ML17146A959
| ML17146A959 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/14/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A960 | List: |
| References | |
| NUDOCS 8709180452 | |
| Download: ML17146A959 (22) | |
Text
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~ 0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER II LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
OOCKET NO. 50-387 SlISQUEHANNA STEAM ELECTRIC STATION, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
70 License No.
NPF-14 1.
The Nuclear RegulatorV Commission
{the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8
Light Company, dated April 13, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended
{the Act),
and the Commission's 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 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 wi 11 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 Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
70 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8709i80452 870914 J
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Attachment:
Changes to the Technical Specifications Date of Issuance:
september l41 1987 Walter R. Butler, Director Project Directorate I-2, Division of Reactor Projects I/II P
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DI-2/PM MThadani:ca OGC PDI-2/D WButler q/z /87 f/$/87 a/
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
septeaher 14 1987 Walter R. Butler, Director Proiect Directorate I-2 Division of Reactor Projects I/II
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~ 0 ATTACHMENT TO LICENSE AMENDMENT NO.
70 FACILITY OPERATING LICENSE NO.
NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified hy Amendment number and contain vertical lines indicating the area of change.
The overleaf pages are provided to maintain document completeness.*
REMOVE 3/4 3-23 3/4 3-24*
3/4 3-25%
3/4 3-26 INSERT 3/4 3-23 3/4 3-24*
3/4 3-25~
3/4 3-26
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TABLE 4. 3. 2. 1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED a.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
b.
Drywell Pressure
- High NA c.
Manual Initiation NA d.
SGTS Exhaust Radiation - High S
e.
Main Steam Line Radiation - High S
2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-Low Low, Level 2
b.
Drywell Pressure
- High c.
Refuel Floor High Exhaust Duct Radiation - High d.
Railroad Access Shaft Exhaust Duct Radiation - High e.
Refuel Floor Wall Exhaust Duct Radiation - High f.
Manual Initiati on NA R
R NA 1, 2, 3
1 2
3 1, 2, 3
1, 2, 3
1, 2, 3
3
/*A* 5*%*
1 2
3 1, 2, 3 and "
1,2,3 1,2,3and*
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 3.
MAIN STEAM LINE ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO a ~
b.
C.
d.
e.
NA S
NA f
Reactor Vessel Water Level-I.ow, Low Low, Level 1
S Main Steam Line Radiation - High S
Main Steam Line Pressure - Low Main Steam Line Flow - High Condenser Vacuum - Low Reactor Building Main Steam Line
- Tunnel Temperature - High NA Reactor Building Main Steam Line Tunnel I Temperature - High NA Manual Initiation NA Turbine Building Main Steam Line NA Tunnel Temperature - Hjgh Q
NA Q
1, 2, 3
1, 2, 3
1,2,3 2**
3*%
1,2,3 1,2,3 1, 2, 3
1, 2, 3
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
C.
d.
e.
g.
RWCU h Flow - High RWCU Area Temperature - High RWCU Area Ventilation h Temperature - High SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2
RWCU Flow - High manual Initiation S
NA NA NA S
S NA Q
NA R
R NA 1,2,3 1-, 2, 3
1,2,3 1, 2, 3
1,2,3 1)2,3 1,2,3
TABLE 4. 3. 2. 1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION CHANNEL CHECK CHANNEL FUNCTIONAL CHANNEL TEST CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION b.
C.
d.
h.
RCIC Steam Line 6 Pressure
- High RCIC Steam Supply Pressure-Low RCIC Turbine Exhaust Diaphragm Pressure
- High RCIC Equipment Room Temperature - High RCIC Equipment Room 6 Temperature - High RCIC Pipe Routing Area Temperature - High RCIC Pipe Routing Area h Temperature - High RCIC Emergency Area Cooler Temperature
- High Manual Initiation Drywell Pressure
- High NA NA NA NA R
1,2,3 1,2,3 1, 2, 3
1, 2, 3
1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1, 2, 3
6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION HPCI Steam Line h Pressure
- High HPCI Steam Supply Pressure Low HPCI Turbine Exhaust Diaphragm Pressure
- High NA NA 1
2 3
1, 2, 3
1, 2, 3
r z
TABLE 4.3.2. 1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION CHANNEL CHANNEL FUNCTIONAL CHECK TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued) 7.
d.
HPCI Equipment Room Temperature
- High NA M
e.
HPCI Equipment Room 6 Temperature - High NA M
f.
HPCI Emergency Area
- Cooler Temperature - High NA M
g.
HPCI Pipe Routing Area Temperature
- High NA M
h.
tlPCI Pipe Routing Area 5 Temperature - High NA M
i.
Manual Initiation NA R
j.
Drywell Pressure
- High NA M
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION Q
NA R
1, 2, 3
1 2
3 1; 2, 3
1 2
3 1
2 3
1, 2, 3
1, 2, 3
a.
b.
C.
d.
e.
g.
When with
- When
- "" When Q
R NA R
Reactor Vessel Water Level-L'ow, Level 3
S M
R t
Reactor Vessel (RHR Cut-in Permissive)
Pressure High NA M
PHR Equipment Area h Temperature - High NA M
Q RHR Equipment Area Temperature-fligh NA M
RHR Flow High S
M Manual Initiation NA R
Prywell Pressure High NA M
t, handling irradiated fuel in the secondary containment and during CORE ALTERATIONS
- a potenti al for drai ning the reactor vessel.
'reactor steam dome pressure
> 1043 psig and/or any turbine stop valve is open.
.VENTING or PURGING the drywell per Specification 3.11.2.8.
1, 2, 3
1,2,3 1,2,3 1,2,3 1, 2, 3
1, 2, 3
1 2
3 and operations
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j"l 0O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 8
LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SIISQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
39 License No.
NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 5
Light Company, dated April 13, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will provisions of the
\\
C.
There is reasonabl by this amendment and safety of the conducted in compl in 10 CFR Chapter operate in conformity with the application, the Act, and the regulations of the Commission; e assurance:
(i) that the activities authorized can be conducted without endangering the health public, and (ii) that such activities will be iance with the Commission's regulations set forth I;
2.
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.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
39 and the Environmental 'Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPEL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
~ ~
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Attachment:
Changes to the Technical Specifications Date of Issuance:
september 141 1987 Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
) /~/87 DI-2/PM MThadani:ca g/g/87 0
$/
87 PDI-2/D WButler g /]qf87
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Septeaher l4, l987 Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
I P
\\
7 v'O OO
~ 1 0 ~
ATTACHMENT TO LICENSE AMENDMENT NO.
39 FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The overleaf pages are provided to maintain document completeness.*
REMOVE 3/4 3-23 3/4 3-24*
3/4 3-25*
3/4 3-26 INSERT 3/4 3-23 3/4 3-24*
3/4 3-25*
3/4 3-26
~ ~
0 ~
~
TABLE 4. 3. 2. 1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-CHANNEL CHECK CHANNEL FUNCTIONAL TEST OPERATIONAL CHANNEL CONDITIONS FOR WHICH CALIBRATION SURVEILLANCE RE UIRED 2.
b.
C.
1)
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
Drywell Pressure High Manual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation-High SECONDARY CONTAINMENT ISOLATION S
S S
NA NA R
R R
R NA R
1 2
1, 2, 1, 2, 1, 2, 1, 2, 1, 2,
- l. 2.
3 3
3 4*** 5***
f a.
b.
C.
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure
- High Refuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High Manual Initiation S
NA S
NA M
R R
NA 1,2,3and*
1 2
3 1, 2, 3 and "
O
TABLE 4.3.2. 1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 3.
MAIN STEAM LINE ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL'ALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIREO a.
b.
C.
d.
e.f.
g.
h.l.
Reactor Vessel Water Level-Low Low Low, Level 1
S Main Steam Line Radiation-High S
Main Steam Line Pressur e-Low Main Steam Line Flow - High Condenser Vacuum.-
Low Reactor Building Main Steam Line Tunnel Temperature
- High Reactor Building Main Steam Line Tunnel d Temperature-High Manual Initiation Turbine Building Main Steam Line Tunnel Temperature - High NA Q
NA 1, 2, 3
1, 2, 3
11,2,3 2** 3**
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
b.
C.
d.
e.
f.
g.
S S
NA RWCU d Flow " High S
RWCU Area Temperature
- High NA RWCU Area Ventilation d Temperature - High SLCS Initiation Reactor Vessel Water Level-Low Low, Level 2:
RWCU Flow - High, Manual Initiation Q
NA R
R NA I, 2, 3
1, 2, 3
1, 2, 3 1, 2, 3
1, 2, 3
1, 2, 3-1, 2, 3
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL FUNCTIONAL TRIP FUNCTION CHECK TEST 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO b.
RCIC Steam Line 6, Pressure
- High.
RCIC Steam Supply Pressure-Low 1, 2, 3
1, 2, 3
C.
e.
g.
h.
RCIC Turbine Exhaust Diaphragm Pressure
- High RCIC Equipment Room Temperature - High RCIC Equipment Room b, Temperature - High RCIC Pipe Routing Area Temperature - High RCIC Pipe Routing Area 6 Temperature High RCIC Emergency Area Cooler Temperature - High Manual Initiation NA NA NA NA j.
Drywell Pressure - High NA 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION Q
NA R
1, 2, 3
1 2
3
- 1) 2, 3
1, 2, 3
1 2
3 1
2 3
1.2 3
1, 2, 3
a.
b.
C.
HPCI Steam Line 6 Pressure
- High HPCI Steam Supply Pressure
- Low HPCI Turbine Exhaust Diaphragm Pressure High NA NA 1
2 3
1, 2, 3
1,2,3
TABLE 4.3.2. 1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION CHANNEL CHANNEL FUNCTIONAL CHANNEL CHECK TEST CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued) d.'.
g.
h.
HPCI Equipment Room Temperature - High HPCI Equipment Room 6 Temperature - High HPCI Emergency Area Cooler Temperature - High HPCI Pipe Routing Area Temperature - High HPCI Pipe Routing Area d Temperature - High Manual Initiation Drywell Pressure
- High NA NA NA NA NA NA 1, 2, 3
1.2 3
1 2
3 1,2,3 1, 2, 3
1 2
3 1, 2, 3
7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION a.
b.
C.
d'.
en with
- "When
"~*When Reactor Vessel Water Level-Low, Level 3
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High RHR Equipment Area d Temperature - High RHR Equipment Area Temperature
- High RHR Flow - High Manual Initiation Drywell Pressure
- High Q
NA R
NA S
NA NA M
and ing irradiated fuel in the secondary containment and during CORE ALTERATIONS a potential for draining the reactor vessel.
reactor steam dome pressure' 1043 psig and/or any turbine stop valve is open.
VENTING or PURGING the drywell per Specification
- 3. 11.2.8.
1 2
3 1,2,3 1
2 3
1 2
3 1
2 3
1, 2, 3
1, 2, 3
and operations