ML20092A723
| ML20092A723 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 09/06/1995 |
| 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 | |
| ML20092A726 | List: |
| References | |
| DPR-70-A-175, DPR-75-A-156 NUDOCS 9509110166 | |
| Download: ML20092A723 (16) | |
Text
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ni UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001
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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 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 175 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 at Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated May 2, 1995, 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 i
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. DPR-70 is hereby amended to read as follows:
9509110166 950906 ~
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PDR ADOCK 05000272 p
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. l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.175, 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 l
implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
h F. Stolz, Direc ect Directorate
-2 Division of Reactor Projects - I/II 1
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance: September 6, 1995 i
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i ATTACHMENT TO LICENSE AMENDMENT NO.175 l
t FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
i Remove Paces Insert Paaes l
3/4 3-20a 3/4 3-20a 3/4 3-22 3/4 3-22 3/4 3-26 3/4 3-26 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 i
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IABLE'3.3-3 iCont15,3 1 ENGINEERED SAFETY FEATURE ACTUATION 3 STEM INSTRUMENTATION MINIMUM TOTAL NO CHANNELS CHANNELS APPLICABLE l
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 8.
AUXILIARY'FEEDWATER l
a.
Automatic Actuation Logic **
2 1
2 1,2,3
'O l
b.
NOT USED c'
Steam Generator water Level--Low-Low
- i. Start Motor Driven Pumps 3/stm. gen.
2/stm. gen.
2/stm. gen.
1,2,3 19*
any stm. gen.
ii. Start Turbine Driven Pumps 3/stm. gen.
2/stm. gen.
2/stm. gen.
1,2,3 19*
any 2 stm. gen.
d.
Undervoltage - RCP Start 4-1/ bus 1/2 x 2 3
1,2 19 Turbine - Driven Pump e.
S.I. Start Motor-Driven Pumps See 1 above (All S.I.
initiating functions and requirements) f.
Trip of Main Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2 21*
Start' Motor Driven Pumps g.
Station Blackout See 6 and 7 above (SEC and U/V Vitai Bus)
SALEM - UNIT 1 3/4 3-20a Amendment No.I75
.____m.._..
e TABLE 3.3-3 (Continued) 1 ACTION 19 -
With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER CPERATION may proceed provided the following conditions are satisfied a.
The inoperable channel is placed in the tripped l
condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.1.
ACTION 20 -
With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> i
for surveillance testing per Specification 4.3.2.1.1 provided the other channel is OPERABLE.
ACTION 21 -
With the number of OPERABLE channels one less than the 1
Minimum Number of Channels, operation may proceed provided that either:
a.
The inoperable channel is restored to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or b.
If the affected Main Feedwater Pump is expected to be out of eervice for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the inoperable channel is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon the loss of the other Main Feedwater Pump.
ACTION 22 -
NOT USED
]
ACTION 23 -
With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel 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 HOT STANDBY within, the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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SALEM - UNIT 1 3/4 3-22 Amendment No.175
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TABLE 3.3-4 fcontinued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLONABLE VALUES 5.
TURBINE TRIP AND FEEDWATER ISOLATION A.
Steam Generator Water Level --
5 67% of narrow range s 68% of narrow range High-High instrument span each instrument span each steam generator steam generator 6.
SAFEGUARDS EQUIPMENT CONTROL Not Applicable Not Applicable SYSTEM (SEC) 7.
UNDERVOLTAGE, VITAL BUS l
a.
Loss of Voltage 2 70% of bus voltage a 65% of bus voltage b.- Sustained Degraded voltage 2 94.6% of bus voltage for k 944 of bus voltage for s 13 seconde s 15 seconds 8.
AUKILIARY FEEDWATER a.
Automatic Actuation Logic Not Apolic.able Not Applicable i
L b.
NOT USED
[
c.
Steam Generator Water Level--
t 9.0% of narrow range 2 8.0% of narrow range j
Low-Low instrument span each instrument span each steam generator steam generator d.
Undervoltage - RCP 2 70% RCP bus voltage E 65% RCP bus voltage i
e.
S.I.
See 1 above (All S.I.
setpoints) f.
Trip of Nain Feedwater Pumps Not Applicable Not Applicable g.
Station Blackout See 6 and 7 above (SEC and Undervoltage, Vital Bus)
SALEM - UNIT 1 3/4 3-26 Amendment No.175 l
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TABLE 4.3-2 iContinued1 ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATIOff SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 8.
Automatic Actuation Logic N.A.
N.A.
M(2) 1,2,3 b.
NOT USED c.
Steam Generator Water S
R Q
1,2,3 Level--Low-Low d.
.Undervoltage - RCP S
R Q
1,2 e.
S.I.
See 1 above (All S.I.
surveillance requirements) f.
Trip of Main Feedwater Pumps N.A.
N.A.
R 1
g.
Station Blackout See 6b and 7 ab'ove (SEC and U/V Vital Bus)
SALEM - UNIT 1 3/4 3-33 Amendment No. 175
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i TABLE 4.3-2 (Continued)
TABLE NOTATION outputs are up to, but not including, the output relays.
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(1) Each logic channel shall be tested at least once per 62 days on a STAGGERED TEST BASIS.
The CHANNEL FUNCTION TEST of each logic channel l
shall verify that its associated diesel generator automatic load sequence timer is OPERABLE with the interval between each load block within 1 second of its design interval.
(2) Each train or logic channel shall be tested at least every 62 days on a staggered basis.
t (3) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by
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applying either a vacuum or pressure to the appropriate side of the 4
transmitter.
(4)
NOT USED l
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(5) NOT USED l
j (6)
Inputs from Undervoltage, Vital Bus, shall be tested monthly.
Inputs from Solid State Protection Sys. tem shall be, tested every 62 days on a l
STACGERED TEST BASIS.
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1 SALEM - UNIT 1 3/4 3-34 Amendment No.175 t
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t UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20066 4001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 4
SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 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
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May 2, 1995, 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 assurarice: (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 1
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. DPR-75 is hereby amended to read as follows:
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(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156, 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 i
Jh F. Stolz, Direc r P
ect Directorate
-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications k
Date of Issuance: September 6, 1995 1
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ATTACHMENT TO LICENSE AMENDMENT NO.156 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 3-21 3/4 3-21 3/4 3-23 3/4 3-23 3/4 3-27 3/4 3-27 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 l
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-o TABLE 3.3-3 (Continuedl ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUt*.
i TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 8.
Automatic Actuation Logic **
2 1
2 1,2,3 20 b.
NOT USED c.
Stm. Gen. Water Level-Low-Low l
1.
Start Motor Driven Pumps 3/sta. gen.
2/stm. gen.
2/sta. gen.
1,2,3 19*
any stm. gen.
ii. Start Turbine Driven Pumps 3/sta. g'e n.
2/sta gen.
2/sta. gen.
1,2,3 19*
any 2 sta. gen.
4 d.
Undervoltage - RCP Start 4-1/ bus.
1/2 x 2 3
1,2 19 Turbine - Driven Pump e.
S.I. Start Motor-Driven Pumps See 1 above (All S.I.
initiating functions and requirements) l f.
Trip of Main Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2 21*
Start Motor-Driven Pumps g.
Station Blackout See 6 and 7 above (SEC and UV Vital Bus) 9.
SEMIAUTOMATIC TRANSFER TO RECIRCULATION a.
RWST Level Low 4
2 3
1,2,3 16 b.
Automatic Actuation Logic 2
1 2
1,2,3 20 l
r SALEM - UNIT 2 3/4 3-21 Amendment No.156
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i TABLE 3.3-3 (Continued)
ACTION 19 -
With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition -
l within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
The Minimum Channels OPERABLE requirements is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.1.
ACTION 20 -
With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to operable status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1 provided 4
the other channel in OPERABLE.
ACTION 21 -
With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:
a.
The inoperable channel is restored to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
j b.
If the affected Main Feedwater Pump is expected to be out of service for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the inoperable channel is jumpered so as to enable the Start Circuit of the I
Auxiliary Feedwater Pumps upon loss of the other Main Feedwater Pump.
ACTION 22 -
NOT USED ACTION 23 -
With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel 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 at least HOT STANDBY within j
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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SALEM - UNIT 2 3/4 3-23 Amendment No.
156
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TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 7.
UNDERVOLTAGE, VITAL BUS a.
Loss of Voltage 2 70% of bus voltage 2 65% of bus voltage b.
Sustained Degraded Voltage 2 94.6% of bus voltage for 2 94% of bus voltage for s 13 seconds s 15 seconds 8.
Automatic Actuation Logic Not Applicable Not Applicable b.
NOT USED c.
Steam Generator Water Level--
2 9.0% of narrow range 2 8.0% of narrow range Low-Low instrument span each instrument span each steam generator steam generator d.
Undervoltage - RCP 2 70% RCP bus voltage 2 65% RCP bus voltage e.
S.I.
See 1 above (all S.I. setpoints) f.
Trip of Main Feedwater Pump Not Applicable Not Applicable g.
Station Blackout See 6 and 7 above (SEC and Undervoltage,' Vital Bus) 9.
SEMIAUTOMATIC TRANSFER TO RECIRCULATION a.
RWST Low Level 15.25 ft. above 15.25 + 1 ft. above Instrument taps instrument taps b.
Automatic Actuation Logic Not Applicable Not Applicable SALEM - UNIT 2 3/4 3-27 Amendment No.156
TABLE 4.3-2 fContinued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
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SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED 8.
Automatic Actuation Logic N.A.
N.A.
M(2) 1,2,3 b.
NOT OSED c.
Steam Generator Water S
R Q
1,2,3 Level--Low-Low d.
Undervoltage - RCP S
R Q
1,2 e.
S.I.
See 1 above (All S.I.
surveillance requirements) f.
Trip of Main N.A.
N.A.
S/U(4) 1,2 l
Feedwater Pumps g.
Station Blackout See 6 and 7 above (SEC and U/V Vital Bus) 9.
SEMIAUTOMATIC TRANSFER TO RECIRCULATION l
a.
RWST Low Level S
R Q
1,2,3 i
b.
Automatic InitLation Logic N.A.
N.A.
N.A.
1,2,3,4 l
SALEM - UNIT 2 3/4 3-36 Amendment No.156 l
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e TABLE 4.3-2 (Continued)
TABLE NOTATION Outputs are up to, but not including, the Output Relays.
(1) Each logic channel shall be tested at least once per 62 days on a STAGGERED TEST BASIS.
The CHANNEL FUNCTION TEST of each logic channel shall verify that its associated diesel generator automatic load sequence timer is OPERABLE with the interval between each load block within 1 second of its design interval.
)
(2) Each train or logic channel shall be tested at least every 62 days on l
a STAGGERED TEST BASIS.
(3) The CRANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.
(4)
If not performed in the previous 92 days.
(5) NOT USED (6)
Inputs from undervoltage, Vital Bus, shall be tested monthly.
Inputs from Solid State Protection System, shall be tested every 62 days on a STAGGERED TEST BASIS.
SALEM - UNIT 2 3/4 3-37 Amendment No.156