ML20039F119
| ML20039F119 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/16/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20039F120 | List: |
| References | |
| DPR-44-A-082, DPR-56-A-081 NUDOCS 8201120016 | |
| Download: ML20039F119 (16) | |
Text
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UNITED STATES 8"
,o NUCLEAR REGULATORY COMMISSION E
wash mciON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COWANY DELMARVA POWER AND LIGHT COMPANY
_ TLANTIC CITY ELECTRIC COMPANY A
DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
82 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 June 29, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amendcd (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 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 l
defense and security or to the health and safety of the public; I
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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-44 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and l
B, as revised through Amendment No. 82, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
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PDR ADOCK 05000277 P
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.This license hmendment is effective as of the date of its issuance.
OR THE NUCLEAR REGULATORY C0!EISSION r
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. Sto z hief O rating Reactors Branci #4 vision of Licensi.ng 6
Attachment:
Chances to the Technical Specifications Date of Issuance:
December 16, 1981 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATIN3 LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 61 61 63 63 93 93*
93a(new) 94 94*
- 0verleaf page; no change.
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TABLE 3.2._A_
j INSTRUMESTATION TitAT INITIATES PRIMARY CONTAINMENT ISOLATION Mintnan No.
Number of Instrument Channels Provided oo Ins t ru:ae nt Instrenent Trip Level Setting Action Channels per By Design (2) na Trip System (1) 2 (6)
Reactor Low Water t 0" Indicated 4 Inst. Channels A
Level Level (3) 1 Reactor High Pressure 1 75 psig 2 Inst. Channels D
(Shutdcwn Cooling Isolation) 2 Reactor Low-Low at or above -49" 4 Inst. Channel's A
Water Level indicated level (4) 2 (6) liigh Drywell Pressure 1 2 psig 4 Inst. Channels A
2 High Radiation Main 13 X Normal Rated (8) 4 Inst. Channels B
Steam Line Tunnel Full Power Background 2
Low Pressure Main L 850 psig (7) 4 Inst. Channels B
Stean Line 2 (5)
High Flow Main i 140% of Rated Steam Line Stean Flow 4 Inst. Channels B
2 Main Steam Line 1200 deg. F (9) 4 Inst. Channels B
Tunnel Exhaust Duct High Temperature l
6
l I
P!JAPS I
NOTES FOR TABLE 3.2.A Vihanuver Primary Contaibment integrity is required by 1.
Sect on 3.7, there shall be two operable or tripped trip sysccms for cach function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken.
Initiate an orderly shutdown and have the reactor in A.
Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load' reduction and havc Main Stcam Lines isolated within eight hours.
C.
Isolate Reactor Watcr Cleanup System.
D.
Isolate Shutdown Cooling.
3.
Instrument set point cor:csponds to 177.7" above top of active fuel.
4.
Instrument set point corresponds to 129.7" above top of active fuel.
5.
Two required for cach steam line.
G.
These signals also start SBGTS and initiate secondary contain-ment isolation.
7.
Only required in Run Mode (interlocked with Mode Switch).
S.
At a radiation level of 1.5 tiscs the normal rated power background an alar =, will be tripped 'in the control room to alert the control room operators to an increase in the main steam line tunnel radiation icycl.
9.
In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 2500F for a period not to exceed 30 minutes to pemic restoration of the ventilation flow. During the 30-minute period, an operator shall observe control room indications of the duct tempera-tures so in the event of rapid increases (indicative of'a steam line break) the operator shall promptly c)ose the main steam line isolation valves.
Amendnent No. 82 :
3.2 BASES
(Cont'd.)
trip and the other a downscale trip.
There is a fifteen minuto delay before the air ejector off gas isolation valve is closed.
This delay is accounted for by the 30-minute holdup time of the off-gas before it is released to the stack during reactor pouer operation when the recombiner system is not operating.
Bodt instruments are required for trip but the instru-ments are so designed that any instrument f ailure gives a downscale trip.
The trip settings of the instruments are set so that the instantaneous stack release rate limit given in Specification 3.8 is not exceeded.
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.
Four instrument channels monitor the radiation from the re-fueling area ventilation exhaust ducts and four instru-ment channels monitor the. building ventilation below the refueling floor.
Each set of instrument channels is arranged in a-1 out of 2 twice trip logic.
Trip settings of <16 mr/hr for the monitors in the re-fueling area ventilation exhaust ducts are based upon initiating norm al ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reac-ter Building via the normal ventilation path but rather all the activity is processed by the standby gas treat-ment system.
Flow integrators are used to record the integrated flow of liquid from the drywell sumps.
The alarm unit in each integrator is set to annunciate before the values specified in Specification 3.6.C are exceeded.
An air sampling system is also provided to detect leakage in-sida the primary containment.
For each parameter monitored, as lis ted in Table 3.2.F, there are two (2) channels of instrumentation.
By com-l paring readings between the two (2) channels, a near continuous surveillance of instrument performance is l
available.
Any deviation in readings will initiate an early recalibration, thereby maintaining the quality of the instrument readings.
The recirculation pump trip has been added at the sug-l gestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.
The response of the plant to this postulated event fall within the envelope of study events given in General Electric Company Topical Report, NEDO-10349, dated March, 1971.
l Amendment No. 82 l October 1973
~
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.
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.
Anendment flo. 82
-93a-
PBAPS 4.2 BASES The instrumentation listed in Table 4.2.A thru 4.2.P will be functionally tested and calibrated at regularly sche-duled intervals.
The same design reliability goal as the Reactor Protection Systeh of 0.99999 is generally applied for all applications of (1 out of 2) X (2) logic.
There-fore, on-off sensors are tested once/3 months, and bi-stable trips associated with analog senscrs and ampli-fiers are tested once/ week.
Those instruments which, when tripped, result in a rod block have their contacts arranged in a 1 out of n logic, and all are capable of being bypassed.
For such a trip-ping arrangement with bypass capability provided, there is an optimum test interval that should be maintained in order to maximize the reliability of a given channel (7).
This takes account of the fact that testing degrades reliability and the optimum interval between tests is approximately given by:
2t i=
-r g
Where:
i = the optimum interval between tests.
t=
the time the trip contacts are disabled from performing their function while the test is in progress.
r = the expected failure rate of the relays.
To test the trip relays requires that the channel be by-passed, the test made, and the system returned 6 its ini-tial state.
It is assumed this task requires an estimated 30 minutes to complete in a thorough and workmanlike man-ner and that the relays have a failure rate of 10-6 failures per hour.
Using this data and the above opera-tion, the optimum test interval is 2(0 5) = 1 x 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> i
=
,6 s
10
= 40 days For additional marain a test interval of once per month will be used initially.
i (7)
UCRL-50451, Improving Availability and Readiness of Field Equipment Through Periodic Inspection, Benjamin Epstein, Albert Shiff, July 16, 1968, page 10, Equa-tion (24), Lawrence Radiation Laboratory.
i APRIL 1973 Amendment No. 82 Onu
- [
UNITED STATES' o'g NUCLEAR REGULATORY COMMISSION y
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E WASHINGTON. D. C. 20555 k
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PHILADELPHIA ELECTRIC COMPANY
.....f 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. 81 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amer.dment by Philadelphia Electric Company, et al. (the licensee) dated June 29, 1981, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
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 Commission's regulations; 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; i
and l
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 e.hanges to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications,
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1 3,3. ~This license hNndment is effective as of the date of its issuance.
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FOR THE NUCLEAR REGULATORY C0!tilSSION x' V
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s ATTACHMENT TO, LICENSE AMENDMENT NO. 81 jo, FACILITY OPERATING LICENSE NO. DPR-56 i
4 j
e" DOCKET NO. 50-278 1
Replaca the follo)ing pages of the Appendix "A" Technical Specifications
,with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
l t
Remove Insert 61 61 63 63 93 93*
93a(new) 4 t
94 94*
- 0verleaf pa'ge; no change.
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TABLE 3.2.A, g.
INSTREMESTATION TilAT INITIATES PRIMARY COSTAINMENT ISOLATION l
Mininun No.
Number of Instrument b
Channeis Provided I n s t r o:.ie n t Ins t rener.t Trip Level Setting Action
$ Char.nels per y Design (2)
Trip System (1) 2 (6)
Reactor Low Water t 0" Indicated 4 Inst. Channels A
Level Level (3) 1 Reactor High Pressure 1 75 psig 2 Inst. Channels D
(Shutdcwn Cooling Isolation) 2 Reactor Low-Low at or above -49" 4 Inst. Channel $s A
Wate: Level indicated level (4) 2 (6)
High Drywell Pressure 1 2 psig 4 Inst. Channels A
Y 2
High Radiation Main 13 X Norma 1 Rated (8) 4 Inst. Channels B
Steam Line Tunnel Full Power Background 2
Low Pressure Main L 850 psig (7) 4 Inst. Channels B
Stean Line 2 (5)
High Flow Main i 140% of Rated Steam Line Stean Flow 4 Inst. Channels B
2 Main Steam Line 1200 deg. F (9) 4 Inst. Channels B
Tunnel Exhaust Duct High Temperature c
w e
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~
y P! SAPS NCTES FOR TABLE 3.2.A
..hanuver Primary Contaikmea integrity is required by 1.
Section 3.7, there shall be two operabis or tripped trip sysccms for cach function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
In19iate an orderly 104d* reduction and have Main Stcam Lines isolated within eight h; trs.
C.
Isolate Reactor Water Cleanup System.
D.
Isola ta Shtitdown Cooling.
3.
Instrument set point corresponds to 177.7" above top of active fuel.
4.
Instrument set point corresponds to 129.7" above top of active
- fuel, b.
Two required for cach steam line.
G.
These signals also start SEGTS and initiate secondary contain-ment isolation.
7.
Only required in P.un Mcdc (interlocked with Mode Switch).
S.
At a radiation icvel of 1.5 times the normal rated power background an alarm will be tripped 'in the control room to alert the control room operators to an increase in the main steam line tunnel radiation icvel.
9.
In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 2500F for a period not to exceed 30 minutes to permic I
restoration of the ventilation flow. During the 30-minute period, an operator shall observe control room indications of the duct tenpera-tures so in the event of rapid increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.
i Amendment No. 81
_63-
n PDAPS
3.2 DASES
(Cont'd.)
trip and the other a downscale trip.
There is a fifteen minuto delay before the air ejector off-gas isolation valve is closed.
This delay is accounted for by the 30-minute holdup time of the off-gas before it is released to the stack during reactor pouer operation vhen the recombiner system is not operating.
Both instruments are required for trip but the instru-ments are so designed that any instrument f ailure gives a do. nscale trip.
The trip settings of the instruments are set so that the instantaneous stack release rate limit given in Specification 3.8 is net exceeded.
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.
Four instrument channels monitor the radiation from the re-fueling area ventilation exhaust ducts and four instru-ment channels monitor the building ventilation below the refueling floor.
Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.
Trip settings of <16 mr/hr for the monitors in the re-fueling area ventilation exhaust ducts are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reac-tor Building via the normal ventilation path but rather all the activity is processed by the standby gas treat-ment system.
Flow integrators are used to record the integrated flow of liquid from the drywell sumps.
The alarm unit in each integrator is set to annunciate before the values specified in Spacification 3.6.C are exceeded.
An air sampling system is also provided to detect leakage in-side the primary containment.
For cach parameter monitored, as listed in Table 3.2'.F, there are tuo (2) channels of instrumentation.
By com-paring readings between the two (2) channels, a near continuous surveillance of instrument performance is availabic.
Any deviation in readings will initiate an carly recalibration, thereby maintaining the quality of f
the instrument roadings.
The recirculation pump trip has been added at the sug-gestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an antiqipated transient.
The response of the plant to this postulated event fall within the envelope of study events given in General Electric Company Topical Report, NEDO-10349, dated March, 1971. O tober 1973
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.
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.
Amendnent flo. 81
-93a-
PDAPS 4.2 BASES The instrumentation listed in Table 4.2. A thru 4.2.P will be functionally tested and calibrated at regularly ache-duled intervals.
The sape design reliability goal as the Reactor Protection System of 0.99999 is generally applied for all applications of (1 out of 2) X (2) logic.
There-fore, on-off sensors are tested once/3 months, and bi-stable trips associated with analog sensors and ampli-fiers are tested once/ week.
Those instruments which, when tripped, result in a rod block have their contacts arranged in a 1 out of n logic, and all are capable of being bypjssed.
For such a trip-ping arrangement'with bypass capability provided, there is an optimum test interval that should be maintained in (7).
order to maximire the reliability of a given channel This takes account of the fact that testing degrados reliability and the optimum interval between tests is approximately given by:
2t i=
-r S
Where:
i = the optimum interval between tests.
t = the time the trip contacts are disabled from performing their function while the test is in progress.
= the expected failure rate of the relays.
I To test the trip relays requires that the channel be by-passed, the test made, and the system returned 6 ite ini-tial statc.
It is assumed this task requires an estimated 30 minutes to complete in a thorough and workmanlike man-nor and that the relnys have a failure rate of 10-6 failures per hour.
Using this data and the above opera-tion, the optimum test interval is 2(0.5) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> i=
= 1 x 10 6
3 10
= 40 days For additional margin a test interval of once per month will be used initially.
(7)
UCRL-50451, Improving Availability and Readiness of Field Equipment Through Periodic Inspection, Benjamin Epstein, Albert Shiff, July 16, 1968, page 10, Equa-tion (24), Lawrence Radiation Laboratory.
APRIL 1973