ML20092J153
| ML20092J153 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/18/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20092J155 | List: |
| References | |
| DPR-70-A-176, DPR-75-A-157 NUDOCS 9509210356 | |
| Download: ML20092J153 (13) | |
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- t UNITED STATES j
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 i
SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated September 20, 1994, 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 Commission; C.
There is reasonable assurance: (i) that the activities authorized by j
l 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 i
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 Facility Operating License No. DPR-70 is hereby 4
I amended to read as follows:
9509210356 950918 PDR ADOCK 05000272 P
i
. (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.176, are hereby incorporated in the license. The licensee shall operate the facility in accordance with l
the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
- h oh
'F.
Stolz, Dir ctor x ject Directora I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1995 4
i I
a i
t ATTACHMENT TO LICENSE AMENDMENT NO.176 FACILITY OPERATING LICENSE NO. DPR-70 l
l DOCKET NO. 50-272 i
Revise Appendix A as follows:
1 Remove Paaes Insert Paaes
~
3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 I
I 4
5 1
4 4
2 1
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TABLE 4.3-1
'REACTDR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUTDRMENTS CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED 1.
Manual Reactor Trip Switch N.A.
N.A.
R 1,
2, and *
~l M
2.
Power Range,' Neutron Flux S
DS, MS Q
1, 2
and Q*
i 3.
Power Range, Neutron Flux, N.A.
R*
Q 1,
2 High Positive Rate 4.
Power Range, Neutron Flux, N.A.
R*
Q 1,
2 High Negative Rate 5.
Intermediate Range, Neutron Flux S
R*
S/tfD 1,
2 and
- 6.
Source Range, Neutron Flux SM R*
Q and S/tf" 2,
3, 4,
5 and
- 7.
Overtemperature AT S
R Q
1, 2
8.
Overpower AT S
R Q
1, 2
9.
Pressurizer Pressure--Low S
R Q
1, 2
10.
Pressurizer Plessure--High S
R Q
1, 2 11.
Pressurizer Water Level--High S
R Q
1, 2
12.
Loss of Flow - Single Loop S
R Q
1 SALEM - UNIT 1 3/4 3-11 Amendment No.I76
-l
TABLE 4.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 13.
Loss of Flow Two Loops S
R N.A.
I 14.
Steam Generator Nater Level--Low-Low S
n Q
1,. 2
- 15. Deleted 16.
Undervoltage - Reactor Coolant Pumps N.A.
R Q
1 17.
Underfrequency'- Reactor Coolant Pumps N.A.
R Q
1 18.
Turbine Trip a.
Low Autostop Oil Pressure N.A.
- N.A.
S/U(1).
1, 2
- b. Turbine Stop Valve Closure N.A.
N.A.
S/U(II 1,. 2
'S f ta e y Injection Input from ESF N.A.
N.A.
M(4)(5) 1, 2
19.
20.
Reactor Coolant Pump Breaker N.A.
N.A.
R N.A.
Position Trip 21.
Reactor Trip Breaker N.A.
N. 'A.
M(5)(11)(13) 1, 2 and
- and R(l'I 22.
Automatic Trip Logic N.A.
N.A.
M(5) 1, 2 and
- SALEM - UNIT 1 3/4 3-12 Amendment No.176 l.
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4 TABLE 4.3-1 (Continued)
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
If not performed in previous 31 days.
(1)
(2)
Heat balance only, above 15% of RATED THERMAL POWER.
(3)
Compare incore to excore axial offset above 15% of RATED THERMAL POWER.
Recalibrate if absolute difference a 3 percent.
(4)
Manual SSPS functional input check every 18 months.
(5)
Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6) -
Neutron decectors may be excluded from ChNNEL CALIBRATION.
Below P-6 (Block of Source Range Reactor Trip) setpoint.
(7)
(8)
Deleted
~
(9)
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip mechanism for the Manual Reactor Trip Function.
The Test shall also verify OPERABILITY of the Bypass Breaker Trip circuits.
(10) -
DELETED i
(11) -
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip mechanisms.
(12)
DELETED f
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l SALEM - UNIT 1 3/4 3 13 Amendment 'No; 176 l*
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4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001 1
j '
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY
]
ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-311 1
j SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.157 License No. DPR-75 i
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
i Gas Company, Philadelphia Electric Company, Delmarva Power and Light i
Company and Atlantic City Electric Company (the licensees) dated September 20, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the l
Commission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and'the rules and regulations of the Commission; l
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 l
defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Consiission'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 Facility Operating License No. DPR-75 is hereby i
amended to read as follows:
4
~
1 l
'(2) Technical snecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 157, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION f
/
4 3
o
. Sto z, Cir ctor i
ject Diree'.or I-2 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical
]
Specifications Date of Issuance: September 18, 1995 i
i i
1 i
i 1
t'
)
i 4
I
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~
ATTACHMENT TO LICENSE AMENDMENT NO.157 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages Insert Paaes 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-13a 3/4 3-13a l
4 l
i a
4 a
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s TABLE 4 3-1 REACTOR TRIP SYSTEM INSTRIMENTATION SURVEILLANCE REOUIR_N.
CHANNEL MODES IN WHICH' CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL IJNIT CHECK CALIBRATION TEST REQUIRED
-1..
Manual Reactor Trip Switch N.A.
N.A.
RM 1,
2, and
- l 2.
Power Range, Neutron Flux S
D*4 M*
Q 1,-2 and Q*
3.
Power. Range, Neutron Flux, N.A.
R*
Q 1, 2.
High Positive Rate 4.
Power Range, Neutron Flux, N.A.
R*
Q 1,
2 High Negative Rate 5.
Intermediate Range, Neutron Flux S
R*
S/If'8 1,
2 and
- 6.
Source Range, Neutron Flux Sm R*
Q and S/If8) 2, 3,
4, 5 and
- 7.
Overtemperature AT S
R Q
1, 2
8.
Overpower AT S
R Q
1, 2
9.
Pressurizer Pressure--Low S
R Q
1, 2
10.
Pressurizer Pressure--High S
R Q-12 11.
Pressurizer Water Level--High S
R Q
1,. 2 12.
Loss of Flow - Single Loop S
R Q
1 SALEM - UNIT 2 3/4 3-11 Amendment No.157 l
. ~. _
~. -
~
TABLE 4.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL.
MODES'IN NHICH-CHANNEL FUNCTIONAL SURVEILLANCE.
' FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED
-13.
Loss of Flow Two Loops S
R N.A.
1 14.
Steam Generator Nater Level--Low-Low S
R Q
1,'2 15.
Deleted
~16.
Undervoltage - Reactor Coolant Pumps N.A.
R Q
1 17.
Underfrequency - Reactor Coolant Pumps N.A.
R Q
1 18.
Turbine Trip a.
Low Autostop Oil Pressure N.A.
N.A.
S/if" N.A.
- b. Turbine Stop Valve Closure N.A.
N.A.
. S/if" '
N.A.
19.
Safety Injection Input from ESF N.A.
N.A.
M'*""
1, 2
20.
Reactor Coolant Pump Breaker N.A.
N.A.
R N.A.
Position Trip i
. M """"#
1, 2 and *'
O 21.
Reactor Trip Breaker N.A.
N.A.
and R"'~
32.
Automatic Trip Logic N.A.
N.A.
M'8 1,
2 and
- SALEM - UNIT 2 3/4 3-12 Amendment No.157 l
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Ti
+- '
i L
I
. TABLE 4,3-1 (Continued)
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
(1)' -
If not performed in previou's 31 days.
(2)
Heat balance'only, above 15% of RATED THERMAL POWER.
(3)
Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference a 3 percent.
Manual SSPS functional input check every 18 months.
(4)
Each train or logic channel shall be tested at least every 62 days on (5) a STAGGERED TEST BASIS.
(6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
Below P-6 (Block of Source Range Reactor Trip) setpoint.
(7)
Deleted (8)
(9) -
The CHANNEL FUNCTIONAL TEST shall independently verify the l
OPERABILITY of the Undervoltage and Shunt Trip mechanism for the i
Manual Reactor Trip Function.
The Test shall also verify OPERABILITY of the Bypass Breaker Trip i
circuits.
(10) -
DELETED (11)
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip l
mechanisms.
(12) -
DELETED 5
t 4-SALEM - UNIT 2 3/4 3-13 Amendment No.157 l
t
E 6
l TABLE 4.3-1 (Continued)
NOTATION I
(13 ) -
Verify operation of Bypass Breakers Shunt Trip function from local pushbutton while breaker is in the test position prior to placing breaker in service.
}
Perform a functional test of the Bypass Breakers U.V. Attachment via i
(14) the SSPS.
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l SALEM - UNIT 2 3/4 3 13a Amendment No.157 l