ML20215B913
| ML20215B913 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 09/29/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215B917 | List: |
| References | |
| NUDOCS 8610090440 | |
| Download: ML20215B913 (10) | |
Text
e urog'o UNITED STATES g
2, NUCLEAR REGULATORY COMMISSION
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E WASHINGTON, D. C. 20555
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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications 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 July 15, 1985, March 12, May 14, and July 14, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the 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 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 l
of the Comission's regulations and all applicable requirements have l
been satisfied, i
i PDR8610090440 860929 ADOCK 05000369
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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-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.63, 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 TS\\
Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: September 29, 1986 hsn PWR}./DP AV MWR-A PWR#4/DPWR-A PWR#4/DPWR-A fC/BETH P
M n:mac DWigginton DHood 30 AMc/
BJYoungblood 09// /86 09/ g /86 09/ g /86 09/y1/86 09/{V86 hh 1
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'o UNITED STATES
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WASHINGTON, D. C. 20555
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications 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 July 15, 1985, March 12 May 14, and July 14, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's 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 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.
r
a 2.
Accordingly, the. license is hereby amended by page changes to the Technical
-Specifications as indicated in the attachments to this license amendment, dnd 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.44, 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 COP 9tISSION V,\\
Darl Hood, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of' Issuance:
September 29, 1986
/
C'"
V %()(}'Q? Y y y 2sIi k
f.mac-A PWR#
WR PWR#4/DPWR-A PWR#4/DPWR-A OGC/ BET PWR#4/DPWR-A Mdun DWigginton DHood BJYoungblood 09//
/86 09/f/86 09/g/86 09/
/86 09/-).,f /86 l
c ATTACHMENT TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND 4
TO LICENSE AMENDMENT NO. 44 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. The corresponding over-leaf page is also provided to maintain document completeness.
Amended Overleaf M
Page 3/4 6-24 3/4 6-25 3/4 6-26 3/4 6-27 3/4 6-28 l
r i
l TABLE 3.6-2 W
CONTAINMENT ISOLATION VALVES g
i E
m MAXIMUM i
ISOLATION VALVE NUMBER FUNCTION TIME (SEC)
U 1.
Phase "A" Isolation w
4 m
BB-18#
Steam Generator A Blowdown Containment Outside Isolation
<10 l
E 88-28#
Steam Generator B Blowdown Containment Outside Isolation 310 i
m B8-3B#
Steam Generator C Blowdown Containment Outside Isolation
<10 l
88-48#
Steam Generator D Blowdown Containment Outside Isolation 710 i
BB-5A#
Steam Generator A Blowdown Containment Inside Isolation 710 j
BB-6A#
Steam Generator B Blowdown Containment Inside Isolation 710 BB-7A#
Steam Generator C Blowdown Containment Inside Isolation 710 i
BB-8A#
Steam Generator D Blowdown Containment Inside Isolation
<10 CF-26AB#
Steam Generator D Feedwater Containment Isolation
<5 R
CF-28AB#
Steam Generator C Feedwater Containment Isolation 75 CF-30AB#
Steam Generator B Feedwater Containment Isolation 75 i
CF-35AB#
Steam Generator A Feedwater Containment Isolation 75 j
CF-126B Steam Generator A Main Feedwater to Auxiliary Feedwater
<10 1
Nozzle Isolation i
CF-127B Steam Generator 8 Main Feedwater to Auxiliary Feedwater
-<10 Nozzle Isolation CF-1288 Steam Generator C Main Feedwater to Auxiliary Feedwater
-<10 Nozzle Isolation
?F CF-129B Steam Generator D Main Feedwater to Auxiliary Feedwater Nozzle Isolation
-<10 CF-134A Steam Generator A Feedwater Containment Isolation Bypass
<10 I
E$
CF-135B Steam Generator B Feedwater Containment Isolation Bypass 710 l
CF-136A Steam Generator C Feedwater Containment Isolation Bypass 710 EE CF-137A Steam Generator D Feedwater containment Isolation Bypass 710 l
y CF-151B Auxiliary Nozzle Temper SG A 310 l
l EE 11 i
ee NN 1
vv 4
e I
j l
TABLE 3.6-2 (Continued) l E
j g
CONTAIPMFNT ISOLATION VALVES E
i m
MAXINUM i
{
ISOLATION i
g VALVE NUPSER FUNCTION TINE (SEC) b 1.
Phase "A" Isolation (continued) 1 g
CF-153A Auxiliary Nozzle Temper SG B
$10
?
o-CF-1558 Auxiliary Nozzle Temper SG C
$10 m
CF-1578 Auxiliary Nozzle Temper SG D
_10 KC-305B#
Excess Letdown Hx Supply Pent. Isolation Outside 530 l
KC-315Bf Excess Letdown Hx Ret. Ndr. Pent. Isoletion Outside
<30 l
KC-320A NCDT Hx Supply Hdr. Pent. Isolation Outside
<.5 5 l
KC-3328 NCOT Hx Supply Hdr. Pent. Isolation Inside 95 j
KC-333A NCDT Hx Return Hdr. Pent. Isolation Outside
<15 KC-429B RB Drain Header Inside Containment Isolation E15
^
KC-430A RB Drain Header Outside Containment Isolation 515 NB-2608 Reactor Makeup Water Tank to NV System
$15 NC-538 Nitrogen to Pressurizer Relief Tank Containment
-<10 l
Isolation Outside NC-54A Nitrogen to Pressurizer Relief Tank Containment
-<10 Isolation Inside l
NC-568 PRT Makeup
<10
[$I NC-1958 NC Pump Motor 011 Containment Isolation Outside 715 i
i
=
NC-1%A NC Pump Motor Oil Containment Isolation Inside 715 kk 4
s=
NF-228A Air Handling Units Glycol Supply Containment
-<15 Isolation Outside ff NF-233B Air Handling Units Glycol Supply Containment j-o; Isolation Inside
-<15 l
i NF-234A Air Handling Units Glycol Supply Containment
((
Isolation Outside
-<15
^^
ee ms NI-47A Accumulator Nitrogen Supply Outside Containment Isolation
-<15 j
NI-95A Test HOR Inside Containment Isoletion
$10 n
TABLE 3.6-2 (Continued) x 4
CONTAINMENT ISOLATION VALVES E
m MAXIMUM ISOLATION g
VALVE NUMBER FUNCTION TIME (SEC) 1.
Phase "A" Isolation (continued)
=
NI-968 Test HDR Outside Containment Isolation
<10 E
NI-1208 Safety Infection Pump to Accumulator Fill Line Isolation 310 g
NI-255ff Note 1 UHI Check Valve Test Line Isolation
<10 l
m t
NI-258A UHI Check Valve Test Line Isolation
<10 i
NI-264Bb UHI Check Valve Test Line Isolation 710 NI-266A UHI Check Valve Test Line Isolation 710 NI-267A UHI Check Valve Test Line Isolation
-10 s
NM-3AC Pressurizer Liquid Sample Line Inside Containment Isolation
<15 i
NM-6A Pressurizer Steam Sample Line Inside Containment Isolation 715 j
R NM-7B Pressurizer Sample Header Outside Containment Isolation 715 NM-22AC NC Hot Leg #1 Sample Line Inside Containment Isolation 715 i
NM-25AC NC Hot Leg #4 Sample Line Inside Containment Isolation 715 NM-26B NC Hot Legs Sample Hdr. Outside Containment Isolation 715 l
NM-728 NI Accumulator A Sample Line Inside Containment Isolation 715 j
NM-75B NI Accumulator 3 Sample Line Inside Containment Isolation 515 NM-788 NI Accumulator C Sample Line Inside Containment Isolation
<15 i
NM-818 NI Accumulator D Sample Line Inside Containment Isolation 715 l
NM-82A NI Accumulator Sample Hdr. Outside Containment Isolation 715 Il NM-187M SG A Upper Shell Sample Containment Isolation Inside 715 l-EE NM-190M SG A Blowdown Line Sample Containment Isolation Inside 715 1
NM-191B#
SG A Sample Hdr. Containment Isolation Outside 215 I
EE NM-1978#
SG B Upper Shell Sample Containment Isolation Inside 715 NM-200B#
SG B Blowdown Line Sample Containment Isolation Inside 715 IE NM-201A#
SG B Sample Hdr. Containment Isolation Inside 715 t
W NM-207M SG C Upper Shell Sample Containment Isolation Inside 715 i
XX NM-210M SG C Blowdown Line Sample Containment Isolation Inside 715 I
EE NM-2118#
SG C Sample Hdr. Containment Isolation Outside 715 33 NM-2178#
SG D Upper Shell Sample Containment Isolation Inside 715 g
NM-220B#
SG D Blowdown Line Sample Containment Isolation Inside 315 l
Note 1:
Upon the deactivation of the UHI System by removal of related components and piping and modifications to the Cold Leg Accumulators, this specification is no longer applicable.
l
~
l
^
TABLE 3.6-2 (Continued) z E
CONTAINMENT ISOLATION VALVES 5
j A
MAXIMUM J
e ISOLATION g
VALVE NUPEER FUNCTION TIME (SEC) 5 1.
Phase "A" Isolation (continued) j!
g NM-221M SG D Sample Hdr. Containment Isolation Outside
<15 1
m NV-7B#
Letdown Containment Isolation Outside
<10 i
NV-94M NC Pumps Seal Return Containment Isolation Inside 710
{
NV-958#
NC Pumps Seal Return Containment Isolation Outside 710 i
NV-457M 45 gpm Letdown Orifice Outlet - Containment Isolation 715 NV-458M 75 gpa Letdown Orifice Outlet - Containment Isolation 315 i
NV-459M High Pressurizer Letdown Orifice Outlet - Containment
-<15 Isolation 4
NV-842AC Standby Makeup Pump Suction Containment Isolation Inside
<15
{
NV-849AC Standby Makeup Pump to RCS seals
$15 l
I i
RF-821A Containment Isolation Outside (Unit 1)
<15 O
RF-832A Containment Isolation Outside (Unit 2) 715 VB-49B Breathing Air Containment Isolation
<15 i
VE-5A Containment #2 Purge to Annulus Inside Containment Isolation
<15
^
VE-6B Containment #2 Purge to Annulus Outside Containment Isolation 715 FF VE-10A Containment #2 Purge Blower Outlet, Containment Isolation 715
{$
(outside) a&
VI-148B Instru. Air Upper Containment Outside Isolation
<15 5I sh "3
j!
??
~~
vv
(
l l
t x
TABLE 3.6-2 (Continued) a 5
CONTAINMENT ISOLATION VALVES A
MAXIMUM c:
ISOLATION 5
VALVE NUMBER FUNCTION TIME (SEC)
DI 1.
Phase "A" Isolation (continued)
~
VI-362A RB Isolation Valve for VI Supply to Annulum Vent.
515 VP-1B**
Upper Containment Purge S*upply #1 Outside Isolation 53 VP-2A**
Upper Containment Purge Supply #1 Inside Isolation 53 VP-3B**
Upper Containment Purge Supply #2 Outside Isolation
$3 VP-4A**
Upper Containment Purge Supply #2 Inside Isolation
$3 VP-6B**
Lower Containment Purge Supply #1 Outside Isolation
$3 VP-7A**
Lower Containment Purge Supply #1 Inside Isolation
$3 VP-88**
Lower Containment Purge Supply #2 Outside Isolation
$3 u,);
VP-9A**
Lower Containment Purge Supply #2 Inside Isolation 13 VP-10A**
Upper Containment Purge Exhaust #1 Inside Isolation
$3 o,
VP-11B**
Upper Containment Purge Exhaust #1 Outside Isolation 13 VP-12A**
Upper Containment Purge Exhaust #2 Inside Isolation 13
- VP-13B**
Upper Containment Purge Exhaust #2 Outside Isolation 53 VP-15A**
Lower Containment Purge Exhaust #1 Inside Isolation 53 VP-16B**
Lower Containment Purge Exhaust #1 Outside Isolation 13 VP-17A**
Incore Instru. Room Purge Supply Inside Isolation
$3 VP-188**
Incore Instru. Room Purge Supply Outside Isolation
$3 VP-19A**
Incore Instru. Room Purge Exhaust Inside Isolation 13 VP-20B**
Incore Instru. Room Purge Exhaust Outside Isolation
$3 VQ-1A Containment Air Release Inside Isolation
$3 VQ-2B Containment Air Release Outside Isolation
$3 VQ-5B Containment Air Addition Outside Isolation 13 VQ-6A Containment Air Addition Inside Isolation 13 VS-128 Containment Station Air Outside Isolation
<15 VX-31A Containment Atmosphere Inside Isolation
$5 VX-33B Containment Atmosphere Inside Isolation
$5
.