ML20087D898
| ML20087D898 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/07/1995 |
| 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 | |
| ML20087D902 | List: |
| References | |
| DPR-70-A-173, DPR-75-A-154 NUDOCS 9508110209 | |
| Download: ML20087D898 (17) | |
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- UNITED STATES '
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NUCLEAR REGULATORY COMMISSION
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wassiNoTon, o.c. 2osswooi PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT'NO. l' AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.173 License No. DPR-70 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, Philadelphia Electric Company, Delmarva Power and Light Company.and Atlantic _ City Electric Company (the licensees) dated
-February 5,1993, supplemented April 13, June 11 and November 17, 1993, 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; a
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.
Tae issuance of this amendment will not be inimical t5 the common defense and security or to the health and safety of the public; and '
E.
The issuance of this amendmer.t 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 hereby amended to read as follows:
9508110209 950807 PDR ADOCK 05000272 P
PDR u
Se,
. (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.173, are hereby incorporated in the license. The licensee shall operate the facility in accordance with l
the Technical Specifications.
t 3.
This license amendment is effective as of its date of issuance, to be implemented by the startup following the twelfth refueling outage.
FOR THE NUCLEAR REGULATORY COM ISSION J
F.Stolz,Directp ject Directorate Division of Reactor rojects - I/IL i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 7, 1995 I
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ATTACHMENT TO LICENSE AMENDMENT NO.173 FACILITY OPERATING' LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes 6 2-6 B 2-6 B 2-6 8 2-7 B 2-7 3/4 3-3 3/4 3-3 3/4 3-10 3/4 3 3/4 3-12 3/4 3-12 I
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a TABLE 2.2-1 (Continued)'
REACTOR TRIP SYSTEM INSTRINGENTATION TRIP SETPOINTS
_ FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 13.
Steam Generator Water a 9.0% of narrow range instrument a 8.0% of narrow range instrument Level--Low-Low span-each steam generator span-each steam generator 14.
Deleted 15.
Undervoltage-Reactor a 2900 volts-each bus a 2850 volts-each bus Coolant Pumps 16.
Underfrequency-Reactor a 56.5 Hz - each bus a 56.4 Hz - each bus Coolant, Pumps 17.
Turbine Trip A.
Low Trip System a 45 psig a 45 psig Pressure B. Turbine Stop Valve s 15% off full open s 15% off full open Closure 18.
Safety Injection Input Not Applicable Not Applicable from SSPS 19.
Reactor Coolant Pump Not Applicable Not Applicable.
Breaker Position Trip I
i e
SALEM - UNIT 1 2-6
' Amendment No.173
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~ LIMITING SAFETY SYSTEM'LETTINGS' B&EX&
through the pressurizer safety valves. No credit was taken for operation of this. trip in the accident analysesi however, its functional capability'at the specified trip setting is required by.this specification to enhance the overall reliability of the Reactor Protection' System.
Loss of Flow-The Loss of Flow trips provide core protection to prevent DNB in the event of a loss of one or more reactor coolant pumps.
Above 11 percent of RATED THERMAL POWER, an automatic reactor trip will occur if the flow in any two loops drop below 90% of nominal full loop flow.
Above 36% (P-8) of RATED THERMAL POWER, automatic reactor trip will occur if the flow in any single loop drops below 90% of nominal full loop flow. This latter trip will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients when 3 loops are in operation and the overtemperature AT trip set point is adjusted to the value specified for all loops in operation. With the overtemperature AT trip set point adjusted to the value specified for 3 loop 4
operation, the P-8 trip at 76% RATED THERMAL POWER will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients with 3 loops in operation.
31 gam Generator Water Level The Steam Generator Water. Level Low-Low trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity. The.specified setpoint provides allowance that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary-feedwater system.
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SALEM - UNIT 1 B 2-6 Amendment No.173
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LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltace and Underfrecuency - Reactor Coolant puma Busses The Undervoltage and Underfrequency Reactor Coolant Pump bus trips provide reactor core protection against DNB as a result of loss of voltage or underfrequency to more than one reactor coolant pump. The specified set points assure a reactor trip signal is generated before the low flow trip set point is reached. Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients. For undervoltage, the delay is set so that the time required for a signal to reach the reactor trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall not exceed 0.9 seconds. For underfrequency, the delay is set so that the time required for a signal to reach the reactor trip breakers after the underfrequency trip setpoint is reached shall not exceed 0.3 seconds.
l Turbine Trio A Turbine Trip causes a direct reactor trip when operating above P-9.
Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient. No credit was taken in the accident analyses for operation of these trips. Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.
I 1
SALEM - UNIT 1 B 2-7 Amendment No.173 I
, ' ::q TABLE 3 3-1 (Continued) u
-REACTOR TRIP SYSTEM INSTRUMENTATION MINIMLM TOTAL NLMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS W TRIP OPERABLE MODES ACTION 11.
Pressurizer Nater Letel--High 3
2 2
1, 2'
6#
12.
Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1
6#
(Above P-8) any oper-each oper-ating loop ating loop 13.
Loss of Flow - Two I. cops 3/ loop 2/ loop in 2/ loop in 1-6#
(Above P-7 and below P 8) two oper-each oper-ating loops ating loop l
14.
Steam Generator Nater Level--
3/ loop 2/ loop in 2/ loop in 1,
2
~ 6#
Low-Low any oper- '
each oper-ating loops ating loop 15.
Deleted I
16 Undervoltage-Reactor Coolant' Pumps 4-1/ bus 1/2 twice 3
1 68 17.
Underfrequency-Reactor Ccolant 4-1/ bus 1/2 twice 3
1 6#
Pumpa I
1 l
SALEM - UNIT.1 3/413-3 asmanAmant No.173
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^3 TABLE 3.3-2 (Conti =ad)
=
REACTOR TRIP SYSTEM INSTRIDEENTATION RESPNCE TIMES FUNCTIONAL UNIT RESPONSE TIME 12.
Loss of Flow - Single Loop (Above P-8) s 1.0' seconds 13.
Loss of Flow - Two Loops (Above P-7 and below P-8) s 1.0 seconds.
y 14.
Steam Generator Nater Level-- Low-Low s 2.0 seconda
'i 15.
Deleted 16.
thdervoltage-Reactor Coolant Pumps s 1.2 seconds 17.
thderfr'equency-Reactor coolant Pumps s 0.6 seconds 18.
Turbine Trip A.
Low Fluid Oil Pressure NOT APPLICABLE i
B.
Turbine Stop Valve NOT APPLICABLE l
=l 19.
Safety Injection. Input from ESF NOT APPLICABLE 20.
Reactor Coolant Pump Breaker Position Trip NOT APPLInnu 21.
Reactor Trip Breakers NOT APPLICABLE l
22.
Automatic' Trip Logic NOT APPLICABLE l
SALEM - UNIT 1 3/4 3 **=t No.173
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'4 TABLE 4.3-1 (Continued)
REACTOR ' TRIP SYSTEM INSTRIDGENTATION SURVEILLANCE REOUIR_=irrS
~
CHANNEL MODES IN NHICH
~
CHANNEL FUNCTIONAL SURVEILIANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED 13.
Loss of Flow Two Loops
~S R
N.A.
1 14.
Steam Generator Nater Level--
S R
.Q 1,
2
~
Low-Low 15.
Deleted I
- 16. Undervoltage - Reactor Coolant N.A.
R Q
1 Pumps
- 17. Underfrequency - Reactor Coolant N.A.
R Q
1
~
Pumps
- 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(1) 1, 2
- 19. Safety Injection Input from ESF N.A.
N.A.
M(4) (5) 1, 2
- 20. Reactor Coolant Pump Breaker N.A.
N.A.
R' N.A.
Position Trip
- 21. Reactor Trip Breaker N.A.
N.A.
S/U(10),
1, 2 and
- M (11,13),
SA(12,13) and R(14)
- 22. Automatic Trip Logic N.A.
N.A.
M(5) 1, 2 and
- t SALEM - UNIT 1 3/4 3-12 Amendment No.173 u
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION E
f WASHINGTON. D.C. 20666-0001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY RELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTAIC COMPANY s
DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENS1 Amendment No.154 License No. DPR-75 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, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated February 5, 1993, supplemented April 13, June 11 and November 17, 1993, 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No OPR-75 is hereby amended to read as follows:
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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 154, 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 by the startup following the current outage.
FOR THE NUCLEAR REGULATORY COMISSION h
F. Stolz, Direct r ject Directorate 2
i vision of Reactor Projects - I/II' Office of Nuclear Reactor Regulation.
Attachment:
thanges to the Technical
'{
Specifications j
Date of :ssuance:
August 7, 1995
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ATTACHMENT TO LICENSE AMENDMENT NO. 154 i
EACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 2-6 2-6 B 2-6 B 2-6 3/4 3-3 3/4 3-3 3/4 3-10 3/4 3-10 3/4 3-12 3/4 3-12 4
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a TABLE 2.2-1 iContinuedi REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.
FUNCTIONAL UNIT TRIP SETFOINT ALLOWABLE VALUES 13.
Steam Generator Water 2 9.0% of narrow range instrument 2 8.0% of narrow range instrument Level--Low-Low span-each steam generator span-each steam generator 14.
Deleted 15.
Undervoltage-Reactor 2 2900 volts-each' bus 2 2850 volte-each bus Coolant Pumps 16.
Underfrequency-Reactor 2 56.5 Hz - each bus-2 56.4 Hz - each bus Coolant Pumps 17.
Turbine Trip 2 45 psig A. Low Trip System 2 45 psig Pressure B. Turbine Stop Valve s 15% off full open 5 15% off full open C1caure 18.
Safety Injection Input Not Applicable Not Applicable from SSPS 19.
Reactor Coolant Pump Not Applicable Not Applicable Breaker Position Trip
' SALEM - UNIT 2 2-6.'
Amendment No.154 -
d LIMITING SAFETY SYSTEM SETTINGS BASES Loss of Flow The Loss of Flow trips provide core protection to prevent DNB in the event of a loss of one or more reactor coolant pumps.
Above 11 percent of RATED THERMAL POWER, an automatic reactor trip will occur if the flow in any two loops drop below 90% of nominal full loop flow. Above 36% (P-8) of RATED THERMAL POWER, automatic reactor trip will occur if the flow in any single loop drops below 90% of nominal full loop flow. This latter trip will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients when 3 loops are in operation and the Overtemperature delta T trip set point is adjusted to the value specified for all loops in operation. With the overtemperature delta T trip set point adjusted to the value specified for 3 loop operation, the P-8 trip at 76% RATED THERMAL POWER will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients with 3 loops in operation.
Steam Generator Water Level The Sceam Generator Water Level Low-Low trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity. The specified setpoint provides allowance that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary feedwater system.
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SALEM - UNIT 2 B 2-6 Amendment No.154
..g TABLE 3.3-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES' ACTION 11.
Pressurizer Water Level--High 3
2 2
1, 2 6#
12.
Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1
6#
(.".bu.c P-8 )
any oper-each oper-ating loop' ating loop l
13.
Loss of 7 low - Two Loops 3/ loop 2/ loop in-2/ loop in 1
6#
(Above P-7 and below P-8) two oper-each cper-ating loops ating loop 14.
Steam Generator Water Level--
3/ loop 2/ loop in 2/ loop in 1, 2 6#
Low-Low any oper-each oper-ating loops ating loop 15.
Deleted 16.
Undervoltage-Reactor Coolant Pumps 4-1/ bus 1/2 twice 3
1 6
17.
Underfrequency-Reactor Coolant Pumps 4-1/ bus 1/2 twice 3
1 6
SALEM - UNIT 2 3/4 3-3 Amendment No.154
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TABLE 3.3-2 (Continued) 1 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME 12.
Loss of Flow - Single Loop s 1.0 seconds (Above P-8) i 13.
Loss of Flow - Two Loops s 1.0 seconds (Above P-7 and below P-8) 1
[
14.
Steam Generator Water Level--
5 2.0 seconds Low-Low 15.
Deleted 16.
Undervoltage-Reactor Coolant Pumps s 1.2 seconds 17.
Underfrequency-Reactor Coolant Pumps s O.6 seconds 18.
Turbine Trip A.
Low Fluid Oil Pressure NOT APPLICABLE B.
Turbine Stop Valve NOT APPLICABLE 19.
Safety Injection Input from ESF NOT APPLICABLE 20.
Reactor Coolant Pump Breaker Position Trip NOT APPLICABLE-21.
Reactor Trip Breakers NOT APPLICABLE 22.
Automatic Trip Logic' NOT APPLICABLE SALEM - UNIT 2 3/4 3-10' Amendment No.154 e
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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.
1
- 14. Steam Generator Water Level--
S R
Q 1, 2 i
Low-Low
- 15. Deleted
- 16. Undervoltage - Reactor Coolant N.A.
R Q
1 Pumps
- 17. Underfrequency - Reactor Coolant N.A.
R Q
1 Pumps
- 18. Turbine Trip i
a.
Low Autostop Oil Pressure N.A.
N.A.
S/U(1)
N.A.
- b. Turbine Stop Valve Closure N.A.
N.A.
S/U(1)
N.A.
- 19. Safety Injection Input from ESF N.A.
N.A.
M(4)(5) 1, 2
- 20. Reactor Coolant Pump Breaker N.A.
N.A.
R N.A.
l Position Trip
- 21. Reactor Trip Breaker N.A.
N.A.
S/U(10),
1, 2 and
- M(11,13),
SA(12,13) and R(14)
- 22. Automatic Trip Logic N.A.
N.A.
N(5) 1, 2 and
- 1 SALEM - UNIT 2 3/4 3-12 Amendment No.154 i
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