ML20083P468
| ML20083P468 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/28/1984 |
| 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 | |
| ML20083P472 | List: |
| References | |
| DPR-44-A-096, DPR-56-A-098 NUDOCS 8404200023 | |
| Download: ML20083P468 (16) | |
Text
.
pS "%q'o UNITED STATES
~g NUCLEAR REGULATORY COMMISSION n
.(
WASHINGTON, D. C. 20555
\\
/
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al.
(the licensee) dated March 11, 1983, 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 regulations of the Comission; 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 Comission's regulations; D.
The issuance of this license 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating. License No. DPR-44 is hereby amended to read as follows:
8404200023 840328 PDR ADOCK 05000277 P
1
_2_
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effec;ive as of its date of issuance.
FORTHENUCLEARREGpLATORYCOMMISSION
?
John'F. Stolz, Chief Ogerating Reactors Branch #4 ivision of Licensing
Attachment:
i Changes to the Technical Specifications a
Date of Issuance: March 28, 1984 4
i I
J 4
21
ATTACHMENT TO !_ICENSE AMENDMENT N0.96 FACILITY OPERATING 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 a vertical line indicating the area of change.
Remove Insert 4
4 67 67
?40m 240m 240n 240n 262 262
)
PBAPS 1
l l.0 DEFINITIONS (cont'd)
I component, or device to perform its function are also capable of performing their related support function.
Operating - Operating means that a system or component is performing its intended functions in its required manner.
Operating Cycle - Interval between the end cf one refueling outage for a particular unit and the end of the next subsequent refueling outage for the same unit.
Primary Containment Integrity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:
1.
All primary containment penetrations reqvired to be closed during accident conditions are either:
a)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b)
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed I
position, except as may be provided in Specifications
- 3. 7.D. 2 and 4. 7.D. 2.
Manual valves may be opened to l
perform necessary operational activities.
i 2.
At least one door in each airlock is closed and sealed.
3.
All blind flanges and manways are closed.
Protective Action - An action initiated by the protection system l
when a limit is reached.
A protective action can be at a channel j
or system level.
Protective Function - A system protective action which results I
from the protective action of the channels monitoring a particular plant condition.
Rated Power - Rated power refers to operation at a reactor power j
of 3,293 MWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license.
Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power. 4 Amendment No. A7, 79, 77, 96
N 8
{
TABLE 3.2.B (CONTINUED)
INSTRUt1ENTATION TilAT INITIATES OR CONTROLS Tile CORE AND CONTAINMENT 5
COOLING SYSTEMS 23 Minimum No.
Of Operable Number of Instru-e Instrument Trip Function Trip Level Setting ment Channels Pro-Remarks Channels Per vided by Design Trip System (l) 2 Core Spray Pump 6 i l sec 4 timers In conjunction with loss Start Timer 10 i 1 sec 4 timers of power initiates the starting of CSCS pumps.
~
2 LPCI Pumo Start Timor 5 i l sec 4 timers
^
(Two Pumps) 1 Auto Blowdown Timer 90 <
t< 120 2 timers In conjunction with Low Reactor Water Level, i
High Drywell Pressure and LPCI or Core Spray
.i Pump running interlock, initiates Auto Dlowdown.
2 RilR (LPCI) Pump 50 1 10 psig 4 channels Defers ADS actuation Discharge Pressure pending confirmation of Interlock Lou Pressure Core Cooling system operation (LPCI Pump running interlock.)
2 Core Spray Pump 185 1 10 psig 4 channels Defers ADS actuation Discharge Pressure pending confirmation of Interlock Low Pressure Core Cooling system operation (Core Spray Pump running interlock.)
Jr 4
w
l l
TABLE 3.14.C.1
~
, FIRE DETECTORS Detector Type /
Minimum Detectors Location Desionation(l)
Ooerable UNIT 2 Primary Containment (2) (3)
S1,'S2, S8 3
CRD Area (135') Rms. 208, 209, S7A, S8A, S9A,S10A 13 212 SilA,S12A,S13A,S14A S15A,S16A,517A,S18A S19A,S20A i
l Isol. Valve Compt. (13 5 ') Rm.204 S21A 1
Operating Area (165')Rm.402,403 S31A,S32A,S33A,S34A 12 S35A,S36A,S37A,S38A S39A,S40A,S41A,S42A S43A Laydown Area (195 ') Rm. 501,502 S45A,S46A,S47A,S48A 7
508 S49A,S50A,S51A,S52A Vent. Equip. Ar ea (19 5 ' ) Rm. 50 6 S53A, S54A 2
Vent Stack Rad. Mon.-Refuel S58A, S59A 2
floor (234')
HPCI Room 573.
1 H5, H6, H7 (See 3.14.B.l.c)
ROIC Room S45, S46 2
Reactor Bldg. Sump Area S79 1
Core Spray Pump Rooms S41, S42, S43, S44 4
Vac. Breaker Area-Rm. 107,108 S91, S92, S9; 3
RHR Rooms Room 101 S30, S31, S32 3
Rcom 102 S33, S34, S35 3
Room 103 S36, S37, S38 3
j Room 104 S39, S40 2
Torus Area S83,S84,S85,S86 7
S87,588,S89,590 M-G Set Lube Oil Rm (Rm 105)
S94,S95,S96,S97,S98 4
l
-240m-Amendment No. 39, $3, SJ,96
TABLE 3.14.C.1 FIRE DETECTORS Detector Tvne/
Minimum Detectorn
!,oca t i on De s i ema ti on ( 1 )
Onorable Pacire. Pumn MC Set Room S15. S16, S17 5
SIR, S19, S20 Emerq. Switchqear Rooms Sll, 512, S13, S14 4
Batterv Roomo Room 214 570, S71 2
Poem 225 S68, S60 2
13KV Switchgear Area (116')
S72, S73, S74 3
FPSt' pumn Room S390 1
II'TT'P 'l Primary containment (2)(3)
S103, S104, S106 3
cRD Aros (139') nms. 250 S166,S167,SIG8,5169 13 257, ?57 S170,S171,S172,S173 S174,S175,S17G,S177 S178,S179 I
Tool. Valve romnt.
S191 1
(135') Rm 244 Onerating Area. (1G5')
51G2, SIR 1,S184,5195 12 Rm, 443, 444 S186,9187,5199, Sing S100,5191,S192,S193 S194 T,avdown Area (145')
S196,S197,S198,S190 7
9m. 517, 918, 923 5103A,S104A,S105A,5106A Vant. Enuip Area (195')
S107A, S103A 2
Rm. 570 U.rnt Stack nad. Mon.-Refuel S109A, S110A 2
floor ~?]4')
HPCI Room S14R-1 I!115, 14116, 11117 (See 3.14.n.1.c)
RCIC Room Sill, 5132 2
Reactor nl.dg. Sump Area S149
~1
-740n-Amendment No. M, $3, 25, 96
PRAPS 6.13 Hich Radiation Area t
l 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20:
a.
Each High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a 7
)
Radiation Work Permit.
Any individual or group of individuals permitted to enter such areas chall be I-provided with or accompanied by one or more of the following:
i 1.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
2.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry.into auch areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
3.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over~ activities within the area and shall perform periodic radiation surveillance at the frequency specified by the plant Health Physicist or his designee on the Radiation Work Permit, b.
Each High Radiation Area in which the intensity of radiation is greater.than 1000 mrem /hr shall be subject to the provisions of 6.13.1 (a) above., In-addition, locked-doors shall be provided to prevent unauthorized entry into such areas ~and the keys shall be maintained under the administrative control of the Shift Superintendent, the Shift Supervisor or the_5enior Health Physicist.
-262-Amendment No. #, A7, 96 l
d'sgo crowD o
UNITED STATES
, !V
'i NUCLEAR REGULATORY COMMISSIOl'J WASHINGTON, D. C. 20555 p*
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 N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia E~iectric Company, et al.
(the licensee) dated March 11, 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 (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; 1
D.
The issuance of this license amendment will not be ininical 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 paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
g v
_2-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98 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.
i FOR THE NUCLEAR REGULATORY COMMISSION l
Jo n F. Stolz, Chief, s0/eratingReactorsBranch#4 Division of Licensing
Attachment:
Changes to the Technical Specifications l
Date of Issuance: March ' 2,1984 8
i t
4 i
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~
ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-56 4
DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment nunber and contain a vertical -line indicating the area of change.
Renove Insert 4
4 67 67 240m 240m 240n.
240n 262 262 4
w l
l 1
4 d
1
..-r
PBAPS 1.0 DEFINITIONS (cont'd).
component, or device to perform its function are also capable of performing their related support function.
Operating - Operating means that a system or component is performing its intended functions in.its required manner.
Ocerating Cycle - Interval between the end of one refueling outage for a particular unit and the end of the next subsequent refueling outage for the same unit.
Primary Containment Integrity - Primary containment integritf means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:
1.
All primary containment penetrations required to be closed during accident conditions are either:
a) u.pable of being closed by an OPERABLE containment automatic isolation valve system, or b)
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as may be provided in Specifications 3.7.D.2 and 4.7.D.2.
Manual valves may be opened to perform necessary operational activities.
2.
At least one door in each airlock is closed and sealed.
3.
All blind flanges and manways are closed.
Protective Action - An action initiated by the protection system when a limit is reached.
A protective action can be at a channel or system level.
Protective Function - A system protective action which results from tne protective action of the channels monitoring a particular plant condition.
Rated Power - Rated power refers to operation at.a reactor power of 3,293 MWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license.
Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.
1
! Amendment No. 37, $$, 7$,. 98
Y..
E
-TABLE 3.2.B (cot 1TINUED) 5 S
It1STIMIM5',!1TATION TIIAT It!ITIATES OR CO!1TROLS Tile CORE At3D cot 1TAlt1 met 1T z
. COOLING SYSTEMS w.
Minimum rio.
2d Of Operable Number of Instro-e Instrument Trip Function Trip Level Setting ment Channels Pro-Remarks Channels Per vided by Design Trip Systum(l) 2 Core Spray Pump 6 1 1 sec 4 timers In conjunction with loss Start Timer 10 i 1 sec 4 timers of power initiates the starting of CSCS pumps.
2 LPCI Pump Start Timer 5 i 1 sec 4 timers (Two Pumps) 1 Auto Blowdown Timer 90 $ t i 120 2 timers In conjunction with Low Reactor Water Level, e
liigh D'rywell Pressure and LPCI or Core Spray i
Pump running interlock, i
initiates Auto Blowdown.
2 RilR (LPCI) Pump 50 + 10 psig 4 channels Defers ADS actuation Discharge Pressure pending confirmation of Interlock Low Pressure Core Cooling system operation (LPCI Pump running interlock.)
j 2
Core Spray Pump 185 1 10 psig 4 channels Defers ADS actuation,
Discharge Pressure pending confirmation of Interlock Low Pressure core Cooling system operation (Core Spray Pnmp running interlock.)
l 1
l
TABLE 3.14.C.1 FIRE DETECTORS Detector Type /
Minimum Detectors Location Desionationfl)
Ooerable 4
UMIT 2 Primary Containment (2) (3)
S1,'S2, S8 3
CRD Area (135') Rms. 208, 209, S7A, S8A, S9A,S10A 13 212 S11A,S12A,S13A,S14A S15A,S16A,S17A,S18A S19A,S20A I
Isol. Valve Compt.(135')Rm.204 S21A 1
l Operating Area (165') Rm.402,403 S31A,S32A,S33A,S34A 12 j
S35A,S36A,S37A,S38A i
539A,S40A,S41A,S42A l
S43A l
i Laydown Area (195')Rm.501,502 S45A,S46A,S47A,348A 7
i 508 S49A,550A,S51A,S52A Vent. Equip. Area (195')Rm.506 553A, S54A 2
Vent Stack Rad. Mon.-Refuel S58A, S59A 2
floor (234')
HPCI Room S78 1
H5, H6, H7 (See 3.14.B.l.c)
RCIC Room S45, S46 2
Reactor Bldg. Sump Area S79 1
+
Core Spray Pump Rooms S41, S42, S43, S44 4
Vac. Breaker Area-Rm. 107,108 591, S92, S93 3
RHR Rooms Room 101 S30, S31, S32 3
Room 102 S33, 534, S35
'3 Room 103 S36, S37, 538 3
Room 104 S39, S40 2
Torus Area S83,S84,585,S86 7
587,S88,S89,S90 M-G Set Lube Oil Rm (Rm 105)
S94,S95,S96,S97,S98 4'
-240m-Amendment No. M, $2, EA, 98
Tabl e 3.T4.C.1
~
FIRE DETECTORS Detector Tvoe/
Mininum Detectort
!.ccation Desinna tion ( 1 )
Ooerable
?.acire. Pump MC Set Room S15 S16, S17 5
4 SIR, S19, S20 i'm ?rg Switchgear Rooms Sll, S12, S13, 514 4
9atterv Room.7 noom 21Q S70, S71 2
Poem 229 568,-S69 2
13KV Switchgear Area (116')
S72, S73, S74 3
ripsis Punn Room 5390 1
pw;m 3 Prinary containment (2)(3)
S103, S104, 5106 3
"nD Area (139') Rms. 250 S166,S167,SIG9,SIG9 13 137, ?97 S170,S171,S172,S173 S174,S175,S17G,S177 S178,S179 T9ol. Valve Comnt.
S191 1
( 13 5 ' ) Rm 249 0,erating Area (165')
S102,SIA1,S194,S195 1?
Rm. 443, 444 S186,5107,S199,S109 S190,5191,5192,S193 S194
!. ave.own Area (145')
S196,S197,S198,S199 7
7n. 517, 518, 523 S103A,5104A,S105A,S106A vant. Enuip Area (195')
S107A, S103A 2
R:n. 970 Vant Stack Rad. Mon.-Refuel S109A, S110A 2
floor (?34')
HPCI Room F149 1_
!!115, Ifl 16, 11117 -
(see 3.14.n.1.c)
RCIC Room
'S131,-S132 2
2an: tor 91dq.
- c. ump Area S149 1
-740n-Amendment No. 39, $/, 5A,98
P3APS
' 6.13 Hich Radiation Area-l 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20:
a.
Each High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance 4
thereto shall be controlled by issuance of a Radiation Work Permit.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
i 1.
A radiation monitoring device which c'ontinuously indicates the radiation dose rate l
in the area.
2.
A radiation monitoring' device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated _ dose is received.
Entry into such areas with this monitoring device may be made i
after the dose rate levels in the area have been established and personnel'have been made knowledgeable of them.
3.
An individual cualified in radiation-protection procedures who is equipped with a radiation dose rate monitoring device.
.This individual shall be responsible for providing positive control over activities'within the area and shall' perform periodic radiation surveillance at the frequency specified by the
-plant Health Physicist or his designee on-the Radiation Work Permit.
b.
Each High Radiation Area in which the intensity of i
radiation is' greater than 1000 mrem /hr shall be subject to the provisions of 6.13.1 (a) above.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Superintendent, the Shift Supervisor or the Senior. Health Physicist.
l I
-262-Amendment No. 39, A7, 98 i
,.