ML20207E386
| ML20207E386 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/02/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207E391 | List: |
| References | |
| TAC-65685, NUDOCS 8808180031 | |
| Download: ML20207E386 (12) | |
Text
- - _ _ _ _ _ _ _ _ _ _ _ _ _.
'o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION g
-l WASHINGTON, D. C. 20555
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TOLED0 EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Toledo Edison Company and The ClevelandElectricIlluminatingCompany(thelicensees)datedAugust7, 1987 as supplemented March 21 and May 2, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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; 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 Cosmission's regulations; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the pubitc; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been shtisfied.
2.
Accordingly, the Itcense is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
kbR bOK 46 P
2-(a) Technical Specifications The Technical Specifications contained in Appendicis A and B as revised through Amendment No.114 are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than September 16, 1988.
FOR THE NUCLEAR REGULATORY C0!94ISSION b Project Directorate III-3 Kenneth E. Perkins, Director U-Division of Reactor Projects - III, IV, V, & Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 2, 1988
ATTACHMENT TO LICENSE AMENDMENT NO. 114 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove lusert 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 3/4 6-21 3/4 6-21 3/4 6-22 3/4 6-22 1
TABLE 3.3-5 (Continued)
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIMI IN SECONDS i.
Containment Isolation Valves (cont'd) 5.
Pressurizer Sample NA 6.
Service Water to Cooling Water NA 7.
Vent Header NA 8.
Drain Tack NA 9.
Core Flood Tank Vent NA 10.
Core Flood Tank Fill NA 11.
Steam Generator Sample NA 12.
Quench Tank NA 13.
Emergency Sump NA 14.
RCP Seal Return NA
- 15. Air Systems NA 16.
N, System NA 17.
Quench Tank Sample NA
- 18. RCP Seal Inlet NA 19.
Core Flood Tank Sample NA 20.
RCP Standpipe Demin Water Supply NA 21.
Containment H Dilution Inlet NA 22.
Containment H Dilution Outlet NA j.
BVST Outlet Valves NA k.
Low Pressure Injection 1.
Decay Heat Pumps NA 2.
Low Pressure Injection Valves NA 3.
Decay Heat Pump Suction Valves NA 4.
Decay Heat Cooler Outlet Valves NA 5.
Deccy Heat Cooler Bypass Valves NA 1.
Containment Spray Pump NA m.
Component Cooling Isolation Valves 1.
Inlet to Containment NA 2.
Outlet from Containment NA 3.
Inlet to CRDM's NA 4.
CRDM Booster Pump Suction NA 5.
Component Cooling from Decay Heat Coolers NA l
DAVIS-RESSE, UNIT 1 3/4 3-15 Amendment No. 112
\\
TABLE 3.3-5 (Continued)
S_m TY FEATURES SYSTEM PISPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECON'uS I
2.
Containment Pressure - High a.
Fans 1.
Emergency Vent Fans 1 25*
2.*
Containment Cooler Fans 5 45*
b.
HV & fl Isolation Valves 1.
ECCS Room
< 75*
2.
Emergency Ventilation j75*
3.
Containment Air Sample
< 30*
4.
Containment Purge i 15*
5.
Penetration Room Purge 375*
c.
Control Room HV & AC Units i 10*
d.
High Pressure Injection 1.
High Pressure Injection Pumps 5 30*
2.
High Pressure Injection Valves 5 30*
Component Cooling Water e.
1.
Component Cooling Water Pumps 5 180*
2.
Component Cooling Aux. Equip. Inlet Valves 5 180*
3.
Component Cooling to Air Compressor Valves 1 180*
f.
Service Water System 1.
Service Water Pumps 1 45*
2.
Service Water Free Component Cooling Heat Exchanger Isolation Valves S NA*
g.
Containment Spray Isolation Valves i 30*
h.
Emergency Diesel Generator i 15*
i DAVIS-RESSE, UNIT 1 3/4 3-16 Amendment No. 114
k TABLE 3.3-5 (Continued)
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 2.
Containment Pressure - High (Continued) 1.
Containment Isolation Valves 1.
Vacuum Relief
< 30*
2.
Normal Sump 525*
3.
RCS Letdown Delay Coil Outlet
< 30*
4.
RCS Lef.down High temperature 530*
5.
Pressurizer Sample 5 48*
6.
Service Water to Cooling Water
< 45*
7.
Vent Header i 15*
8.
Drain Tank i 15*
9.
Core Flood Tank Vent i 15*
10.
Core Flood Tank Fill i 15*
11.
Steam Generator Sample 515*
12.
Quench Tank
-< 15*
13.
Emergency Sump NA*
14.
RCP Seal Return
< 45*
- 15. Air System i 15*
16.
N2 System j15*
17.
Quench Tank Sample 1 35*
18.
RCP Seal Inlet
< 17*
19.
Core Flood Tank Sample 515*
20.
RCP Standpipe Demin Water Supply 1 15*
21.
Containment H Dilution Inlet
< 75*
22.
Containment H2 Dilution Outlet j75*
j.
BWST Outlet Valves NA*
k.
Low Pressure Injection 1.
Decay Heat Pumps 1 30*
2.
Low Pressure Injection Valves 1 NA*
3.
Decay Heat Pump Suction Valves
$ NA 4.
Decay Heat Cooler Outlet Valves 1 NA*
5.
Decay Heat Cooler Bypass Valves 5 NA*
3.
Containment Pressure--High-High a.
Containment Spray Pump 1 80*
b.
Component Cooling Isolation Valves 1.
Inlet to Containment i 25*
2.
Outlet from Containment i 25*
DAVIS-RESSE, U'-lIT 1 3/4 3-17 Amendment No.112,
TABT.E 3.3-5 (Continued)
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS b.
Component Cooling Isolation Valves (Continued) 3.
Inlet to CRDM's
< 35*
4.
CRDM Booster Pump Suction 535*
5.
Component Cooling from Decay Heat Cooler 1 NA*
4.
RCS Pressure-Low
)
j a.
Fans l
1.
Emergency Vent Fans 1 25*
2.
Containment Cooler Fans 5 45*
b.
(
1.
ECCS Room
( 75*
{
2.
Emergency Ventilation 575*
3.
Containment Air Sample 5 30*
4.
Containment Purge 5 15*
5.
Penetration Room Purge 5 75*
c.
Control Room HV & AC Units 5 10*
I d.
High Pressure Injection 1.
High Pressure Injection Pumps 5 30*
2.
High Pressure Injection Valves 5 30*
e.
Component Cooling Water 1.
Component Cooling Water Pumps i 180*
2.
Component Cooling Aux. Equipment Inlet Valves
< 180*
3.
Component Cooling to Air Compressor Valves i 180*
1 f.
Service Water Systea
{
l 1.
Service Water Pumps 1 45*
2.
Service Water from Component Cooling Heat Exchanger Isolation Valves i NA*
3 Containment Sprsy Isolation Valves 1 80*
l h.
Emergency Diesel Generator 5 15*
{
l DAVIS-BESSE, UNIT 1 3/4 3 18 Amendment No. 114 I
1 l
TABLE 3.3-5 (Continued)
SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AhT FUNCTION RESPONSE TIME IN SECONDS 4.
RCS Pressure-Low (continued) 1.
Containment Isolation Valves 1.
Vacuum Relief
< 30*
2.
Normal Sump 525*
3.*
RCS Letdown Delay Coil Outlet 3 30*
4.
RCS Letdown High Temperature 5 30*
5.
Pressurizer Sample 5 45*
6.
Service Water to Cooling Water 5 45*
7.
Vent Header
< 15*
8.
Drain Tank i 15*
9.
Core Flood Tank Vent i 15*
10.
Core Flood Tank Fill i 15*
11.
Steam Generator Semple 515*
12.
Quench Tank
$ 15*
- 13. Emergency Sump NA*
14.
Air Systems i 15*
15.
Na System i 15*
16.
Quench Tank Sample 1 35*
17.
Core Flood Tank Sample i 15*
- 18. RCP Standpipe Demin Water Supply 1 15*
19.
Containment H Dilution Inlet
< 75*
20.
Containment H Dilution Outlet 575*
j.
BWST Outlet Valves NA*
5.
RCS Pressure--Low-Low a.
Low Pressure Injection 1.
Decay Heat Pumps 3 30*
2.
Low Pressure Injection Valves
< NA*
3.
Decay Heat Pump suction Valves 5NA*
4.
Decay Heat Cooler Outlet Valves 3 NA*
5.
Decay Heat Cooler Bypass Valo;s 1 NA*
b.
Component Cooling Isolation Valves 1.
Auxiliary Equipment Inlet S 90*
2.
Inlet to Air Compressor i 90*
3.
Component Cooling from Decay Heat Cooler i NA*
c.
Containment Isolation Valves 1.
RCP Seal Return
< 45*
2.
RCP Seal Inlet 517*
DAVIS-BESSE, UNIT 1 3/4 3-19 Amendment No. 44,112, b
TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PENETRATION VALVE ISOLATION KUMBER NUMBER FUNCTION TIME
~~
(seconds) 16 RC1719A Containment Vessel Vent Header 10 16 RC1719B Containment Vessel Vent Header 10 18 #
SS598 Steam Generator Secondary Water Sample Line 10 19 #
HP2A High Pressure Injection Line 15 20 #
HP2B Hi h Pressure Injection Line 15 t
21 DW6831A Demineralized Water Supply Line 10 21 DW6831B Demineralized Water Supply Line 10 22 #
HP2D High Pressure Injection Line 15 25 CS1531 Containment Spray Line 35 26 CS1530 Containment Spray Line 35 30 #
DH9A Containment Sump Emergency Recirc Line 71 31 #
DH98 Containment Sump Esat~gency Recirc Line 71 32 RC1773A RCS Drain to RC Drain Tank 10 32 RC1773B RCS Drain to RC Drain Tank 10 DAVIS-BESSE, UNIT 1 3/4 6-17 Amendment No. 3,72,112,
TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PEKETRATION VALVE ISOLATION KUMBER NUMBER FUNCTION TIME (seconds) 41 RC232 Pressurizer Quench Tank Circulating Inlet Line 10 42A SA2010 Service Air Supply Line 10 l
42B CV5010E Containment Vessel Air Sample Return 15 43A IA2011 Instrument Air Supply Line 10
)
43B CV5011E Containment Vessel Air Sample Return 15 44A CF1541 Core Flood Tank Fill and N2 Supply Line 10 44B NN236 Pressurizer Quench Tank N2 Supply I
Line 10 I
47A CV1545 Core Flood Tank Sample Line 10 47B CV1542 Core Flood Tank Vent Line 10 l
l 48 RC229A Pressurizer Quench Tank Circulating 3
Outlet Line 10
'i8 RC229B Pressurizer Quench Tank circulating Outlet Line 10 50 #
HP2C High Pressure Injection Line 15 51 CV5037 Hydrogen Purge System Exhaust Line 60 51 CV5038 Hydrogen Purge Systew Exhaust Line 60 I
$2 MU66A Reactor Coolant Pump Seal Supply 12 53 NU66B Reactor Coolant Pump Seal Supply 12 54 MU66C Reactor Coolant Pump Seal Supply 12 55 NU66D Reactor Coolant Pump Seal Supply 12 56 NU38 Reactor Coolant Pump Seal Return 12 56 MU59A Reactor Coolant Pump Seal Return 30 56 NU59B Reactor Coolant Pump Seal Return 30 56 NU59C Reactor Coolant Pump Seal Return 30 56 NU59D Reactor Coolant Pump Seal Return 30 DAVIS-RESSE, UNIT 1 3/4 6-18 Amendment No. 79.109,
TABLE 3.6-2 CONTAINMENT ISOLATION VALVES (Continued)
PENETRATION VALVE ISOLATION KUMBER NUMBER FUNCTION TIME (seconds)
- 29 #
DH11 Decay Neat Pump Suction Line N/A
- 29 DH23 Decay Heat Pump Suction Line N/A 29 #
PSV4849 Decay Heat Pump Suction Line N/A 35 #
AF599 Auxiliary Feedwater Line N/A 36 #
AF608 Auxiliary Feedwater Line N/A 37 #
FW601 Main Feedwater Line N/A 38 #
FW612 Main Feedwater Line N/A
- 39 #
MS100 Main Steam Line N/A
- 39 #
ICS11A Main Steam Line
?I/A 39 #
MS375 Main Steam Line 1:/A 39 #
MS100-1 Main Steam Line N/A
- 39 #
MS107 Main Steam Line N/A
- 39 #
MS107A Main Steam Line N/A
- 40 #
MS106 Main Steam Line N/A
- 40 #
MS106A Main Steam Line N/A
- 40 #
MS101 Main Steam Line N/A
- 40 #
ICS11B Main Steam Line N/A 40 #
MS394 Main Steam Line N/A 40 #
MS101-1 Main Steam Line N/A 41 RC113 Pressurizer Quench Tank Inlet Line N/A 42A SA502 Service Air SupplS Line N/A 42B CV124 Containment Vessel Air Sample Return N/A 43A IA501 Service Air Supply Line N/A 43B CV125 Containment Vessel Air Sample Return N/A 44A CF15 Core Flood Tank Fill and Nitrogen i
topply Line N/A 44B NN58 Pressuriser Quench Tank Inlet Line N/A
- 47A CF2A Core Floed Tank Sample Line N/A
- 47A CF2B Core Flood Tank Sample Line N/A
- 47B CF5A Core Flood Tank Vent Line N/A
- 41B Cr5B Core Flood Tank Vent Line N/A 49 DH87 Refueling Canal Fill Line N/A 49 DH88 Refueling Canal Fill Line N/A i
DAVIS-BESSE, UNIT 1 3/4 6-21 Amendment No. 3,
TABLE 3.6-2 CONTAINKENT ISOLATION VALVES (Cot:Linued)
PEKETRATION VALVE ISOLATION NUMBER NUMBER FUNCTION
__ TIME (seconds) 49 DH87 Refueling Canal Fill Line N/A 49 DH88 Refueling Canal Fill Line N/A 50 #
HP48 Hign Pressure Injection N/A 50 MU6421 RCS Makeup Line N/A 52 MU242 RCP Seal Water Supply N/A 53 MU243 RCP Seal Water Supply N/A 54 MU244 RCP Seal Water Supply N/A
~5 MU245 RCP Seal Water Supply N/A 7
59 Flange Secondary Side C162..ing (Inside Containment)
N/A 59 Flante Secocdary Side Cleaning (Outside Containment)
N/A 57 MS603 Steam Generator Blowdown Line N/A 60 MS611 Steam Generator Blowdown Line N/A 67 CV209 Hydrogen Dilution System Supply N/A 69 CV210 Hydrogen Dilution System Supply N/A 71A #
CV2000B Containment Pressure Sensor N/A 71C CT16 Core Flood Tank Nitrogen Fill Line N/A 72A 6 CV2001B Containment Pressure Sensor N/A 72C #
CV624B Containment Pressure Differential Transmitter N/A
??A #
CV2002B Containment Pressure Sensor N/A 73C #
CV645B Containment Pressure Differential Transmitter N/A 74A #
CV20038 Containment Pressure Sensor N/A
- 74C DH2735 Pressurizer Auxiliary Spray N/A
- 74C DH2736 Pressuriser Auxiliary Spray N/A
- May be opened on an intermittent basis under administrative control.
- Not subject to Type C leakage tests.
- Surveillance testing not required prior to entering N0DE 4 but shall be performed prior to entering Mode 3.
- Provisions of Specification 3.0.4 are not epplicable provided the valve is in the closed positions and deactivated.
DAVIS-BESSE, UNIT 1 3/4 6 22 Amendment No. 3,31,79,112,
_