ML20084C827
| ML20084C827 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/11/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084C816 | List: |
| References | |
| NUDOCS 8404300303 | |
| Download: ML20084C827 (2) | |
Text
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o tec j
oq'o, UNITED STATES y
NUCLEAR REGULATORY COMMISSION e
n WASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated December 22, 1977, as supplemented July 29,1983 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 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 license 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 Specifications as indicated in the attachment to this license amendment, and p_aragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
8404300303 840411 PDR ADOCK 05000277 P
I
. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are hereby incorporated in the license. PEC0 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
.i J 'n F. Stolz, Chief -
erating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 11, 1984
ATTACHMENT TO LICENSE AMENDMENT N0. 99 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET N0. 50-278 Replace the following pages and add the new pages of the Appendix "A" Technical Specifications with the enclosed pages. The pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 71 71 71a 71b 81 81 81a 93a 93a
TABLE 3.2.B (CONTINUED)
INSTRUMENTATION TIIAT INITIATES OR CONTROLS TIIE CORE AND CONTAINMENT
~
, COOLING SYSTEMS Minimum No.
Number of Cf Operable Instrument Instrument Trip Function Trip Level Setting Channels Remarks Chhnnels Per Provided by Trip System (1)
Design l
l 4(5)
IIPCI Steam Line 100>p>50 psig (3) 4 Inst.
Low Pressure 2
IIPCI Turbine
<200 deg.F (3) 4 Inst.)
~
Compartment
)
Temperature
.)
l
)
l 4
IIPCI Steam Line
<200 deg.F (3) 8 Inst.) 16 Inst.
Area Temperature
)
i
)
w
)
Y 2
HPCI/RHR Valve
-<200 deg.F (3) 4 Inst.)
Station Area Temperature 1
LPCI Cross-Connect NA 1 Inst.,
Initiates annun-Position clation when valve is not closed.
I per 4KV 4KV Emergency Bus 251(+5%)of Rated
- 1. Trips all loaded Bus Undervoltage Relay Voltage breakers.
(HGA)
- 2. Fast transfer permissive.
- 3. Dead bus start of diesci.
1 per 4KV 4KV Emergency Bus 951(+0%,-10%)of Pormits sequential Bus Sequential Loading Rated Voltage starting of Relay (SV) vital loads Amendment No. JJ, 99
J
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TABLE 3.2.B (CONTINUED)
INSTRUMENTATION TIIAT INITI ATES OR CONTROLS Tile CORE AND CONTAINMENT COOLING SYSTEMS Minimum No.
Number of of Operable Instrument l
Instrument Trip Function Trip Level, Setting Channels Remarks l
Channels Per Provided by Trip System (1)
Design 2 per 4 KV Emergency 60%(+5%)of Rated
- 1. Trips emergency Bus Transformer Voltage. Test at transfer feed Undervoltage(IAV) zero volts in 1.8 to 4KV emer-(Inverse time-seconds (+10%).
gency bus.
voltage)
- 2. Fast transfer permissive.
l 2 per 4 KV Emergency Trans-90%(+2%) of Bus former Degraded raEed voltage voltage (ITE)
(Instantaneous) 8, 60 second
- 1. Trips emergency
'y'
(+5%) time delay.
transformer feed s
to 4 KV emopgency bus.
- 2. Fast transfer permissive.
6 second(+5%)
- 1. Trips emergency
. time deTay.
transformer feed to 4 KV emer-gency bus.
- 2. Pant transfer permissive.
- 3. Safety injec-tion signal required.
/Wiendment No. 99
TABLF. 3.2.B (CONTINUED)
INSTRUMENTATION TilAT INITIATES OR CONTROLS Tile CORE AND CONTAINMENT COOLING SYSTEMS Minimum No.
Number of Of Operable Instrument Instrument Trip Function Trip Level Setting Channels Pemarks Channels Per Provided by Trip System (1)
Design 2 per 4 KV Emergency Trans-87t(+5%) of
- 1. Trips emergency Bus former Degraded Rated Voltage.
transformer feed voltage (Inverse Tests at 2940 to 4 KV emer-time - voltage).
volts in 30 s'conds gency bus.
e (CV-6)
(+10%)
- 2. Fast trannfer
~
permissive.
4 Yr 1
l Amendment No. 99
u TABLE 4.2.B HINIMUM TEST AND CALIBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check 1)
Reactor water (1) (3)
Once/ operating cycle Once/ day i
Level (7) 2)
Drywell Pressure (1) (3)
Once/ operating cycle Once/ day (7) 3)
Reactor Pressure (1) (3)
Once/ operating cycle Once/ day (7)
~
4)
Auto Sequencing NA Once/ operating cycle None Timers 5).
Once/3 months None Pump Disch. Pressure Interlocks 16)
Trip System Bus (1)
NA Hono y'
Power Monitors 7)
Core Spray (1)
Once/6 months once/ day Sparger d/p 8)
Steam Line High (1)
Once/3 months None Flow (HPCI & RCIC) 9)
Steam Line High (1) (3)
Once/ operating cycle Once/ day Temp. (HPCI & RCIC) 10)
Safeguards Area (1)
Once/3 months None Hi gh Temp.
Once/3 months Nonc Steam Line Low l
Pressure l
Amendment No. pf, 99
u__.
TABLE 4.2.B (CONTINUED)
MINIMUM TEST AND CALIBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional Test Calibration Frequency Inntrument check
- 12) HPCI Suction Source (1)
Once/3 months None Levels
- 14) ADS Relief Valves Once/ operating cycle Once/ operating cycle None Bellows Pressure Switches IF) LPCI/ Cross connect Once/ refueling cycle N/A N/A Valve Position
- 16) 4KV Emergancy Power Once/ month Once/ operating cycle None i
Source Degraded Voltage Relays o
(IAV,CV-6,ITE) 1 l
l kiendment No. 99 u____
pBAPS 3.2 BASES (Cont'd)
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.
Restcration of the main steam line tunnel ventilation flow momentarily exposes the temperature sensors to high gas temperatures.
The momentary temperature increase can cause an unnec.essary 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 undervoltuge relaying. With a degraded voltage condition on the offsite source the undervoltage sensing relays operate to initiate a timing sequence.
The timing sequence provides constant and inverse time voltage s
characteristics.
Degraded voltage protection includes: (1) An instantaneous relay (ITE) initiated at 90% voltage which initiates a 60-second time delay relay and a 6 second time delay relay.
The 6 second time. delay relay requires the presence of a Saf ety Injection Signal to initiate transfer; (2) 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 (3)
An inverse time voltage relay (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 tre transferred to the alternate source. ite sixty second timing sequences were selected to prevent unnecessary transfers during motor starts and to allow the automatic tapchanger on the startup transf ormer to respond to the voltage condition.
The six second timing sequence is necessary eo prevent separation of the emergency buses from the offsite source during motor starting transients; yet still be contained within the time envelope in FSAR Table 8.5.1.
-93a-Amendment No. 57,99
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%,.....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENTS NOS. 97 AND 99 TO FACILITY OPERATING LICENSES NOS. DPR-44 AND DPR-56 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COPPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION, UNITS NOS. 2 AND 3 00CKETS NOS. 50-277 AND 50-278 Introduction By letter dated December 22, 1977, the Philadelphia Electric Company (the licensee) requested an amendment for the Peach ' Bottom Atomic Power Station, Units Nos. 2 and 3, to provide limiting conditions for operation, surveillance requirements, and bases associated with a modification that would provide a second level of undervoltage protection with a time delay for safety-related loads (degraded grid voltage protection system). This application was supplemented on July 29, 1983, as a result of discussions and correspondence between the licensee and the NRC staff.
Evaluation By letter dated June 14, 1983, the NRC staff provided the licensee with a revised Safety Evaluation Report.
In its Safety Evaluation, the NRC staff concluded that the licensee should revise its previous application for amendment to reflect a functional testing frequency of once per month for degraded grid voltage relays and incorporate the surveillance setpoints for the CV-6 and IAV relays in the Technical Specifications. The licensee's submittal of July 29, 1983, supplementing its previous application, proposed the incorporation of these two changes into the Peach Bottom Technical Specifications. Therefore, we now conclude that the licensee's proposed limiting conditions for operation, surveillance requirements, and bases pertaining to a modification providing a second level of undervoltage protection are acceptable.
In addition, the licensee also proposed the deletion of obsolete specifications and footnotes for Unit 3 on Table 4.2.-
.ecause the modifications authorized by Amendment No. 67 have beet completed.
We find this request to be administrative in nature, and therefore, conclude that the proposed deletions are acceptable.
t
_2_
Environmental Considerations We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 951.5(d)(4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safet will not be endangered by operation in the proposed minner,y of the public and(2)such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
April 11, 1984 The following NRC personnel have contributed to this Safety Evaluation:
Gerry Gears P
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