ML20206L744
| ML20206L744 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/10/1987 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206L704 | List: |
| References | |
| NUDOCS 8704170221 | |
| Download: ML20206L744 (9) | |
Text
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~,, UNITED STATES -
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DUKE POWER COMPANY DOCKET N0. 50-369.
McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.70 License No. NPF-9
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated May 14, 1986, as revised or supple-mented July 14, and November 21, 1986, and March 12, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I;
- 8. The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
8704170221 870410
2-
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment,-
and Paragraph 2.C.-(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.70, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance.
F0P, THE NUCLEAR REGULATORY COMMISSION W\
Darl Hood, Project Manager-PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: April 10, 1987
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DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.51 License No. NPF-17
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by_the Duke Power Company (the licensee) dated May 14, 1986, as revised or supple-mented July 14, and November 21, 1986, and March 12, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as -
set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) 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 Comission's regulations set forth in 10 CFR Chapter I; 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.
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- 2. Accordingly, the license is hereby amended by page changes to.the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.51, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
\6\
Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: April 10, 1987 4
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PWRf4/DPWR-A fY C/B PWR -A MDbn'4/D dan:mac DHood BJY od gqu e/87 04/3 04/ /87 04/ l /87 04/ [ /87
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- l ATTACHMENT TO LICENSE AMENDMENT NO.70 FACILITY OPERATING LICENSE NO. NPF-9 i
DOCKET N0. 50-369 :
AND TO LICENSE AMENDMENT Nd.51 FACILITY OPERATING LICENSE N0. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and-contain vertical lines indicating the areas of change.
Amended Page 3/4 6-5 3/4 6-9a 3/4 6-29 3/4 6-30' 5
TABLE 3.6-1 -
2 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS i
g PENETRATION TEST
- NUMBER SERVICE RELEASE LOCATION TYPE 7 M216 Pressurizer Relief Tank Makeup Auxiliary Building Type C E M212 Nitrogen to Pressurizer Relief Tank Auxiliary Building Type C a
g M259 Reactor Makeup Water Tank to NV
, System Auxiliary Building Type C o
[ M373 Ice Condenser Glycol In w xiliary Building Type C M372 Ice Condenser Glycol Out Auxiliary Building Type C M330 Nitrogen to Accumulators Auxiliary Building Type C M321 Safety Injection Test Line Auxiliary Building Type C M348 Upper Head Injection Test Line# Auxiliary Building Type C cp Post Accident Liquid Sample m Discharge #
M374 Containment Floor Sump Incore Instrument Sump Discharge Auxiliary Building ,
Type C M360 Reactor Coolant Drain Tank Gas Space to Waste Gas System Auxiliary Building Type C
([
=a EE M375 Reactor Coolant Drain Tank Heat Exchanger Discharge Auxiliary Building Type C yy M356 Equipment Decontamination Auxiliary Building Type C
$o M235 Pressurizer Sample Auxiliary Building Type C fee M309 Reactor Coolant Hot Leg Sample Auxiliary Building Type C ro e M322 Component Cooling to Component Cooling Drain Tank Auxiliary Building Type C
N TABLE 3.6-1 (Continued) '.*
[] SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS .
E n' PENETRATION TEST
' NUMBER SERVICE RELEASE LOCATION TYPE C
Cont. Press. Monitor Auxiliary Building Type C us Narrow Range w
g; M354 Fuel Transfer Tube Auxiliary Building Type B ro R
T if 5E
&R
$E re r+
NE l 5Y 72;E o=
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< sN
- Upon the deactivation of the Upper Head Injection System by removal of related components and piping and modifications to the Cold Leg Accumulators, this penetration is utilized for Post Accident Liquid Sample discharge.
TABLE 3.6-2 (Continued) .
! CONTAINMENT ISOLATION VALVES .
ni MAXIMUM ISOLATION
. ' VALVE NUMBER FUNCTION TIME (SEC)
$ 1. Phase "A" Isolation (continued) l 5 WL-1B NCDT Pumps Discharge Outside Containment Isolation <10 w WL-2A NCDT Pumps Discharge Inside Containment Isolation 710
= WL-39A NCDT Vent Inside Containment Isolation 710
- 5. WL-41B NCDT Vent Outside Containment Isolation 710 ro WL-64A RB Sump Pump Discharge Inside Containment Isolation 715 WL-658 RB Sump Pump Discharge Outside Containment Isolation 715 WL-321A Containment Vent Unit Drains Inside Containment Isolation 715 WL-3228 Containment Vent Unit Drains Outside Containment Isolation 715 WL-1301B## PALS Discharge Outside Containment Isolation 715 WL-1302A## PALS Discharge Inside Containment Isolation 315 3 g YM-115B Demin. Water Containment Outside Isolation <15 ,
[ 2. Phase "B" Isolation A
- KC-3388 NC Pump Supply Header Pent. Isolation (outside) <40 ,
KC-424B NC Pumps Return Hdr. Pent Inside Isolation 740 KC-425A NC Pumps Return Hdr. Outside Isolation 340 RN-252B Nonessential Supply to P9 Penetration Outside Isolation <30 RN-253A Nonessential Supply to NB Penetration.Inside Isolation , 730 gg RN-276A Nonessential Return to RB Penetration Inside Isolation 730 gg RN-2778 Nonessential Return to RB Penetration Outside Isolation 130
, EE RV-32A Lower Containment Vent. Unit Supply Containment Isolation -<60
$E
"" (outside) .
RV-33B Lower Containment Vent. Unit Supply Containment Isolation -<60 4
EE
(inside)
RV-76A Lower Containment Vent. Unit Discharge Containment Isolation -<60 EU (inside)
^^ RV-77B Lower Containment Vent. Unit Discharge Containment Isolation -<60
- (( (outside)
VI-129B "A" Header Containment Outside Isolation <15 i CO VI-150B Instrument Air Lower Containment Outside Isolation 715 VI-160B "B" Header Containment Outside Isolation 315 4 .l
TABLE 3.6-2 (Continued)
E CONTAINMENT ISOLATION VALVES E MAXIMUM n' ISOLATION i VALVE NUMBER FUNCTION TIME (SEC)
$ 2. Phase "B" Isolation (continued) w
" Upper Containment Vent. Unit Supply Containment Isolation Outside <30 RV-79A
" Upper Containment Vent. Unit Supply Containment Isolation Inside 730 RV-80B
$ RV-101A Upper Containment Vent. Unit Discharge Containment Isolation Inside 730 RV-102B Upper Containment Vent. Unit Discharge Containment Isolation Outside 330
[
- 3. Main Steam Isolation SM-1AB# Main Steam D Isolation <5 SM-3AB# Main Steam C Isolation 75 SM-5AB# Main Steam B Isolation 75 SM-7AB# Main Steam A Isolation 75 w SM-9AB# Main Steam D Isolation Bypass Ctrl. 75 1 SM-10AB# Main Steam C Isolation Bypass Ctrl. 75 m SM-11AB# Main Steam B Isolation Bypass Ctrl. 75 g SM-12AB# Main Steam A Isolation Bypass Ctr1. 35
- 4. Manual NC141* NC Pump Motor Oil Drain N.A.
NC142* NC Pump Motor Ui1 Drain -
N.A.
WE13* Equipment Decontamination N.A.
EE WE23* Equipment Decontamination N.A.
EE VX34* Containment H Sample N.A.
EE VX40* Containment H Sample N.A.
EE FW11* Refueling Wat r N.A.
"" FW13* Refueling Water N.A.
FW4* Refueling Water N.A.
E. E.
U "May be opened on an intermittent basis under administrative control.
y ** Valve also receives a High Radiation (H) isolation signal.
E3 #Not subject to Type C leakage tests. .
sm ##Upon the deactivation of the Upper Head Injection System by removal of~related components and piping and modifications to the Cold Leg Accumulators, this valve is utilized to isolate Post Accident Liquid Sample discharge.
NOTE: Times are for valve operation only, and do not include any sensor response _or circuit delay times.
See Specification 3/4.3.2 for system actuation response times.
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