ML20247Q523
| ML20247Q523 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247Q527 | List: |
| References | |
| NUDOCS 8906060451 | |
| Download: ML20247Q523 (18) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION o
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PUBLIC SERVICE ELECTRIC & GAS COMPANY l
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 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 Cor;any,(Delmarva Power and Light Company and Atlantic City Electric Company the licensees) dated October 17, 1985, and supplemented on December 18, 1986, 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 A d, and the rules and regulations of the i
Comission; C.
There is reasonable assurance: (i) that the activities authorized by this amendmerc can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliaoce with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issrance 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 is!.uance of this amendment is in accordance with 10 CFR Part 51 of j
the Cocunission's regulations and all applicable requirements have been j
satisfied.
1 2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as in,iicated 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:
8906060451 890531 ADDCK 05000272 [7 PDR PNU y
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(2)'.TechnicalSpecificationsandEnvironmentalProtection-Plan-o The Technical S' specifications contained in Appendices A and B, as revised through Amendment No. '97 ;,.,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 dat'efof issuance,to be-
~ implemented within 30 days of the date of: issuance; FOR THE NUCLEAR-REGULATORY-COMMISSION
' S/2
/
Walter R. Butler,'Directdr Project Directorate.1-2 Division of Reactor Projects I/II.
Attachment:
a Changes to the Technical-Specifications l
Date of Issuance: May 31, 1989 y
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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. 97, are hereby incorporated in the.
license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This' license anendment'is effective as of its date of issuance to be L
implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
v Walter R. Butler, Director i
Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the. Technical t
1 Specifications Date of Issuance:
May 31, 1989 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-4 3/4 3-4 3/4 3-7 3/4 3-7
-' t 3/4 3 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-13a I'
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N SALEM - UNIT 1 3/4 3-4 Amendment No. 97
i TABLE 3.3-1 (Continu d) 4 ACTION 9 -
. With a channel associated with an operating loop inoperable, restore the inoperable' channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in 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 />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.
ACTION 10 -
Deleted.
ACTION.11 -
With less than the Minimum Number of ' Channels OPERABLE, operation may continue.provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.-
ACTION 12 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, 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 next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 13 -
With the number of 01Y2ABLE channels one less than the Minimum Channels OPERABLE requirement, 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 open the' reactor trip breakers within the next hour.
ACTION 14 -
With one of the diverse trip features (Undervoltage or shunt.
trip attachment) inoperable, restore it 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 declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The breaker shall not be
' bypassed while one'of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.
REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels < 6 x 10-11 the manual block of amps.
source range reactor trip.
P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels 2 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low i
impulse chamber pressure channels flow in more than one 2 a pressure equivalent to 11% of primary coolant loop, i
RATED THERMAL POWER.
reactor coolant pump L
undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.
SALEM - UNIT 1
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TABLE 4.3-1TContinuEd)
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-With theLreactor trip system breakers closed and the control rod
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drive system capable of rod withdrawal.
(1) -
If not performed in previous 7 days.
(2)
Heat balance only, above'15% of RATED THERMAL POWER.
(3)
Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrates if absolute difference 1 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 detectors may be excluded from CHANNEL CALIBRATION.
(7)
Below P-6 (Block of Source Range Reactor Trip) setpoint.
(8) -
Deleted (9)
If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip-wiring.
(10) -
If not' performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:
Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSPS)
Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)
(11) -
Perform a functional test of:
Reactdr Trip Breaker independent operation of U.V. Trip and Shunt Trip (irie SSPS) and conduct response time testing of U.V. and Shunt Trip / Breakers (event recorders)
Reactor Trip Breaker Shunt Trip (via manual pushbutton controls) l (12) -
Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as follows:
response time testing, (3 times) (visicorder) trend data a.
b.
trip bar lift force measurements
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c.
UV output force measurement d.
dropout voltage check i
servicing / lubrication / adjustments (See Table 3.3-1 Notation e.
OHH) f.
repeat testing steps (a-d) following any necessary actions at step (e) l SALEM - UNIT 1 3/4 3-13 Amendment No. 97 l
1
. TABLE'4.3-1(Continuod),
o NOTATION (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.
( 1' 4 ) --
Perform a functional test of the B.rpass Breakers U.V. Attachment via the SSPS.
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SALDf - UNIT 1 3/4 3-13a Amendment No. 97
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UNITED STATES l-
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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 SALEM GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-75 1.
The Nuclear Regulatory Comission (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 Ligh Company and Atlantic City Electric Company thelicensees) dated October 17, 1985, and supplemented on December. 18, 1986, 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 Comission; 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 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 Comission's regulations and all applicable requirements have been satisfied.
i 2.
Accordingly, the license is amended by changes to the Technical Specifica-l tions as indicated in the attachment to this license amendment, and i
paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
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(2) Technical Specifications and Environmental Protection Plan s
The Technical Specifications contained.in Appendices-A and B -as revised through Amendment No..74
,.are hereby-incorporated in the
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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 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY,. COMMISSION
~
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' Walter R., Butler, Director.
Project Directorate I-2
~
Division.of Reactor Projects.I/II
Attachment:
Changes to the. Technical Specifications
' Date of' Issuance:
May 31, 1989 1
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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. 74, 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 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c:
G qi Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 31, 1989 I
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_---__---_--_-_a
ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
sa-Remove Pages Insert Pages 3/4 3-4 3/4 3-4 3/4 3-7 3/4 3-7 3/4 3-12 3/4 3-12 3/4-3-13 3/4-3-13 3/4 3-13a
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TABLE 3.3-1 (Continu-d)
ACTION 9 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in 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 /> however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.
ACTION 10 -
Deleted.
ACTION 11 -
With less than the Minimum Number of Channels OPERABLE, j
operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 12 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, 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 next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 13 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, 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 open the reactor trip breakers within the next hour.
ACTION 14 -
With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERA 2LE status -
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.
REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range,11 P-6 prevents or defeats Neutron Flux Channels < 6 x 10 the manual block of amps.
source range reactor trip.
P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels 2 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low impulse chamber pressure channels flow in more than one 2 a pressure equivalent to 11% of primary coolant loop, RATED THERMAL POWER.
reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.
SALEM - UNIT 2 3/4 3-7 Amendment No.
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/t v
f nou y
oi o
L mL mS r s r s iLT t
t t t
A s
a -
a ep ep b
e ci c
N s
ew ew d m d m r
f as a
O o
t o t o nu nu u
a eo e
I L
SL SL UP UP T ab S
RP R
TC N
U 3
4 5
6 7
8 9.
0 1
F 1
1 1
1 1
1 1
2 2
1 vy3, c2 -:54 2 o;
b" 2 { 3" 5 3
^
t]
s.y TABLE 4.3-l'(Continurd)
NOTATION With the reactor trip system breakers closed and the control rod
. drive system capable of rod withdrawal.
(1)
If not performed in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER.
-(3)
-Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrates if absolute difference 2 3 percent.
(4)
_ Manual-SSPS functional input clieck every 18 months.
(5)
Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
'Below P-6-(Block of Source' Range Reactor Trip) setpoint.
(8)
Deleted (9)
If.not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of.the U.V. and shunt trip wiring.-
(10) -
If not performed in'the previour, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct'a functional test of:
Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSPS)
Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)
(11) -
Perform a functional test of:
Reactor Trip Breaker independent operation of U.V. Trip and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip / Breakers (event recorders)
Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)
(12) -
Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as follows:
a.
response time testing, (3 times) (visicorder) trend data b.
trip bar lift force measurements c.
U.V. output force measurement d.
dropout voltage check l
l.
SALEM - UNIT 2 3/4 3-13 Amendment No. 74
b TABLE 4.3-1 (Continutd)
)
~ ' '
NOTATION servicing / lubrication / adjustments (See Table 3.3-1 e.
Notation fl##)-
.f.
repeat testing steps (a-d) following any necessary actions'at step-(e)
.(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.
(14) -
Perform a functional test of the Bypass Breakers U.V. Attachment via the SSPS.
1 l
SALEM - UNIT 2 3/4 3-13a Amendment No. 74 l
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