==ining three, detectors shall be used for computing the average.
RATED THERMAL POWER
- 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2900 MWt.
].
' REACTOR TRIP SYSTEM RESPONSE TIME.
1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shallbe the timeintervalfrom when the monitored parameter exceeds its trip setpoint at the channel sensor
. until loss of stationary gripper coil voltage.
- REPORTABLE EVENT
- 1.27 A REPORTABLE EVENT shallbeanyofthoseconditionsspecifiedin Section 50.73 to 10 CFR Part 50.
' 1.28 SHUTDOWN MARGIN. shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be suberitical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the sm' gle rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shallbe the energization of each slave relay and
- verification ofOPERABILITY of each relay. The SLAVE RELAY TEST shallinclude a continuity check, as a minimum, of associated testable actuation devices.
I.30 NotUsed SOURCE CHECK
= 1.31 A SOURCE CHECK shallbe thequalitative assessmentofchannelresponse when the channel sensor is exposed to a radioactive source.
SUMMER:- UNIT 1 1-5 Amendment No. 35,104,117,133
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REACTOR' COOLANT' SYSTEM-t i
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CONTR'JLLING MATERIAL: ' LOWER SHELL r.
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CRITICALITY LIMIT SASED ON' INSERVICE NVOADSTAT!C TEST
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. TEMPERATURE (237*F) FOR THE.
.- SERVICE PERIOD UP T013 EFPYi i...i4 c,,
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l inoicatto truptmatunt (oco.r) i Figure 3.4-2 V. C. Sumer Unit 1: Reactor
- Coolant System Heatup Limitations (Heat.
up rates up to 50 and 100*F/hr) Applicable for the First 13 EFPYL(With Margins-10*F and 60 psig For Instrumentation Errors) o
. SutHER'-' UNIT 1 d /4 4-31
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1 REACTOR C00LANT' SYSTEM 1
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. MATERIAL PROPERTY BASIS l
CONTROLLING MATERIAL:
LOWER SHELL i
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10*F ART 'AFTER 13 EFPYi 1/4T, 96*F l
3/4T, 83*F 2500 may1wso
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Figure 3.4-3 ' V. C. Summer Unit 1 Reactor Coolant System Cooldown (Cooldown rates-upto100'F/hr)[. imitations'ApplicablefortheFirst 1
13 EFPY (With Margins 10*F and 60 psig For Instrumentation Errors) 1 SUMER - UNIT-1 3/4 4-32 Amendment tio. 33,113,
133 i
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~ RADIOACTIVE EFFLUENTS GAS STORAGE TANKS
~
LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank
- shall be limited to less than or equal to 131,000 curies noble gases l
(considered as Xe-133).
APPLICABILITY: At all times.
- ACTION:
ai.
With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of.
radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions ~ of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
' 4.11.2.6 The quantity of radioactiv'e material contained in each gas storage tank shall be determmed to be within the above limit at least one 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank. per..
/
t SUMMER' UNIT 1 3/4 11-5 Amendment No.104,133
j ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient 3.1.3.5 - Shutdown Bank Insertion Limit,3.1.3.6 --
Control Bank Insertion Limit,3.2.1 - Axial Flux Difference,3.2.2 -
Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor),
b.
WCAP-10216-P-A,Rev.1A," RELAXATION'OF CONSTANT AXIAL e
OFFSET CONTROL FQ SURVEILLANCE TECHNICAL
)
SPECIFICATION", February 1994 (W Proprietary).
~
b (Methodology for Specificetions 3.2.1 - Axial Flux Difference 4
(Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (FQ Methodology for W(Z) surveillance requirements).)--
c.
WCAP-10266-P-A,Rev.2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987; Including
. Addendum 2-A," BASH. METHODOLOGY IMPROVEMENTS AND RELIABILITY ENHANCEMENTS," MAY 1988, (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).
)
l The core operating limits shall be determined so that all applicable limits ~
(e.g., fuel thermal mechanical limits, core thermal-hydraulic limits, nuclear
' limits such as shutdown margin, and transient and accident analysis limits) of,#
the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and i
Resident Inspector.
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L-1 1
1 SUMMER -UNIT 1 6-16a Amendment No. 88,121,133
..