ML19345H629
| ML19345H629 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/15/1981 |
| 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 | |
| ML19345H630 | List: |
| References | |
| DPR-44-A-078, DPR-56-A-077 NUDOCS 8105210484 | |
| Download: ML19345H629 (34) | |
Text
'3 ! :.3}[g}(?7., MU[i lNd.$h h v.-
I s
pp C.g(
NUCLEAR REGULA
$350000004
-mmysm v.
,g DOCKET IW. 90-U 7 l
FiACH BOTTOM ATOMIC poler 17A 00N. UNIT 110. I AMENDKNT TO FACILITY OPitAT!WE LICDISE Amendment No. 78 License lie. BPR-44 1.
The Nuclear Regulatory Commission (the Commission) sias found 'that:
The a A.
al. (pplication for ameMment by Philadelphia Electric Company, et the licensee) dated January 9,1981, complies with the standards and requirements of the Atomic Ene Act of 1954, as amended (the Act), and the Commission's rules regulations set forth in )$ 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 (11) 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; and g
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 e
and paragraph 2.C.(2) of Facility Operating License No. WR-44 is j
hereby amended to read as follows:
Technical Specifications I
The Technical Specifications contained in A?pendices A and B, as revised through Amendment No.78, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
j l
8105210 N
~
2-i 3.
This license amendment is effective as~ of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0ft11SSION oh 7. Stolz, Chief ating Reactors Branch #4 Division of Licensing l
Attachment:
Changes to the Technical t
Specifications Date of Issuance: May 15,1981 i
I O
e
._,_.,_..~,-_,,-.~,,v__,-..,__,%.,_.w,,
m...
,..m.,,,
_4
.,w,,..,
m,-__...,...,...,~,.,_,,,_.,y.,.-,.
.,,,,y
,_.. _ - ~ _,
..,__,,,..n,
o
-.=
1 ATTACHMENT TO LICENSE AMENDMENT NO. 78 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 vertical lines indicating the area of change.
Remove Pages Insert Pam 9
9 9a j
10 10 11 11 11a 37-37 40 40 73 73 74 74 133a 133a 133c 133c
'148 148 o
149 149 160 160 1
4 e
g
+-w-
,-.,.e
,-,.w,._.,.t,,_
~
PBAPS Unit 2 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY 1
Applicability:
Applicability:
The Safety Limits established The Limiting Safety System Settingk to preserve the fuel cladding apply to trip settings of the instru-4 integrity apply to those ments and devices which are provided.
variables which monitor the to prevent the fuel cladding integrity fuel thermal behavior.
Safety Limits from being exceeded.
Obiectives:
Obiectives:
The objective of the Safety The objective of the Limiting Safety Limits is to establish limits System Settings is to define the level i
which assure the integrity of of the process variables at which auto-the fuel cladding.
matic protective action is initiated to prevent the fuel cladding integrity Safety Limits from being exceeded.
Specification:
Specification:
The limiting safety system settings shall be as specified below:
A. Reactor pressure k800 psia A.
Neutron Flux Scram and Core Flow k10% of Rated The existence of a minimum 1.
APRM Flux Scram Trip Settino critical power ratio MCPR less (Run Mode) than 1.07 for two recirculation loop operation, or 1.08 When the Mode Switch is in the for single loop operation, RUN position, the APRM flux shall constitute violation scram trip setting shall be of the fuel cladding integrity safety limit.
S.S 0.66W +54%-0.66 AW f
To ensure that this safety where:
limit is not exceeded, neutron flux shall not be above the S = Setting in percent of scram setting established in rated thermal power specification 2.1.A for (3293 MWt) longer than 1.15 seconds as indicated by the process com-W = Loop recirculation flow puter. When the process computer rate in percent of rated is out of service this (rated loop recirculation safety limit shall be assumed flow rate equals 34.2 x 108 to be exceeded if the neutron Ib/hr).
flux exceeds its scram setting and a control rod scram does not occur.
2 Amendment No.,,W, ) (, g M 70
_9
PBAPS Unit 2
SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY AW = Difference between two loop and single Icop effective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting
(-0.66 AW)) is accomplished by correcting the flow input of the flow biased scram to preserve the original (two loop) relationship betwee.1 APRM scram setpoint and recirculation drive flow or by adjusting the APPJi flux trip setting.
AW = 0 for two loop operation.
i t
Amendment tio. 78
-9a-
~ _ - _ _.. _.. _ _ _
_ -..,. ~..... _. _.. _.
~.
py,
-s..
4 PRAPS Unit 2 4
MArETY LIMIT LIMITING SAFETY SYSTEM SETTING i
2.1.A (Cont'd)
In the event of operation with i
a maximum fraction of limiting i
power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows.
S 1 (0.66 W + 54% -0.66 AW) ( FRP
)
- where, FRP = fraction of rated thermal power (3293 MWt) j i
MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all 8x8 fuel.
The ratio of FRP to MFLPD shall be. set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
2.
APRM--When the reactor mode '
switch is in the STARTUP position, the APRM scram shall be set at less than or equal to 15 percent of rated power.
3.
IRM--The IRM scram shall be set at less-than or equal to 120/125 of full scale.
4.
When the reactor mode switch is in the STARTUP or RUN position, the reactor shall not be operated in the natural circulation flow mode.
1 l
Amendment No.,M; 34~. X.,M. N.,#, 78 l
~
PBAPS Unit 2 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING B. Core Thermal Power Limit B.
APRM Rod Block Trio Settinc (Reactor Pressure 5 800 osia)
SRB 5 0.66 W + 42% - 0.66 AW When the reactor pressure is 5 800 psia or core flow is where less than 10% of rated, the core thermal power shall not SRB =
Rod block setting in exceed 25% of rated thermal percent of rated thermal power.
power (3293 MWt)
Loop recirculation flow W
=
rate in percent of design W is 100 for core flow of 102.5 million Ib/hr or greater.
difference between two AW
=
loop and single loop effective recirculation drive flow at the same core flow.
During single loop operation, the reduc-tion in trip setting
(-0.66 AW) is accom-plished by correcting the flow input of the flow biased rod block to preserve the original (two loop) relationship between APRM Rod block setpoint and recircu- -
lation drive flow or by adjusting the APRM Rod Block trip setting.
l AW = 0 for two loop operation.
I In the event of operation with l
maximum fraction limiting
(
power density (MFLPD) greater than the fraction of rated power (FRP); the setting shall be modified as follows.
~ Amendment No. g, )<", g jg,p 78
~
PBAPS Unit 2 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING B. Core Thermal Power Limit P,.
APRM Rod Block Trio Setting (Reactor Pressure 5 800 osia)
SRB S(0.66 W + 42%- 0.66 AW) (FRP)
MFLPD where:
FRP = fraction of rated thermal power (3293 MWt).
MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all 8x8 fuel The ratio of FRP to MFLPD snall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
C. Whenever the reactor is in the C.
Scram and isolation--2538 in, above shutdown condition with reactor low water vessel zero irradiated fuel in the reactor level (0" on level vessel, the water level shall instruments) not be less than 17.1 in. above the top of the normal active fuel zone.
l l
I l
l l
t l
1
-11a-Amendment No. 78
o-TABLE 3.1.1 h
REACTCSt PROTECTION SYSTEM (SCRAM) INSTRONENTATICN REQUIREMENT En 5
Hielmuse No.
Modes in Which Norrber of k of Operable Function Must be Instrument In3trument Trip Level Cperable.$
Channels Action'
% Channels Trip Funct. ion Settin9 Provided (1) per Trip Refuel Startup Run Dy Design Eyctem (1)
(7) 1 Mode Switch In X
X A
1 Mode Switch A
Shutdown (4 Sections) y o>
1 Manual Scram X
X X
2 Instrument A
Channels 3
IRM High Flux 5120/125 of Full X
X (5) 8 Instrument A
Scale Cnannels e
3 IRM Inoperative X
X (5) 8 Instrument A
g Chsnnels 2
APRM Iligh Flux
(. 66W
- 54 -0. 6 66W)
X 6 Irstrument A or B FRP/MFLPD Chann01s (12) (13) 2 APRM Inoperative (11)
X X
X 6 Instrument A or B Channels 2
APRM D'ownscale 22.5 Indicated (10; 6 Instrument A or D on Scale
.Cnannels C
2 APHr1Iligh Flux
$15% Power X
X 6 Instrument A
E in startup Cnarwtels ro 2
High Heactor
$1055 psig X (9)
X X
4 Instrument A
Pressure Channala 2
High Drywell
$2 psig X (8)
X (8)
X 4 Instrument A
Pressure Channels 2
Reactor Low
. 20 in. Indicated X
X X
81 Instrument A
Water Level Leve1 Channels
PBAPS' Unit 3 1'
NOTES FOR TABLE 3.1.1 (Cont'd)
(
10.
The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not high.
i 11.
An APRM will be considered operable if there are at least 2 LPRM inputs per level and at least 14 LPRM inputs of the normal complement.
12.
This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater j
than the fraction of rated power (FRP), where:
FRP = fraction of rated thermal power-(3293 MWt).
MFLPD =
maximum fraction of limiting power density where the limiting power density is 18.5 KW/ft for all 7x7 fuel and 13.4 KW/ft for all 8x8-fuel.
9 The ratio of FRP to MFLPD shall be set equal to 1.0-unless the actual operating value is less than the design value of 1.0, in which case the. actual operating value will be used.
W=
Loop Recirculation flow in percent of design.
W is 100 for core flow of 102.5 million Ib/hr or greater.
26 W=
the difference between two loop and single loop effective recirculation drive flow rate at the same core flow.
During single loop operation, the reduction in trip setting (-0.666W) is accomplished l
by correcting the flow input of the flow biased High Flux trip setting to preserve the original (two loop) relationship between APRM High Flux setpoint and recirculation drive flow or by adjusting the APRM Flux
('
trip setting.
W = 0 for two loop operation.
Trip level setting is in percent of rated power (3293 MWt).
13.
See Section 2.1.A.1.
l 1
I s Amendment No. XX, K, 77 L........
1
~.
1 iq{.
lJi.
16 4
s TABLE 3.2.C g
INSTFUMENTATION THAT INITIATES CCNTHOL ROD BLOCMS Minimum Mo.
Instrument Trip Level Setting flureber of Instrument ~
Action 5
of operable Channels Provided j
Instrument Channels Per by Design Trip System 2
APRM Upscale. (Flow
$ (0.66W e 4 2-0. 66AW) x 6 Inst. Channels (1)
I Biased)
._EEP i
MFLPD (2) 2 APRM Upscale (Star tup
$127, 6 Inst. Channels (1)
Mode) h 2
APRM cownscale 22 5 indicated on 6 Inst. Channels (1) scale u
1 (7)
Hod Elock Monitor
$ (0. 66W+ 41 -0.6 6AW) x 2 Inst. Channels (1)
(Flow Biased)
,,_[RP MFLPDF (2) 1 (7)
Hod Block Monitor 22.5 indicated on 2 Inst. Channels (1) l Downscale scale t'
3 IRM ccwnscale (3) 22 5 inoicated on 8 Inst. Channels (1) scale 3
IRM cetector not in (C) 8 Inst. Channels (1) 4 Startup Position 1
F 3
'IRM Upscale
$108 indicated on 8 Inat. Channels (1) scale N
2 (5)
SRM Uetector not in (4) 4 inst. Channels (1) i Startup Position 2 (S) ( 6)
SkM upscale
$105 counts /sec.
4 Inst. Channels (1)
~
PBAPS Unit 2 NOTES FOR TABLE 3.2.C 1.
For the startup and run positions of the Reactor Mode.
Selector Switch, there shall be two operable or tripped trip systems for each function.
The SRM and IRM blocks need not be operable in "Run" mode, and the APRM and RBH rod blocks need not be operable in "Startup" mode.
If the first column cannot be met for one of the two trip systems, this condition may exist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped.
If the first column cannot ce met for both trip systems, the systams shall be tripped.
2.
This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of ra.ted power (FRP) where:
FRP = fraction of rated thermal power (3293 MWt}
maximum fraction of limiting power density where MFLPD
=.
the limiting power density is 13.4 KW/ft for all 8x8 fuel.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
W=
Loop Recirculation flow in percent of design.
W is 100 for core flow of 102.5 million Ib/hr or greater.
Trip level setting is in percent of rated power (3293 MWt).
21W is the difference between two loop and single loop effective recirculation drive flow rate at the same core flow.
During single loop operation, the reduction in trip setting (-0.66A W) is accomplished by correcting the flow input of the flow biased Rod Block Monitor (RBM) to preserve the original (two loop) relationship between the RBM setpoint and recirculation, drive flow, or by adjusting the RAN setting.
W = 0 for two loop operation.
3.
IRM downscale is bypassed when it is on its lowest range.
4.
This function is bypassed when the count rate is 2 100 cps.
S.
One of the four SRM inputs may be bypassed.
6.
This SRM function is bypassed when the IRM range switches are on range 8 or above.
7.
The trip is bypassed when the reactor power is $ 30%.
8.
This function is bypassed when the mode switch is p' aced in Run.
AmendmentNo.)f,Aff,)6778 --,_
y
-,,.-...,r
,,r,r--,
m
-,.__m,._
,___.y__.
--.y 2
PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.I Averaoe Planar LHGR 4.5.I Averace Planar LHGR During power operation, the APLHGR The APLHGR for each type of fuel for each type of fuel as a function as a function of average planar of average planar exposure shall not exposure shall be checked daily exceed the limiting value shown in during reactor operation at Figure 3.5.1.C, D, F, G, H, and I 125% rated thermal power.
as applicable during two recirculation loop operation.
During single loop operation, the APLHGR for each fuel type shall not exceed the above values multipled by the following reduction factors: 0.82 for 8X8 fuel; 0.79 for LTA: 0.80 for 8X8R, and P8X8R fuel.
If at any time during operation it is determined by normal surveillance that the limiting value of APLHGR is being exceeded, action shall be initiated within one (1) hour to restore APLHGR to within 1
prescribed limits.
If the APLHGR is not returned to within prescribed limits within five (5) hours reactor power shall be decreased at a rate which would bring the reactor to the i
cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless APLHGR is returned to within limits during this period.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
3.5.J Local LHGR 4.5.J Local LHGR During power operation, the linear The LHGR as a function of core heat generation rate (LHGR) of height shall be checked daily any rod in any fuel assembly at during reactor operation at any axial location shall not exceed 125% rated thermal power.
the design LNGR.
LHGR $ LHGRd LHGRd = Design LHGR 13.4 Kw/ft for all 8X8 fuel.
i f
-133a-Amendment No. g,f s, X 78 i
-- ~
- \\
i PBAPS Unit 2 Table 3.5-2 OPERAT"NG LIMIT MCPR VALUES AS DETERMINED FROM INDICA"ED TRANSIENTS FOR VARIOUS CORE EXPOSURES MCPR Operating Limit
- l Fuel Type For Incremental Cycle 5 Core Averace Exposure BOC to 1000 MWD /t 1000 MWD /t before EOC Before EOC To EOC 8x8 1.28 1.28 8x8R & LTA 1.28 1.28 P0x8R 1.30 1.-30 4
These values shall be increased by 0.01 for Single Loop Operati'on t
Amendnent No.)&;Jrl78
-133c-
~
PBAPS Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps 4.6.E Jet Pumps
- 1. Whenever the reactor is in 1.
Whenever there is recirculation the startup or run modes, flow with the reacter in the all jet pumps shall be startup or run modes jet operable. If it is determined pumpoperabilitysee.11be that a jet pump is inoperable, checked daily by verifying an orderly shutdown shall be that the following i
initiated and the reactor shall conditions do not occur be in a Cold Shutdown within simultaneously:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2) Flow indications from each of a)
The two recirculation loops have the 20 jet pumps during two a flow imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single loop operation operated at the same speed.
shall be verified prior to initiation of reactor startup b)
The indicated value of core flow from a cold shutdown condition.
rate varies from the value derided from loop flow measure-
- 3) The indicated core flow is the ments by more than 10%.
4 sum of the flow indication j
from each of the 20 jet pumps.
c)
The diffuser to lower plenum If flow indication failure differential pressure reading j
occurs for two or more jet on an individual jet pump puups immediate corrective varies from the mean of all
]
action shall be taken. If jet pump differential pressures flow indication for all but by more than 10%.
l 1 jet pump cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an orderly.
2.
Additionally when operating with shutdown shall be initiated, one recirculation pump with and the reactor shall be in the equalizer valves closed, the i
cold shutdowr' condition withia diffuser to lower plenum l
t 2$ hours.
differential pressure shall be
[
checked daily and the differential pressure of any jet pump in thw idle loop shall not vary by more than 10% from established i
pattern.
l 3.
The baseline data required to evaluate the conditions in i
specification 4.6.E.1 and i
4.6.E.2 will be obtained each operating-cycle.
1 i
(
1
-148-I Amendment No. X,* J f, 78 l
f PBAPS Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F Recirculation Pumps 3.6.F Recirculation Pumps
- 1. Following one-pump operation, the discharge valve of the i
low speed pump may not be opened unless the speed of the faster pump is less than 50% of its rated speed.
- 2. The requirements applicable to i
l single loop operation as identified in sections 1.1.A, 2.1.A, 2.1.B, 3.5.I & 3.5.K shall be in effect within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the removal of one recirculation loop from service, or the unit placed in the Hot Shutdown condition.
3.6.G Structural Integrity 4.6.G Structural Integrity 1
)
The nondestructive inspections J
The structural integrity of the primary system listed in Table 4.6.1 shall j
boundary shall be maintained be performed as specified.
at the level required by the The results obtained from j
original acceptance standards compliance with the
{
throughout the life of specification will be the station. The reactor shall evaluated after 5 years be maintained in a Cold and the conclusions of this i
Shutdmm condition until evaluation will be reviewed i
each indication of a with the hRC.
defect has been investi-gated and evaluated.
I t
i Amendment No. M 78
-149-
Unit 2'
~
PBAPS 3.6.F & 4.6.F 3,AEEE, Jet Pqgit Flow Mismatch i
Requiring the discharge valve of the lower speed loop to remain closed until the speed of faster pump is below 50% of its rated speed provides assurance when going from one to two pump operation that excessive vibration of the jet pump risers will not occur.
Operation with one recirculation loop in service is permitted.
In such instances, the designated adjustments for APRM rod block and scram setpoints, RBM setpoint, MCPR fuel cladding integrity safety limit, MCPR operating limits, and MAPLHGR limits are raquired.
t
-160-Amendment No. E. 7g
~~
j u
UNITED STATES j
k NUCLEAR REGULATORY COMMISSION
(
WASHINGTON, D. C. 20666
\\.....
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECfRIC 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. 77
~
License No. DPR-56 1.
The fiuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 9,1981, 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; 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 condeted 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; 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. DPR-56 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 77, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specificatiorfs.
- - -, - + - - - - -. -. -, - -. - - -.. - - -. -, ~ -. - - - -,., - - -, - -. - - -,..
w n.
2-i 3.
This license amendwnt is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0tt11SSION ALL /
Jo r. F. Stolz, Chief erating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 15, 1981 6
8 4
e
-,-..m.----
w,----..~e
.s. -, -.
,er,,
.-r,,mem%,,w.,r+-
_,,.w.+.,._.,
.----w--*----,e--,-.wwv-e-wwm++
-y,.w g e n,,
.g'---*
' ' ' " " *~
ATTACHMENT TO LICENSE AMENDMENT NO. 77 FACILITY OPERATING LICENSE NO. DPR-56 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 number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 9
9 9a 10 10 11 Il lla 37 37 40 40 73 73 74 74 133a 133a 133c 133c,
148 148 4
149 I49 160 160 l
I g
e 4
4-
.-r
-n--
-v-w
-n
n.
=w,-- - ~ ~
w
~
~
PBAPS Unit 3 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Applicability:
Applicability:
The Safety Limits established The Limiting Safety System Settings to preserve the fuel cladding apply to trip settings of the instru-integrity apply to those ments and devices which are provided variables which monitor the to prevent the fuel cladding integrity fuel. thermal behavior.
Safety Limits from being exceeded.
Obiectives:
Obiectives:
The objective of the Safety The objective of the Limiting Safety Limits is to establish limits System Settings is to define the level which assure the integrity of of the process variables at which auto-the fuel cladding.
matic protective action is initiated to prevent the fuel cladding integrity Safety Limits from being exceeded.
Specification:
Specification:
The limiting safety system settings shall be as specified below:
A. Reactor pressure 2800 psia A.
Neutron Flux Scram and Core Flow 210% of Rated The existence of a minimum 1.
APRM Flux Scram Trio Settinc critical power ratio MCPR less (Run Mode) than 1.07 for two recirculation loop operation, or 1.08 When the Mode Switch is in the for single loop operation, RUN position, the APRM flux shall constitute violation scram trip setting shall be:
of the fuel cladding integrity safety limit.
S.$ 0.66W +54%-0.66 AW l
To ensure that this safety
~ where:
limit is r.ot exceeded, neutron flux shall not be above the S = Setting-in percent of scram setting established in rated thermal power specification 2.1.A for (3293 MWt) longer than 1.15 seconds as indicated by the process com-W = Loop recirculation flow puter. When the process computer rate in percent of rated is out of service this (rated loop recirculation safety limit shall be assumed flow rate equals 34.2 x 10*
to be exceeded if the neutron Ib/hr).
flux exceeds its scram setting j
and a control rod scram does not occur.
Amendment No. X, M 77 l
.3
PBAPS Unit 3 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY AW = Difference between two loop and single loop effective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting
(-0.66 AW)) is accomplished by correcting the flow input of the flow biased scram to preserve the original (two loop) relationship between APRM scram setpoint and recirculation drive flow or by adjusting the APRM flux trip setting.
AW = 0 for two loop operation.
t l
i t
Amehdment tio. 77
-9 * '
W D
r PBAPS INIT 3 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 2.1.A (Cont'd)
In the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows.
S $ (0.66 W + 54% -0.66 AW) ( FRP MFLPD
- where, FRP = fraction of rated thermal power (3293 MWt)
MFLPD = maximum fraction of limiting power density where the limiting power density is 18.5 MW/ft for all 7X7 fuel and 13.4 KW/ft for all 8X8 fuel.
f The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
2.
APRM--When the reactor mode switch is in the STARTUP position, the APRM scram shall be set at less than or equal to 15 percent of rated power.
j 3.
IRM--The IRM scram shall be set at less than or equal to i
120/125 of full scale.
I 4.
When the reactor mode switch is in the STARTUP or RUN position, the reactor shall not be operated in the natural circulation flow mode.
Amendnent No.M)K AI,g 77.
.w
.w.,
... _.,.. _ ~,,,., _.,..
,m
,.y-,
e, et i
I PBAPS Unit 3
SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING B. Core Thermal Power Limit B.
APRM Rod Block Trip Setting (Reactor Pressure 5 800 psia)
SRB $ 0.66 W + 42% - 0.66 AW When the reactor pressure is 5 800 psia or core flow is where less than 30% of rated, the core thermal power shall not SRB =
Rod block setting in exceed 25% of rated thermal percent of rated thermal power.
power (3293 MWt)
Loop recirculation flow W
=
rate in percent of design W is 100 for core flow of 102.5 million Ib/hr or greater.
difference between two AW
=
loop and single loop effective recirculation drive flow at the same core flow.
During single loop operation, the reduc-tion in trip setting
(-0.66 AW) is accom-plished by correcting the flow input of the flow biased rod block to preserve the original (two loop) relationship between APRM Rod block setpoint and recircu -
lation drive flow or by adjusting the APRM Rod Block trip setting.
aW = 0 for two loop operation.
In the event of operation with maximum fraction limiting power density (MFLPD) greater than the fraction of rated power (FRP); the setting shall be modified as follows.
l I
Amendnent No. X, J5, M,M 77
'_ij_
--,,v...
...-m,_
PBAPS Unit 3 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING B. Core Thermal Power Limit B.
APRM Rod Block Trip Settina-(Reactor Pressure 5 800 psia)
SRB <(0.66 W + 42%- 0.66 AW) (FRP)
MFLPD where:
FRP = traction of rated thermal power (3293 MWt).
MFLPD = maximum fraction of limiting power density where the limiting power density is 18.5 KW/ft for all 7x7 fuel and 13.4 KW/ft for all 8x8 fuel The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
C. Whenever the reactor is in the C.
Scram and isolation--2538 in. above shutdown condition with reactor low water vessel zero irradiated fuel in the reactor level (0" on level vesse.', the water level shall instruments) not be less than 17.1 in. above the top of the normal active fuel zone.
1 e
-11a-Amendment No. 77
d i
i TABLE 3.1.1
{
li s
REACTCR PROTECTION SYSTEM (SCRAM) INSTHUMEllTATICN REQUIREMENT
~@
$re Modes in which Hunber of
'[ Hinimum No.
Function Must be Instrument of Operable Instrument Trip Level Cpgrable Channels Action L Channels Trip Function Setting Provided (1)
Retuel Startup Run Dy Design 1% per Trip (7)
System (1 )
} 2j 1
i 1
Mode Switch In X
X X
1 Mode Switch A
Shutdown (4 Sections) i 1
X X
2 Instrument A
Channels 3
IHM High Flux
$120/125 of Full X
X (5) 8 Instrument A
Scale Cnannels i
i s
3 IRM Inoperative X
X (5) 8 Instrument A
Channels w
2 APRM liigh Flux
(.66W*54-0.666W)
X 6 Instrument A or B i
FRP/MFLPD Channels l
(12) (13) i 2
APRM Incperative (11)
X X
X 6 Instrument A or B Channels 2
APHM Downscale 22.5 Indicated (10; 6 Instrument A or B I.
on Scale Cnannels c:1 2
APHM liigh Flux
$15% Power X
X 6 Instrument A
{
Cnannels in Startup 2
High Eeactor
$1055 psig X (9)
X X
4 Instrument A
Channels Pressure..
2 High Drywell
$2 psig X (8)
X (8)
X 4 Instrument A
Channels Pressure 2
Reactor Low 20 in. Indicated X
X X
4 Instrument A
Water Level Level Channels s
i.
=
e PBAPS Unit 3
~
NOTES,F,OR TABLE 3.1.1 (Cont'd)
\\
i 10.
The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not high..
11.
An APRM will be considered operable if there are at least 2 LPRM inputs per level and at least 14 LPRM inputs of the normal complement.
12.
This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), where FRP = fraction of rated thermal power (3293 MWt).
MFLPD =
maximum fraction of limiting power density where the limiting power density is 18.5 KW/ft for all 7x7 fuel and 13.4 KW/ft for all 8x8 fuel.
+
The ratio of FRP to MFLPD shall be set equal co 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
W=
Loop Recirculation flow in percent of design.
W is 100 for core flow of 102.5 million Ib/hr or greater.
LL W =
the difference between two loop and single loop i
effective recirculation drive flow rate at the same core flow.
During single loop operation, the reduction in trip setting.(-0.66AW) is accomplished by correcting the flow input of the flow biased High Flux trip setting to preserve the original (two loop) relationship between APRM High Flux setpoint and recirculation drive flow or by adjusting the APRM Flux trip setting.
W = 0 for two loop operation.
Trip level setting is in percent of rated power (3293 MWt).
13.
See Section 2.1.A.I.
i J
Amendment No. X X. g, 77 - - -... -
~y y,
L.
S.
TABLE 3.2.C g
m INSTFUMENTATION THAT INITI ATES CCNTHOL ROD BLOC 8S
. :s F
CL 5
Minimum No.
Instruisent Trip Level Setting
!1urnber of Instrument Action
! E+
cf operable Channels Provide <1 g
Instrument by Design Channels Per
! L Trip System
. '4' 2
APRM Upscale ~ (Flow
$ (0. 66W ' 4 2-0. 6 6AW) x 6 Inst. Channels (1)
{
Biased)
____ F N P _
d MFLPD (2)
I 2
APRM Upscale (Startup
$12 /,
6 Inst. Channels (1)
]
Mode) l i'
2 APRM Eownscale 22.5 indicated on 6 Inst. Channels (1) scale e
1 (7)
Hod Plock Monitor
$ (0. 66W + 41 -0. 6 6AW) x 2 Inst. Channels (1)
(Flow Biased)
_FRP 1
l MFLPD (2) l 1 (7)
Rod Block Monitor 22.5 indicated on 2 Inst. Channels (1)
Downscale scale f
3 IRM Ccunscale, (3) 12.5 indicated on 8 Inst. Channels (1) r scale 3
IRM Cetector not in (8) 8 Inst. Channels (1)
Startup Position 3
IRM Upscale
$108 indicated on 8 Inst. Channels (1) 9 scale w
2 (5)
SRM Detector not in (4) 4 Inst. Channels (1)
Startup Position 2 (5) ( 6) SkM Upscale
$105 counts /sec.
'4 Inst. Channels (1)
P
_73 f
f
I f
PBAPS Unit 3 NOTES FOR TABLE 3.2.C 1.
For the startup and run positions of the Reactor Mode Selector Switch, there shall be two operable or tripped trip systems,for each function.
The SRM and IRM blocks need not be operable in "Run" mode, and the APRM and RBM rod blocks need not be operable in " Stat tup" mode.
If the first column g
cannot be met for one of the t-v Luip systems, this condition may exist for up to seven days provided that I
during that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped.
If the first column cannot be met for both trip systems, the -
systems shall be tripped.
2.
This equation will be used in the event of. operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP) where:
FRP = fraction of rated thermal power (3293 MWt) maximum fraction of limiting power density where MFLPD
=
the limiting power density is 18.5 KW/ft for all 7x7 fuel and 13.4 KW/ft for all 8x8 fuel.
l The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of
- 1. 0, in which case the actual operating value will be used.
W=
Loop Recirculation flow in percent of design.
W is 100 for core flow of 102.5 million Ib/hr or greater.
Trip level setting is in percent of rated power (3293 MWt).
dsW is the difference between two loop and single loop effective recirculation drive flow rate at the same core flow.
Durinc single loop operation, the reduction in trip setting (-0.66 A W) is accomplished by correcting the flow input of the flow biased Rod Block Monitor (RBM) to preserve the original (two loop) relationship between the RBM setpoint and recirculation drive flow, or by adjusting the j
i RBM setting.
W = 0 for two loop operation.
3.'
IRH downscale is bypassed when it is on its lowest range.
4.
This function is bypassed when the count rate is 2 100 cps.
5.
One of the four SRM inputs may be bypassed.
1 4.
This SRM function is bypassed when the IRM range switches are on range 8 or above.
7.,
The trip is bypassed when the reactor power is 5 30%.
8.
This function is bypassed when the mode switch is placed in Run.
Amendment flo. E. M. EI.77 L
PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION-SURVEILLANCE REQUIREMENTS 3.5.I Averace Planar LHGR 4.5.I Averace Planar LHGR During power operation, the APLHGR The APLHGR for each type of fuel for each type of fuel as a function as a function of average planar of average planar exposure shall not exposure shall be checked daily exceed the limiting value shown in during reactor operation at Figure 3.5.1.A,B, C, D, F,G & H 125% rated thermal power as applicable during two recirculation loop operation.
During single loop operation, the APLHGR for each fuel type shall not exceed the above values multipled by the following reduction factors: 0.71 for 7X7 fuel; 0.83 for 8X8 fuel; 0.81 for PTA, 8X8R and P8X8R fuel.
If at any time during operation it is deter-mined by normal surveillance that the limiting value of APLHGR is being ex-ceeded, action shall be initiated within one (1) hour to restore APLHGR to within prescribed limits.
If the APLHGR is not returned to within pre-scribed limits within five (5) hours reactor power shall be decreased at a rate which would bring the reactor to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless APLEGR is returned to within limits during this period.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
3.5.J Local LHGR 4.5.J Local LHGR During power operation, the linear The LHGR as a function of core heat generation rate (LHGR) of height shall be checked daily any rod in any fuel assembly at during reactor operation at any axial location shall not exceed 225% rated thermal power.
the maximum allowable LHGR as calculated by the following equation:
LHGR < LHGRd (1-(AP/P) max (L/LT)
LHGRd'= Design LHGR
= 18.5 kW/ft for 7X7 fuel 13.4 kW/ft for all 8x8 fuel
( P/P) max = Maximum power spiking penalty
= 0.026 for 7x7 fuel
= 0.000 for 8x8 fuel LT = Total core length
= 12.167 ft for 7x7 & Ex8 fuel 12.5 ft for 8x8R, 8x8 PTA and P
=
8x8R fuel e
'L = Axial position above bottom of core
-133a Amondment lio. J% fM ftl 77.
~
PBAPS Unit 3 Table 3.5-2
/
OPERATING LIMIT MCPR VALUES AS DETERMINED FROM INDICATED TRANSIENTS FOR VARIOUS CORE EXPOSURES MCPR Operating Limit
- l Fuel Type
. For Incremental Cycle 4 Core Averace Exposure BOC to 2000 MWD /t 2000 MWD /t before EOC Pefore EOC To EOC 7x7 1.23 (LH) 1.23-(LR) 8x8 1.24 (LH) 1.30 (LR)
PTA & P 8x8R 1.27 (RWE)
'1.32 (LR) 8x8R 1.27 (RWE) 1.30 (LR)
RWE - Rod Withdrawal Error -
LR -
Load Rejection with failure of bypass valves to open LH Loss of 100 #F Feedwater Heating 1
i These values shall be increased by 0.01 for single loop operation.
f f
1 l
8 Amendment No. M #[, 77
-133c-
m o
d PBAPS Unit 3
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps 4.6.E Jet Pumps i
- 1. Whenever the reactor is in 1.
Whenever there is recirculation the startup or run modes, flow with the reactor in the all jet pumps shall be startup or run modes, jet operable. If it is determined pump operability shall be that a jet pump is inoperable, checked daily by verifying an orderly shutdown shall be that the following initiated and the reactor shall conditions do not occur be in a Cold Shutdown within simultaneously:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2) Flow indications from each of a)
The two recirculation loops have the 20 jet pumps during two a flow imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single loop operation operated at the same speed.
shall be verified prior to initiation of reactor startup b)
The indicated value of core flow from a cold shutdown condition.
rate varies from the value derived from loop flow measure-
- 3) The indicated core flow is the ments by more than 10%.
sum of the flow indication from each of the 20 jet pumps.
c)
The diffuser to lower plenum If flow indication failure differential pressure reading occurs for two or more jet on an individual jet pump-pumps immediate corrective varies from the mean of all action shall be taken. If jet pump differential pressures flow indication for all but by more than 10%.
1 jet pump cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an orderly 2.
Additionally when operacing with shutdown shall be initiated, one recirculation pump with and the reactor shall be in the equalizer valves closed, the cold shutdown condition within diffuser to lower plenum 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
differential pressure shall be checked daily and the differential pressure of any jet pump in the idle loop shall not vary by
}
more than 10% from established pattern.
3.
The baseline data required to evaluate the conditions in specification 4.6.E.1 and 4.6.E.2 will be obtained each operating cycle.
i 1
/
Amendment ia. X JY, 77
-148-c 1
~h l
1 PBAPS Unit' 3
j LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.F Recirculation Pumps 3.6.F Recirculation Pumps
- 1. Following one-pump operation, the discharge valve of the low speed pump may not be opened unless the speed of the faster pump-is less than 50% of its rated speed.
- 2. The requirements applicable to single loop operation as identified in sections 1.1.A, 2.1.A, 2.1.B, 3.5.I & 3.5.K shall be in effect within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the removal of one recirculation lcop from service, or the unit placed in the Hot Shutdown condition.
3.6.G Structural Integrity 4.6.G Structural Integrity The structural integrity The nondestructive inspections of the primary system listed in Table 4.6.1 shall boundary shall be maintained be performed as specified.
at the level required by,the The results obtained from original acceptance standards compliance with the throughout the life of specification will be the station. The reactor shall evaluated after 5 years be maintained in a Cold and the conclusions of this Shutdam condition until evaluation will be reviewed each indication of a with the NRC.
defect has been investi-gated and evaluated.
t i
i 1
4 t
3,. :
i Amendment No. X '77
-149-L
i e
I PBAPS Unit 3 3.6.T & 4.6.F BASES Jet Pump Flow Mismatch Requiring the discharge valve of the lower speed loop to remain closed until the speed of faster pump is below 50% of its rated speed provides assurance when going from one to two pump operation that excessive vibration of the jet pump risers will not occur.
Operation with one recirculation loop in service is permitted.
In such instances, the designated adjustments for APRH rod block and scram setpoints, RBM setpoint, MCPR fuel cladding integrity safety limit, MCPR operating limits, and MAPLHGR limits are required.
l
-160-Amendment No. X 77
" - " - - - ~ - <
w-
_