ML20248K562
| ML20248K562 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/13/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248K567 | List: |
| References | |
| NUDOCS 8904170376 | |
| Download: ML20248K562 (14) | |
Text
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~k UNITED STATES l'
NUCLEAR REGULATORY COMMISSION c
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j WASHINGTON. D. C. 20656 s...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMAPVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FAC'. CITY OPERATING LICENSE Amendment No.143 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated on January 26, 1989, as supplemented on March 6,1989 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 fcrth 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 such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or 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 Specifications as indicated in the attachment to this license amendment, and paragraph ?.C(?) of Facility Operating License No. OPR-44 is hereby amended to read as follows:
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(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No. '143, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications..
i 1
3.
This license amendment is effective as-of its date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION l
/s/
Walter R. Butler, Director Pro,iect Directorate I-2 Division of Reactor Proiects I/II Attachment.
Changes to the Technical
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 143, are hereby incorporated in the license.
PEC0 shall operate the. facility in accordance with the q
Technical Specifications, q
3.
This ifcense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ql 0
u Walter R. Butler, Director Pro.iect Directorate I-2 Division of Reactor Pro,iects I/II
Attachment:
Changes to the Technical l
Specifications 1
Date of Issuance: April 13, 1989 l
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ATTACHMENT TO LICENSE AMENDMENT NO.143 i
FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 I
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
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s P8APS Unit 2 3.2 8ASES (Cont'd.)
The recirculation pump trip limits the consequences of an anticipated transient without scram (ATWS) event.
The response of the plant to this postulakd event is within the bounds of study events given in General Electric Company Topical Report, NE00-10349, dated March, 1971.
An alternate rod insertion scram limits the consequences of a Reactor Protection System failure to scram during an anticipated transient.
The ARI/RPT System is electrically diverse from the RPS logic and actuation circuitry, which significantly reduces the potential for ATWS events caused by common mode electrical failures in RPS.
The ARI/RPT system is required by 10 CFR 50.62.
In the event of a loss of the reactor building ventilation system, radiant heating in the vicinity of the main steam lines raises the ambient temperature above 200 degrees F.
Restoration of the main steam line tunnel ventilation flow momentarily exposes the temperature sensors to high gas temperatures.
The momentary temperature increase can cause an unnecessary main steam line isolation and reactor scram.
Permission is provided to increase the temperature trip setpoint to 250 degrees F for 30 minutes during restoration of ventilation system to avoid an unnecessary plant transient.
The Emergency Aux. Power Source Degraded Voltage trip function prevents damage to safety ralated equipment in the event of a sustained period of low voltage.
The voltage supply to each of the 4kV buses will be monitored by undervoltage relaying.
With a degraded voltage condition or, the off-site socrce, the undervoltage sensing relays operate to initiate a timing sequence.
The timing sequence provides constant and inverse time voltage characteristics.
Degraded voltage protection includes:
(1) An instantaneous relay (27N) initiated at 98% voltage which initiates a 60 second time delay relay which is inhibited (locked out) from initiating transfer in the presence of a safety injection signal; (2) An instantaneous relay (27N) initiated at 89% voltage which intiates a 9 second time delay relay which requires the presence of a safety injection signal to initiate tra;1sfer; (3) An inverse time voltage relay (CV-6) initiated at 87% voltage with a maximum 60 second delay and operates at 70% voltage in 30 seconds; and (4) An inverse time voltage relay l
(IAV) initiated at approximately 60% voltage and operates at 1.8 seconds at zero volts.
When the timing sequence is completed, the corresponding 4kV emergency circuit l
breakers are tripped and the emergency buses are transferred to the alternate j
source.
The O-second timing sequences were selected to prevent unnecessary transfers during motor starts and to allow the automatic tapchanger on the I
startup transformer to respond to the voltage condition.
The 9-second timing l
sequence is necessary to prevent separation of the emergency buses from the off-site source during motor starting transients, yet still be contained within the time envelope in FSAR Table 8.5.1.
-93a-Amendmen t No. 82, 97, 123, 14I,143 1
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o UNITED STATES l
t, NUCLEAR REGULATORY COMMISSION g
E WASHINGTOU D. C. 20656 k.....,o I
s PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.145 i
License i'o. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated on January 26, 1989, as supplemented on March 6, 1989 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; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health or safety of the public; and E.
The issuance of this aan 1ent 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 Specifications as indicated in the attachment to this license amendment, i
and paragraph P.C(2) of Facility Operating License No. DPR-56 is hereby l
amended to read as follows:
l I
1 l
I
. (2)
Technical Specifications ThE Technical Specifications contained in Appendices A and 8, as revised through Aaendment No.145, are hereby incorporated in the license. PEC0 s,.all operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: April 13, 1989
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n' ' Yl t
L Walter R. Rutler, Director Project Directorate I-?
Division of Reactor Proiacts I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: April 13, 1989
l ATTACHMENT TO LICENSE AMENDMENT NO.14_5 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 l
Replace the following pages of the Appendix A Technical Specifications with j
the enclosed pages. The revised areas are indicated by marginal lines.
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9 PBAPS Unit 3 3.2 BASES (Cont'd.)
The recirculation pump trip limits the consequences of an anticipated transient without scram (ATWS) event.
The response of the plant to this postulated event is within the bounds of study events given in General Electric Company Topical Report, NE00-10349, dated March, 1971.
An alternate rod insertion scram limits the consequences of a Reactor Protection System failure to scram during an anticipated transient.
The ARI/RPT System is electrically diverse from the RPS logic and actuation circuitry, which significantly reduces the potential for ATWS events caused by common mode electrical failures in RPS.
The ARI/RPT g
system is required by 10 CFR 50.62.
In the event of a loss of the reactor building ventilation system, radiant heating in the vicinity of the main steam lines raises the ambient temperature above 200 degrees F.
Restoration of the main steam line tunnel ventilation flow momentarily exposes the temperature sensors to high gas temperatures.
The momentary temperature increase can cause an unnecessary main steam line isolation and reactor scram.
Permission is provided to increase the temperature trip setpoint to 250 degrees F for 30 minutes during restoration of ventilation system to avoid an unnecessary plant transient.
The Emergency Aux. Power Source Degraded Voltage trip function prevents damage to safety-related equipment in the event of a sustained period of low voltage.
The voltage supply to each of the 4kV buses will be monitored by undervoltage relaying.
With a degraded voltage condition on the off-site source, the undervoltage sensing relays operate to initiate a timing sequence.
The timing sequence provides constant and inverse time voltage characteristics.
Degraded voltage protection includes:
(1) An instantaneous relay (27N) initiated at 98% voltage which initiates a 60 second time delay relay which is inhibited (locked out) from initiating transfer in the presence of a safety injection signal; (2) An instantaneous relay (27N) initiated at 89% voltage which intiates a 9 second time delay relay which requires the presence of a safety injection signal to initiate transfer; (3) An inverse time voltage relay (CV-6) initiated at 87% voltage with a maximum 60 second delay and operates at 70% voltage in 30 seconds; and (4) An inverse time voltage relay l
(IAV) initiated at approximately 60% voltage and operates at 1.8 seconds at zero volts.
When the timing sequence is completed, the corresponding 4kV emergency circuit breakers are tripped and the emergency buses are transferred to the alternate source.
The 60-second timing sequences were selected to prevent unnecessary transfers during motor starts and to allow the automatic tapchanger on the startup transformer to respond to the voltage condition.
The 9-second timing l
sequence e, necessary to prevent separation of the emergency buses from the off-site source during motor starting transients, yet still be contained within the time envelope in FSAR Table 8.5.1.
-93a-Amendment No. SI, 99, 227, JH,145
_