ML20058F736
| ML20058F736 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/16/1993 |
| From: | Larry Nicholson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058F740 | List: |
| References | |
| NUDOCS 9312080265 | |
| Download: ML20058F736 (12) | |
Text
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f (Dj k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION gv,/
wassincTON, D.C. 2055MD01 i
k PUBLIC SERVICE ELECTRIC & GAS COMPANY i
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO, 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
l A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelpnia Electric Company, Delmarva Power and Light Company and Atlantic City Ele:tric Company (the licensees) dated July 19,1993, and supplemented by letter dated August 5, 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 Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and 1
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR j
Chapter I; 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 Comission'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 to read as follows:
9312080265 931116 DR ADDCK 050002 2
i (2) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.147, 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 and shall be implemented within 60 days of the date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION p'
~ 4 r
Lar E. Nicholson, Acting Director Project Directorate'I-2 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance: November 16, 1993 a
i s
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'l i
h ATTACHMENT TO LICENSE AMENDMENT NO.147 i
FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 t
i Revise Appendix A as follows:
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Remove Paaes Insert Paoes l
3/4 3-54 3/4 3-54 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 2
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TABLE 3.3-11 l
ACCIDENT MONITORING INSTRUMENTATION REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT CHANNELS E N.NELS ACTION 1.
Reactor Cootent Outlet Temperature -
2 1
1, 2
7 (Wide Range) 2.
Reactor Cootent Intet Temperature -
2 1
1, 2
T COLD 3.
Reactor Coolant Pressure (Wide Range) 2 1
1, 2
4.
Pressurizer Water Levet 2
1 1,
2 5.
Steam Line Pressure 2/ Steam Generator 1/ Steam Generator 1,
2 6.
Steen Generator Water Levet (Norrow 2/ Steam Generator 1/ Steam Generator 1,
2 Range) 7.
Steam Generator Water Level (Wide 4 (1/ Steam Generator) 3 (t/ Steam Generator) 1, 2
Range) 8.
Refueting Water Storage Tonk Water 2
1 1,
2 Level 9.
deleted
- 10. Auxillery Feedwater Flow Rate 4 (1/ Steam Generator) 3 (1/ Steam Generator) 4, 6
- 11. Reactor Coolant System subcooling 2
1 1,
2 Marsin Monttor
- 12. PORY Position Indicator 2/ valve **
1 1,
2 SALEM - UNIT 1 3/4 3-54 Amendment No.147
b r
TABLE 3.3-11 feontinuedi i
i TattE NOTAT10N l
ACTION 1 With the number of CPERABLE accident monitoring channets less than the Required Number of Channels shown in Table 3.3-11, restore the Inoperable channet(s) to CPERABLE status within 7 days, or be in NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 2 With the number of OPERABLE accident monitoring channels less than the MINIMUM Number of Channels
{
shown in Tabte 3.3-11, restore the Inoperehte channet(s) to CPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in NOT $NUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 ceteted i
l ACTION &
With the number of OPERABLE channets one less than the Required Number of Channels shown in Table 3.3.11, operation may proceed provided that an OPERABLE Steam Generator Wide Range Level-channet l
1s avaltable as an alternate means of indication for the Steam Generator with no OPERATABLE Auxiliary Feedwater Flow Rate channet.
I ACTION 5 With the number of OPERABLE channets less than the I
Required Number of Channels show in Table 3.3-11, operation may proceed provided that steam Tables are available in the Control Room and the following Required Channets shown in Table 3.3-11 are OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:
I f
l a.
Reactor Coolant Outlet Temperature T
(Wide Range) j l
b.
Reactor Coolant Pressure (Wide Range) i i
l SALEM - UNIT 1 3/4 3-56 Amendment N o.147 i
TABLE 4.3-11 SURVEttLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CNANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECKS CALIBRATION TEST 1.
Reactor Coolant Outlet Temperature M
R NA T NOT (Wide Range) 2.
Reactor Coolant Intet Temperature M
R NA T COLD (Wide Range) 3.
Reactor Coolant Pressure (Wide Range)
M R
NA 4.
Pressurizer Water Level M
N NA 5.
Steam Line Pressure M
R NA 6.
Steen Generator Water Level M
R NA (Narrow Range) 7.
Steam Generator Water Levet M
R NA (Wide Range) 8.
Refueling Water Storage Tank Water Level M
R NA 9.
deleted
- 10. Auxillery Feedwater Flow Rate SU8 R
NA
- 11. Reactor Coolant System Subcooling M
N/A*
NA Margin Monitor gAuxillary Feedwater System is used on each startup and flow rate indication is verified at that time.
- The instruments used to develop RCS subcooling margin are calibrated on en 18 month cycle; the monitor will be compared quarterly with calcuteted subcooling margin for known input values.
i SALEM - UNIT 1 3/4 3-57 Amendment No.
107'
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( ) k UNITED STATES
($.c/
i NUCLEAR REGULATORY COMMISSION g wi wassiuctow. o.c. rosss-oooi PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY OELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendinent No.125 License No. DPR-75 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 July 19, 1993, and supplemented by letter dated August 5, 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 Comission; 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 in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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. DPR-75 is hereby amended to read as follows:
f (2) Technical Soecifications and Environmental Protection Plan 6
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.125, are hers by 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 and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Larry
. Nicholson, Acting Director Proje t Directorate 1-2 Division of Reactor Projects
.I/II-Office of Nuclear Reactor Regulation l
l
Attachment:
Changes to the Technical Specifications l
Date of Issuance: November 16, 1993 t
i i
i I
I I
I
l l
I
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\\
ATTACHMENT TO LICENSE AMENDMENT NO.125 l
l FACILITY OPERATING LICENSE NO. OPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
t Remove Paaes Insert Paaes 3/4 3-51 3/4 3-51 l
3/4 3-51b 3/4 3-51b l
3/4 3-52 3/4 3-52 l
l I
l 4
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TABLE 3.3-11 ACCIDENT MONITORING INSTRUMENTAfl0N REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT CHANNELS CHANNELL ACTION 1.
Reactor Cootent Outtet Temperature 2
1 1,
2 7
(Wide Range) 2.
Reactor Cootent Intet Temperature -
2 1
1, 2
T (Wide Range) 3.
Reactor Coolant Pressure (Wide Range) 2 1
1, 2
4.
Pressurizer Water Level 2
1 1,
2 5.
Steam Line Pressure 2/ Steam Generator 1/ Steam Generator 1,
2 6.
Steen Generator Water Level (Norrow 2/ Steam Generator 1/Steen Generator 1,
2 Range) 7.
Steam Generator Water Level (Wide 4/(1/ Steam Generator) 3 (1/ Steam Generator) 1, 2
Range) 8.
Refueling Water Storage Tank Water 2
1 1,
2 Level 9.
deleted
- 10. Auxitlery Feedwater Flow Rate 4 (1/Steen Generator) 3 (1/Steen Generator) 4, 6
- 11. Reactor Cootent System Subcooling 2
1 1,
2 Margin Monitor
- 12. PORY Poettion Indicator 2/ valve **
1 1,
2 UNIT 2 3/4 3-51 Amendment No.125 SALEM l
4 l
TABLE 3.3-11 fcentinued) i TABLE NOTATION _
ACTION 1 With the number of CPERABLE accident monitoring channets tess than the Required Number of Channels shown in Table 3.3-11, restore l
the Inoperable channel (s) to OPERABLE status within 7 days, or be in NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
[
ACTION 2 With the number of CPERABLE accident monitoring channets less then the Minimum Number of Channels shown'in Table 3.3-11, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 deleted i
ACTION 4 With the number of OPERABLE channels one less then the Required Number of Channets shown in Table 3.3-11, operations may proceed provided that an OPERAtLE Steam Generator Wide Range Level channet is avaltable es en alternate means of indication for the Steam Generator with no OPERABLE Auxiliary Feedwater Flow Rate Channet.
i ACTION 5 With the number of OPERABLE channels less than the Required i
Number of Channels show in Table 3.3-11, operation may proceed provided that steam Tables are avaltable in the Control Room and the following Required Channets shown in Table 3.3-11 are OPERABLE to provide en alternate means of calculating Reactor Coolant System subcooling margins i
s.
Reactor Coolant Outlet Temperature T
NOT (Wide Range) b.
Reactor Coolant Pressure (Wide Range) i i
i I
i t
l i
t SALEM UNIT 2 3/4 3-51b Amendment No. 125 l
TABLE 4.3-11 SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL CNANNEL FUNCit0NAL INSTRUMENT CHECKS CALIBRAfl0N TEST 1.
Reactor Cootent Outlet Temperature M
R WA T NOT (Wide Range) 2.
Reactor Cootent intet Temperature -
M R
NA T COLD (Wide Range) 3.
Reactor Cootent Pressure (Wide Range)
M R
NA 4.
Pressuriter Water Level M
R NA 5.
Steen Line Pressure M
R NA 6.
Steam Generator Water Level M
R NA (Narrow Range) 7.
Steam Generator Water Level N
R NA (Wide Range) 8.
Refueling Water Storage Tank Water Levet M
R
'wa 9.
deleted
- 10. Auxillery Feedwater Flow Rate 508 R
mA
- 11. Reactor Coolant system subcooling M
W/A*
uA Margin Monitor
- Auxillery Feedwater System is used on each startup and flow rete indicotton is verified at that time.
- The Instruments used to develop RCS subcooling margin are' calibrated on en 18 month cycte; the monitor wilt be compared quarterly with calcuteted subcooling mergin for known input values.
SALEM - UNIT 2 i
3/4 3-52 Amendee.
so. 125
.-