ML20100K024
| ML20100K024 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/22/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20100K028 | List: |
| References | |
| NPF-57-A-093 NUDOCS 9603010013 | |
| Download: ML20100K024 (8) | |
Text
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WASHINGTON, D.C. 20065 4001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric
& Gas Company (PSE&G) dated October 31,, 1994, 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 Commission; 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license 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-57 is hereby amended to read as follows:
9603010013 960222 PDR ADOCK 05000354 P
. (2) Technical Soecifications and Environmental Protection Plan The Technical. Specifications contained in Appendix A, as revised through Amendment No.93, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r]&
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J6 n F. Stolz, Direct' oject Directorate
-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1996
ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 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.
Remove Insert
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3/4 6-21 3/4 6-21 3/4 6-30 3/4 6-30 3/4 6-31 3/4 6-31 3/4 6-32 3/4 6-32 3/4 6-36 3/4 6-36 i
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TABLE 3.6.3-1 (Continued)
' PRIMARY CONTAINMENT ISOLATION VALVES MAKIMUM ISOLATION PENETRATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds). NOTE (S)
P&ID (c) RHR Shutdown Cool.ing Suction Isolation Valve M-51-1 i
Outside: HV-F008 (BC-V164)
P3 45 3
(d) RHR Head Spray' Isolation Valve M-51-1.
Outside: HV-F023 (BC-V020)
P10 60 3
(e) RHR Shutdown Cooling Return Isolation Valves M-51-1 Outside:
Loop A: HV-F015A (BC-V110)
P4B 45 3
Loop B: HV-F015B (BC-V013)
P4A 45 3
'4. Group 4 - Core Spray System Outside:
(a) Core Spray Test to Suppression Pool Isolation Valves M-52-1 Loop A: HV-F015A (BE-V025)
P217B 80 11 Loop B: HV-F015B (BE-V026).
P217A:
80 11
- 5. Group 5 - High Pressure Coolant Injection (HPCI) System (a) HPCI Turbine Steam Supply Isolation Valves M-55-1 Inside: HV-F002 (FD-V001)
P7 NA 3
HV-F100 (FD-V051)
P7 NA 3
Outside: HV-F003 (FD-V002)
P7 NA 3
(b) HPCI Pump Suction Isolation Valve M-55-1 ~
Outside:
HV-F042 (BJ-V009)
P202 NA 11 HOPE CREEK 3/4 6-21 ATENDMENT NO. 93
o TABLE 3.6.3-1 (Continued)..
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION PENETRATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)
NOTE (S)
P&ID Outside:
(b)
RCIC Pump Suction Isolation Valve HV-F031 (BD-V003)
P208 NA 11' M-49-1 Outside:
(c)
RCIC Minimum Return Line Isolation Valve SV-F019 P209 NA 11 M-49-1 Outside:
(d)
RCIC Vacuum Pump Discharge HV-F060 (FC-V0ll)
P210 NA 4
M-49-1 (e)
Feedwater Line Discharge Valve Outside:
HV-F013 (BD-V005)
P2A NA 2
M-49-1
- 4. Group 25 - Core Spray System (a)
Core Spray injection Valves M-52 Outside:
Loop A&C HV-F005A (BE-V007)
PSB NA-3 Loop-B&D HV-F005B 3E-V003)
PSA NA 3
(b)
Core Spray Suppression Pool Suction Valves M-52-1 Outside:
Loop A HV-F001A (BE-V017)
P216D NA 11 Loop B HV-F001B (BE-V019)
P216A NA 11 Loop C HV-F001C (BE-V018)
P216C NA 11 Loop D HV-F001D (BE-V020)
P216B NA' 11 (c)
Core Spray Minimum Flow Valves
. M-52-1 Outside:
Loop A&C HV-F031A (BE-V035)
P217B NA 11 Loop B&D HV-F031B (BE-V036)
P217A NA 11 V
HOPE CREEK 3/4 6-30 AMENDMENT NO. 93
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TABLE ^3.6.3-1 Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION PENETRATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)
NOTE (Sj.
P&ID 5.
Group 26 - Residual Heat Removal System (a)
Low Pressure Coolant Injection Valves
.M-51-1 Outside:
Loop A: HV-F017A (BC-V113)
P6C NA 3
Loop B: HV-F017B (BC-V016)
P6B NA 3
Loop C: HV-F017C (BC-V101)
P6D NA 3
Loop D: HV-F017D (BC-V004)
P6A NA 3
(b) RHR Containment Spray M-51-1 Outside:
Loop A: HV-F021A (BC-V116)
-P24B NA 3
Loop B: HV-F021B (BC-V019)
P24A NA 3
(c) RHR Suppression Pool Suction M-51-1 Outside:
Loop A: HV-F004A (BC-V103)
P211C NA 11 Loop B: HV-F004B (BC-V006)
P211B NA 11 Loop C: HV-F004C (BC-V098)
P211D NA 11 Loop D: HV-F004D (BC-VOO1)
P211A NA 11 (d) RHR Minimum Flow Isolation Valves M-51-1 Outside:
Loop A: HV-F007A (BC-V128)
P212B NA 11 Loop B: HV-F007B (BC-V031)
P212A NA 11 Loop C: HV-F007C (BC-V131)
P212B NA 11 Loop D: HV-F007D (BC-V034)
P212A NA 11 i
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HOPE CREEK 3/4 6-31 AMENDMENT NO. 93
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TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION PENETRATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds)
NOTE (S)
- 6. Group 27 - Standby Liquid Control M-48-l' Outside:
HV-F006A (BH-V028)
P18 NA 3
-HV-F006B (BH-V054)
P18 NA 3
- 7. Group 28 - Containment Atmosphere Control System Suppression Chamber Vacuum Relief M-57-1 Outside:
HV-5031 (GS-V038)
P220 NA 3
HV-5029 (GS-V080)
P219 NA 3
- 8. Group 69 - TIP Syr, tem Explosive Shear Valves M-59-1 Outside:
SE-XV-J0v4B1 (SE-V021)
P34A NA 7
SE-XV-2004B2 (SE-V022)
P34B NA 7
SE-XV-J004B3 (SE-V023)
P34C NA 7
SE-XV-J004B4 (SE-V024)
P34D NA 7
SE-XV-J004B5 (SE-V025)
P34E NA 7
HOPE CREEK 3/4 6-32 AMENDMENT NO.93
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION PENETRATION TIME VALVE FUNCTION AND NUMBER NUMBER (Seconds) NOTE (S)
P&ID 1
(d) RHR Suppression Pool Return Valves M-51-1 Outside:
HV-F011A (BC-V126)
P212B NA 11 HV-F011B (BC-V026)
P212A NA 11 10.
Group 40 - Core Spray System
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Thermal Relief Valves M-52-1.
I Outside:
Loop A&C:
BE-PSV-F012A P217B NA 5
Loop B&D:
BE-PSV-F012B P217A NA 5
.I 11.
Group 41 - Drywell Pressure Instrumentation M-42-1
{
Outside:
BB-V563 J6A NA 6
BB-V564 J8D NA 6
BB-V565 J7A NA 6
BB-V566 J10D NA 6
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HOPE CREEK 3/4 6-36 AMENDMENT NO: 93 i
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