ML19338F526

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Proposed Tech Specs,Sections 3.0 & 4.0,incorporating Surveillance Requirements Re Scram Discharge Vol Valves & Limiting Conditions Re Reactor Protection Sys & Control Rod Block Limit Switches
ML19338F526
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 10/10/1980
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19338F516 List:
References
NUDOCS 8010200464
Download: ML19338F526 (9)
v • d • e


Text

UNIT 2 TABLE 4.1.1 (Cont'd)

GD g REACTOR PROTECTION SYSTE!! ( S CR A!!) INSTRUl!ENT FUNCTIONAL TESTS M

e  !!INIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS C

,y

.8=

c y CROUP (2) FUNCTIONAL TEST MINIMU:1 FREQUENCY (3)

High Unter Level in Scran A Trip Channel and Alara Every 1 month Discharge Tank Turbine Condenser Lou Vacuum (6) B2 Trip Channel and Alaru (4) Every 1 month (1)

Main S t eara Line lii gh RadiatLon El Trip Channel and Alarc: (4) Once/ week

'!ain Stcan Line Isolation A Trip Channel and Alar.a Every 1 tao n t h (1)

Valve Closure Turbine Control Valve A Trip Channel a a :1 A la r:a Every 1 conth EllC 011 Pressure Turbine First Stage Pressure A Trip Channel and Alarc Every 3 months (1)

Permissive Turbine Stop Valve Closure A Trip Channel and Alara Every 1 month (1)

Reactor Pressure Pernissive (6) B2 Trip Channel and Alarm (4) Every 3 months.

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UNIT 13-TABLE.4.'l.1-(Cont'd)

' REACTOR PROTECTION" SYSTEM-(SCRAM) INSTRUMENT-FUNCTIONAL TESTS MINIMU)! FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT At?D CONTROL CIRCUITS-

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CROUP (2) . FUNCTIONAL TEST HINIMUM FREQUENCY (3)

High Water Level in Scram A

Trip Channel and Alarm Every.l.conth

' Discharge Tank

. Turbine Condenser' Low: Vacuum.(6)'

B2 Trip Channel and Alarm (4). Every l' month (1)

.bain Steam-Line High Radiation B1 Trip Channel and Alarm (4) Once/ week.

!!ain' Steam Line : Isolation A Trip Channel and Alaru

, Valve-Closure. Every I conth (1)

LTurb'ine' Control Valve A Trip ~ Channel and Alarm Every 1 conth' EHC 0111 Pressure- ,

Turbine 'First.-Stage Pressure A Trip Channel and Alarm Every 3 months-(l)-

, ~ Permissive 1.

/ Turbine Stop Valve Closure A Trip Channel and Alarm 1 -.

Every 1 month (1)

{ '

  • R'e a c t o r Pressure Permissive (6)

B2 Trip Channel and Alarm (4) Every 3 months.

**Reac' tor Press'ure Permissive A Trip Channe1~and Alarm Every 3 months Deleted when modification authorized by Amendment No. 67 are cocpleted.

Effective when modifications authorized by-Amendment No. 67 are completed..

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TABLE 3.2.C INSTRUMEI;TATION TilAT INITIATES CONTROL ROD BLOCKS Mininum No. Instrument Trip Level Setting Number of Instrument Action of Operable Channels Provided Instrument by Design Channels Per' Trip System -

2 APR!! Upscale (Flow f(0.66W+42)x FRP 6 Inst. Channels (1)

Blased) MFLPD (2) 2 APR'! Upscale (Startup 112% 6 Inst. Channels (1)

Mode) 2 APRM Downscale >2.5 indicated on 6 Inst. Channels (1) scale 1 (7) Rod Block Monitor f(0.66W+41)x FRP 2 Inst. :hannels (1)

(Flow Biased)  !!FLPD (2) 1 (7) Rod Block Monitor ~

>2.5 indicated on 2 Inst. Channels (1)

Dounseale scale 3 IRM Downscale (3) >2.5 indicated on 8 Inst. Channels (1) scale 3 IRM Dete,ctor not in (8) 8 Inst. Channels (1)

Startup Position 3 IRM Upscale fl08 indicated on 8 Inst. Channels (1) scale 2 (5) SRif Detector not in (4) 4 Inst. Channels (1)

Startup Position 2 (3) (6) SRt! Upscale $10 5 counts /sec. 4 Inst. Channels (1) 1 Scram Discharge Vol u ra e f .2 5 gallons 1 Inst. Channel (9)

!!igh Level 2 .

UBIT 2 PBAPS i

NOTES FOR TABLE 3.2.C 2 1. For the startup and run positions of the Reactor Mode  ;

i 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 ar.d RBM 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 3

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 colum cannot j be met for both trip systems, the systems shall be tripped.

I 2. This equation will be used in the event of. operation with a maximum fraction of limiting power density (MFLPD) greater i than the fraction of rated power (FRP)'where:

{ FRP = fraction of rated thermal power (3293 MWt) i 4

MFLPD = maximum fraction of limiting power density where 4

j the limiting power density is 13.4 KW/ft for all 8x8 fuel.

1 The ratio of FRP to MFLPD shall be set equal to 1.0 unless i

the actual operating value is less than the design ~value of 1.0, in which case the actual operating value will be used.

f, 1 W= Loop Recirculation flow in percent of design. W is 100 A

for core flow of 102.5 million Ib/hr or greater.

Trip level setting is in percent of rated power (3293 MWt).

3. IRM downscale is bypassed when it is on its lowest range. k
4. t j This function.is bypassed when the count rate is > 100 cps. '

'4 l S. One.of the four SRM inputs may be bypassed.

l 6.

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i This SRM function is bypassed when the IRM range switches are  !

on range 8 or above. i 4 .

(

7.

The trip is bypassed when the reactor power is s 30%. I

8. This function.is bypassed when the mode switch is placed in l Run.
9. I If the number of operable channels is less than required by I the minimum operable per-trip function requirement, place the l

s-Inoperable channel in the tripped condition within one hour. i This note is saplicable in the "Run" mode, the "Startup" mode L i

and the " Refuel" mode if more than one control rod is withdrawn.

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UNIT 3 PBAPS 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 "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 chall 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:

FRF = 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 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).

3. IRM downscale is bypassed when it is on its lowest range.
4. This function is bypassed when the count rate is > 100 cps. ,
5. 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. L
7. The trip is bypassed when the reactor power is < 30%.
8. This function is bypassed when the mode switch is placed in i Run.  :

4

.9. If the number of' operable channels is than required by the

  • minimum operable' channels per trip function requirement,  ;

place the inoperable channel in the tripped condition within -

( one hour. This' note ic applicable in the "Run" mode, "Startup" mode and " Refuel" mode if more than one control rod is withdrawn.

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Tabic 4.2.C -

MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD BLOCKS ACTUATION Instruuent Channel Instrument Functional Calibration Instru=ent Test Check

1) APRM - Downscale (1) (3) Once/3 nonths Once/ day
2) APRM - Upscale (1) (3) Once/3 nonths Once/ day
3) 1RM - Upscale (2) (3) Startup or Control (2)

Shutdown

4) . IRM - Downscale (2) (3) Startup or Control (2)

Shutdown

5) RBM - Upscale (1) (3) Once/6 months once/ day
6) RBM - Downscale (1) (3) Once/6 months once/ day
7) SRM - Upscale (2) (3) Startup or Control (2)

Shutdown

8) S R M -- Detector Not in Startup (2) (3) Startup or Control (2)

Position Shutdown

9) IRM - Detector Not in Startup (2) (3) Startup or Control (2)

Position Shutdown

10) Scram Discharge Voluue - Quarterly Once/ Operating Cycle NA High Level Logic Systen Functional Test (4) (6) Frequency (1) System Logic Check once/6 months P il A P S 3.2 BAS,ES (Cont'd)

The APRM rod block function is flow biased and prevents a significan* reduction in !!CPR, especially during operation at reduced flow. The APRM provides gross core protection; i.e.,

limits the gross core power increase fron wi;hdrawal of control rods in the normal withdrawal sequences. The trips are set so that MCPR is maintained greater than the fuel cladding integrity safety limit.

The RBM rod block function provides local protection of the core; i.e., the prevention of boiling transition.in the local region of the core, for a single rod withdrawal error from a limiting control , rod pattern.'  ;

The IRM rod block function provides local as well as gross core  !

I protection. The scaling arrangement is such that trip setting is (

less than a factor of 10 above the indicated level.

t A downscale indication on an APRM or IRM is an indication the  ;

instrument han failed or the instrument is not sensitive enough. i in either case the instrument will not respond to changes in the '

control' rod motion and thus, control rod motion is prevented.

The downscale trips are set at 2.5 indicated on scale.

The flow comparator components have only one logic channel and are not required for safety. The flow comparator must be bypassed when operating with one recirculation water pump. 3 f

The refueling interlocks also operate one logic channel, and are [

' required for safety only when the mode switch is in the refueling position. l liigh water level-in the scram discharge volume nay be indicative t of excessive scram valve leakage, or plugging or closing of the. _g

' discharge. volume drain valve, and could jeopardize the a bility of-ull rods to fully insert on a scran signal.- L

- V For effective emergency core. cooling for small pipe breaks, the llPCI system must function since reactor pressure does not decrease rapidly enough to' allow either core spray or LPCI to operate in time. 'The automatic pressure relief function (ADS) is ,

'provided as a backup to the 11PC; in the event the IIPCI does not '

operate. The arrangement of the tripping contacts is such as to' i

-provide this function when necessary and-minimize spurious +

operation. 'The crip settings given in the. specification are '

adequate to assure'the above criteria are act. The specification i;

preserves.the effectiveness of the system during periods of maintenance, testing, or calibration, and also-minimizes ~ the risk l

offinadvertent' operation; i.e., only one instrument channel out l

of-service.

Two~ air ejector off gas monitors are provided and when their trip 1:

point line, is reached,'cause an. isolation'of the. air ejector off nas '

luolation is; initiated when both instruments reach their -

high trip point or one has.an upscale

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity Limitations 4.3.A Reactivity Limitations ICont'd) (Cont'd) failure is not due to a or partially withdrawn rod failed control rod drive which cannot be moved and for mechanism collet housing. which control rod drive mech-anism damage has not.been ruled out. The surveillance need not be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the number of inoperable rods

  • has been reduced to less than 3 and if it has been demonstrated that control rod drive mech-anism collet housing failure is 2

not the cause of an immovable control rod.

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b. The control rod directional b. The scram discharge volume control valves for inoper- drain and vent valves shall able control rods shall be be verified open at least e

j disarmed electrically and once per month. These j the control rods shall be valves may be closed  ;

in such positions that intermittently for testing.  ;

, Specification 3.3.A.1 is met. '

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c. Control rods with scram times c. At least once every 3 greater than those permitted months verify that the f by Specification 3.3.C.3 are scram discharge volume }

inoperable, but if they can drain and vent valves {

be inserted with control rod closed within 15 seconds drive pressure they need not after receipt of a closure be disarmed electrically. signal, and. reopen upon ,

j reset-of the closure signal. i

d. Control rods with a failed d. A second licensed operator

' " Full-in" or " Full-out" shall verify the conformance position switch may be by- to Specification 3.3.A.2d passed in the Rod Sequence before a rod may be bypassed Control System and considered in the Rod Sequence Control operable if the actual rod System.

position is known. These rods must be moved in sequence to their. correct positions (full in on  !

insertion or full out on l.

withdrawal.)  !

e.  !-

Control rods with inoperable  !

accumulators or those whose '

position cannot be positively determined shall be i considered inoperable. .

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-100-

L PBAPS 3.3'&'4.3 BASES (Cont'd) identified as.thelresistance to drive motion by an* internal centrol rod drive filter. The filter had been loaded by foreign material, probably accelerated by construction debris. The sudden changes ~in_ drive scram' performance which were observed at that plant were_due to stepwise release into-reactor coolant of 9

particulate matter as the reactor.and subsystem were subsequently started'up. The design of the present. control rod drive (Model i 7RDB144B) is grossly improved-by the relocation of the filter to-a location out of the scram drive path; i . e., it can no longer interfere with scram performance, even if completely blocked.

The degraded performance of the original drive (CRD7RDB144A)

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under dirty operating conditions and the insensitivity of the redesigned drive (CRD7RDB144B) has been demonstrated by a series of engineering tests under simulated reactor operating conditiens. The successful performance of the new-drive under actual operating' conditions has also_been demonstrated by consistently ~ good in-service test results for plants using the i

i new drive and may be inferred from plants using the older model  !

drive with a modified (larger screen size) internal filter which is less prone-to plugging. Data has been documented by -

4 surveillance reports in various operating plants. These include ,

t i

Oyster Creek, Monticello, Dresden 2 and Dresden 3. Dresden 2 has currently 27 "B" type drives. Approximately 4718 drive tests ,

have been recorded to date. Data documenting t~ne successful i parformance of the modified drive has been submitted to the NRC t with a letter from Commonwealth Edison Company to the Commission dated November 6, 1972 with the subject of the letter being Proposed. Changes to Quad-Cities. Power Station Operating License, including Appendices A and B, DPR'29 and 30, AEC Dkts 50-254 and 50-265. ,

Although the cause and cure of the dirt problem were known at the I time of the writing of the~Dresden 3. Tech Specs, the progressive f

surveillance requirement was. incorporated into.the technical i specification to ostensibly detect any other unforeseen drive y

! problems. The possibility of this being a temporary requirement J 4

-may be inferred from the provision for review of all surveillance requirements after the first operating cycle.-

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. Operability of the scram discharge volume vent'and drain valves  !

10 necessary for maintaining a reservoir to contain the water '

exhausted from all control rod drives during.a scram. L i

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