ML20203B487
| ML20203B487 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/29/1998 |
| 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 | |
| ML20203B492 | List: |
| References | |
| DPR-70-A-205, DPR-75-A-187 NUDOCS 9802240300 | |
| Download: ML20203B487 (10) | |
Text
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UNITED STATES
.I NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2000M001 k
- a PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPAg1 DELMARVA POWER AND LIGHT CMPANY ATLANTIC CITY-ELECTRIC COMPANY DOCKET N0. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. I t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.205 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Cosmiission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Elech ic Company, Delmarva Power and Light Company and Atlantic City Elect ic Company (the licensees) dated October 21, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the u.'), ar.d the Commission's rules and regulations set forth in 10 CFR Ch ~ter I; B.
The facility will operate in conformity with the applicuion, the -
provisions of the Act, and the rules and regulations of the Commission; 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 s
in compliance with the Commission's regulations set forth in 10 CFR C> apter I; D.
7he issuance of this amendment will not be inimical to the common oefense 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. DPR-70 is hereby amended tu read as follows:
e 9002240300 900129 DR ADOCK 0500 2 2
. (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment NoE05
, are hereby incorporated in the license. The licensee shall operata the facility in accoruance with I
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 COMISSION i
J n F. Stolz, Direct r o ect Directorate
-2 ision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 29, 1998
ATTACMENT TO LICENSE AMENDMENT NO. 205 fACJLITY OPERATING LICENSE N0. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Ramave Paaes Insert Paoes 3/4 3-2 3/4 3-2 3/4 3-11 3/4 3-11
1 TABLE 3.3-1
' REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NUMBER CHANNELS' CHANNEI.S.
APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES-ACTION 1.
1 2
1,2 and.*
12.
I 2.
Power Range, Neutron Flux-4 2
3 1,2,"and 3*
2 3.
Power Range, Neutron Flux 4
2 3
1,2 2
High Positiire Rate 4.
Power Range, Neutron Flux 4
2
' 3' 1,2
.2 High Negative Rate 5.
Intermediate Range, Neutron Flux 2
1 2
1,2.and *
.3 6.
Source Range, Neutron Flux A.
Startup 2
1 2
255'and
- 4'.
B.
Shutdown 2
0
'I 3,4, and 5
~ 5 7.
Overtrinperature AT 4
2 3
'1,2 6
8.
Overpower AT 4
2 3
1,2 6.-
9.
Pressurizer Pressure-Low
.4 2-3 1,2 6:
10.
Pressurizer Pressure--High 4
2 3
1,2 6-SALEM - UNIT 1 3/4 3-2 Amen & tent No. TM,205-
y TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SU-tVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1.
Manual Reactor Trip Switch N.A.
N.A.
R "'
1, 2, and '
2.
Power Range, Heutron Flux S
D, M'"
Q 1, 2, and 3*
and Q
3.
Power Range, Neutron Flux, N.A.
R '
Q 1,
2 High Positite Rate 4.
Power Range, Neutron Flux, N.A.
R
O 1, 2 High Nega'_ive Rate 5.
Intermediate Range, Neutron Flux S
R '
S/U'"
1, 2 and
- 6.
Source Range, Neutron Flux S '
R
Q and S/U
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
1, 2 11.
Pressurizer Water Level--liigh S
R Q
1, 2 12.
Loss of Flow - Single Loop S
R Q
1
- A
- F M UNIT I 3/4 3-11 Amendment No.776, 205
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p UNITED STATES L
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NUCLEAR REGULATORY COMMISSION I
?
WASHINGTON, D.C. 30e06 4001
-\\.....
i PUBLIC SERVICE ELECTRIC & GAS CohPANY PHILADELPHIA ELECTRIC COMPANY-DELMARVA POWER A L _IGHT COMPANY
-ATLANTIC CITY ELECTRIC COMPANY
. DOCKET NO. 50-311 SALEM NUCLD.R GENERATING STATION. UNIT No. 2-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.187 License No. DPR-75
- 1. -The Nuclear' Regulatory Cosmiission (the Commission or the NRC).has found that:-
A.
The application for amendment filed by the Public Service Electric L I
Gas-Company, Philadelphia Electric Company, Delmarva Power and Light
. Company and Atlantic City Electric Company (the licensees) dated October 21, 1997, 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: (1) that the activities authorized by
.this amendment can be conducted without endangering the health and safety of the public, and (ii) that cuch 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 Techr,1 cal 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 amended to read as follows:
J
. (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Ap>endices A and B as l
revised through Amendment No.187, are heresy incorporated in the license. The licensee shall operate the facility in eccordance 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 Co MISSION
-J n T. Stolz, Directo Po et Directorate I-D sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Spr,1fications Date of Issuance: January 29, 1998 e
ATTACMFNT TO LICENSE AMENDMENT NO.1R7 FACILITY OPERATINC LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 3-2 3/4 3-2 3/4 3-11 3/4 3-11
l TABLE 3.3 REACTOR TRIP SYSTEM INSTRUMENTATION
.j-MINIMUM
- TOTAL NUMBER CHANNELS CHANNELS APPLICAB'E FUNCTIONAL UNIT OF CHANNELS TO TRIP.
MODES ACTION-1.
Mar ual Reactor Trip 2
1
'7 1,2 and *-'
12
~
2.
Power Range, Neutron Flux 4
2 1,2 and 3*
2 3.
Power Range, Neutron Flux 4
1 3
1, 2 -
2 High P3sitive Rate 4.
Power Range, Neutron Flux, 4
2 3
1, 2 -
2-High Negative Rate 5.
Intermediate Range, Neutron Flux 2
1 2
1,2 and
- 3 6.
Source Range, Neutron Flux
'4 A.
Startup 2
1 2
258, and'*
B.
Shutdown 2
0 1
3,4 and 5-5-
7.
Overtemperature AT 4
'2 3
1, 2 '
6 8.
Overpower AT 4
2 3
1, 2 6
9.
Pressurizer Pressure-Low 4
2 3
1,2 6
10.
Pressurizer Pressure--High 4
2 3.-
1,2 6
Amendment No.Ilj,187
- ist.ty -
f 111T 2 3/4 3-2
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREND(TS CHANNEL MODES IN WHICH CHANNEL FTJNCTIONAL SURVEILLANCE FUNCTIONAL UNIT
._ CHECK CALIBRATIOd TEST REQUIRED 1.
Manual Reactor Trip Switch N.A.
N.A.
R*
1, 2,
and
- 2.
Power Range, Neutron Flux 5
D'", M'"
Q 1, 2, and 3*
and Q
3.
Power Range, Neutron Flux, N.A.
R*
O 1,
2 liigh Positive Rate 4.
Power Range, Neutron Flux, N.A.
R "'
O 1,
2 liigh Negative Rate S.
Intermediate Range, Neut ron Flux S
R "'
S/U'"
1, 2 and
- 6.
Source Range, Neutron Fl ux S'"
R*
Q and S/U'"
2, 3,
4, 5 and
- 7.
Overtemperature AT S
R Q
1, 2 6.
Overpower AT S
R Q
1, 2 9.
Pressurizer Pressure--Low S
R Q
1, 2
10.
Pressurizer Pressure--ifigh S
R Q
1, 2
11.
Pressurizer Water Level--liigh S
R Q
1, 2
12.
Loss of Flow - Single Locp S
R Q
l l
2 3/4 3-11 Amendment No.}37,187
_ _ -