ML20069A407
| ML20069A407 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/01/1983 |
| 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 | |
| ML20069A410 | List: |
| References | |
| DPR-44-A-088, DPR-56-A-088 NUDOCS 8303150692 | |
| Download: ML20069A407 (21) | |
Text
_ _ _
p asc
,f uq(o UNITED STATES
+
g NUCLEAR REGULATORY COMMISSION y
it,(( g
, '. E WASHINGTON, D. C. 20555
(-
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 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 October 14, 1980, as supplemented October 7,1981, 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 conformity with the application, the provisions of the Act, and the rules and 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; 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 Licens( No. DPR-44 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amt.ndment No.88, are hereby incorporated in the license.
PECo shall operate the facility in accordance with the Technical Specifications.
8303150692 830301 PDR ADOCK 05000277 P
e 1
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ohn '. Stolz, Chief Op tir.g Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 1,1983 I
O
ATTACHMENT TO LICENSE AMENDMENT NO. 88 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 Insert 42 42 73 73 74a (new page) 83 E3*
92 92 100 100 112 112
- 0verleaf page provided for document completeness.
E O
O t
b 1
+-----,--,c-
--.,---,-w-w--
+~--
w m
I l
TAllLE 4.1.1 (cont'd)
REACTOR PROTECTION SYS"'EM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUCNCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2)
Functlona1 Test Minimum Frequency (3)
I j
High Water Imvel In Scram A
Trip Channel and Alarm Every I month, l
Discharge Tank i
i Turbine Condenser Low Vacuum
,(6)
B2 Trip Channel and Alarm (4)
Every 1 month (1).
{
Main Steam Line High Radiation B1 Trip Channel and Alarm (4)
Once/ week.
Main Steam Line Isolation A
Trip Channel and Alarm Every 1 month (1).
Valve Closure
~;
Turbine Control valve A
Trip Channel and Alarm Every 1 month.
EHC Oil Pressure Turbine First Stage Pressure A
Trip Channel and Alarm Every 3 months (1).
1 Permissive i
]
Turbine stop Valve Closure A
Trip channel and Alarm Every 1 month (1).
Reactor Pressure Permissive (6)
D2 Trip Channel and Alarm (4)
Every 3 anonths.
i i
t 1
i l
4 Amendmer.t No.
65, 88
i I
I F-4 TABLE 3.2.C INSTFUMENTATION TelAT INITI ATES CCNTMOL ROD BLOCNS 1
3 i
Minissue 290.
1sestrument Trip Level Setting Number of Instrument' Action of operable Channels Provideel
]
Instrument j
Channels Fer by Design 4
Trap System
)
2 APRM Upscale (Flow
$ (0.66W
- 4 2-0. 66AW) x 6 Inst. Channels (1) stased)
_ERE_
MFLPD (2) 2 APRM Upscale (Startup
.512%
6 Inst. Channels (1)
Mode) 2 APRM Eownscale 22.5 indicated on 6 Inst. Channels (1) scale i
N*
1 (7)
Nod Elock Monitor
$ (0. 66W e 41 -0.6 6AW) x 2 Inst. Channels (1)
(Flow biased)
_LRP l
MFLPli (2) l 1 (7)
Mod Block Monitor
),2.5 indicated on 2 T.st. Channels (1)
Downscale scale j
3 JAM Ecuriscale. (3)
>,2.5 Indicated on 8 Inst. Channels (1) 1 scale 3
IRM Cetector not in (8) 8 Inst. Channels (1)
Startup Position 9
3 IRN Upscale 15 08 indicated on 8 InJt. Channels (1)
N 1
scale i
N 2 (5)
SRM Uetector not in (4) 4 Inst. Channels (1)
Startup Position i
2 (5) (6)
SRM Upscale
.510s counts /sec.
4 Inst. Channels (1) 1 Scram Ql3 charge Volume 1.25 gallons High Level 1 Inst. Channel
-( 9)
[
-73 I
i
PBAPS NOTES FOR TABLE 3.2.C (Cont.)
9.
If the number of operable channels is less than required by the minimum operable per trip function requirement, place the inoperable channel in the tripped condition within one hour.
This note is applicable in the "Run" mode, the "Startup" mode and the " Refuel" mode if more than one control rod is withdrawn, i
l l
Amendment No. 88
-74a-
!E R
l 3
i TAB 1.F 4.2.C l
!I
~
j MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD BIDCKS ACTUATION OS 1
Instrument Functional Instrument Instrument Channel Test Calibration Check 1)
APRM - Downscale (1) (3)
Once/3 months once/ day i
2)
APRM - Upscale (1) (3)
Once/3 months once/ day 3)
IRM - Upscale (2) (3)
Startup or Control Shutdown (2) 4)
IRM - Downscale (2) (3)
Startup or Control Shutdown (2) 5)
RBM -- Upscale (1) (3)
Once/6 months Once/ day l
6)
RBM - Downscale (1) (3)
Once/6 months once/ day i
7)
SRM - Upscale (2) (3)
Startup or Control Shutdown (2) 8)
SRM - Detector Not in Startup Position (2) (3)
Startup or Control Shutdown (2) g IRM - Detector Not in Startup Position (2) (3)
Startup or Control Shutdown (2) 10)p Scram Discharge Volume - High Level Quarterly Once/ Operating Cycle NA ol ca Logic System Functional Test (4) (6)
Frequency h
, (1)
System Logic Check once/6 months i
O I
l 1
1
- ,e i
i
i i
5 I
TABLE 4.2.D 5
{
j MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS l
Instrument Channels Instrument Functional Calibration Instrument i
Test Check (2) l 1)
Refuel Area Exhaust Monitors - Upscale (1)
Once/3 months Once/ day 2)
Reactor Building Area Exhaust Monitors (1)
Once/3 months Once/ day
- Upscale M
3)
Off-Gas Radiation Monitors (1)
Once/3 months Once/ day l
g 4
i o,
m I
Logic System Functional Test (4) (6)
Frequency I
1)
Reactor Building Isolation Once/6 months 2)
Standby Gas Treatment System Actuation Once/6 months 3)
Steam Jet Air Ejector Off-Gas Line Isolation Once/6 months l
4 6
W
P1APS g
3.2 BAS,ES (Cont'd)
The APRM rod block function is flow biased and prevents a significant reduction in HCPR, especially during operation at reduced flow.
The APRM provides gross core protect' ion; i.e.,
limits the gross core power increase from withdrawal 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 IRH rod block function provides local as well as gross core protection.
The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level.
A downscale indication on an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough.
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 onc recirculation water pump.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
Higl. water level in the scram diccharge volume may he indicative of excessive scram valve leakage, or plugging or closing of the discharge volume drain valve, and could jeopardize the abilit,y of all rods to fully insert on a scram signal.
For effective emergency core cooling for small pipe breaks, the
!!P CI 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 HPC1 in the event the HPCI does not operate.
The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious l
operation.
The trip settings given in the specification are adequate to assure the above criteria are met.
The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes th'e risk l
of inadvertent operation; i.e.,
only one instrument channel out of service.
l Two air ejector off gas monitors are provided and when their trip t
point is reached, cause an isolation of the air ejector off cas line.
Isolation is initiated when both instruments reach their i
high trip point or one has an upscale Amendment No. 76, f$, 79,88 '
---,-m_. - - - - - - - - - - -
w
,-.,a,
---,_n,n--,wnnn-----g
---+v
-,ng,-,--y,m
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.3.A Reactivity Limitations 4.3.A Reactivity Limitations (Cont'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 dyive 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 not the cause of an immovable control rod.
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 disarmed electrically and once per month. These the control rods shall be valves may be closed in such positions that intermittently for testing.
Specification 3.3.A.1 is met, c.
Control rods with scram times c.
At least once every 3 greater than those permitted months verify that the by Specification 3.3.C.3 are scram discharge volume inopcrable
' ut if they can drain and vent valves i
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
~ reset of the closure signal.
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 be' fore 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 f
insertion or full out on withdrawal.)
e.
Control rods with inoperable accumulators or those whose position cannot be positively determined shall be considered inoperable.
Amendment No. 77, H, 88
-100-
)
3.3 & 4.3 BASES (Cont'd) identified as ths resistance to drive motion by an internal control 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 particulate matter as the reactor and subsystem were subsequently started up.
The design of the present control rod drive (Model 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) 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 conditions.
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 new drive a.nd 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 surveillance reports in various operating plants.
These include 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 the successful performance of the modified drive has been submitted to the NRC with a letter from Commonwealth Edison Company to the Commission dated November 6, 1972 with the subject of the letter being Proposed Chances to Quad-Citier Power Station Oparating License, l
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 time of the writing of the Dresden 3 Tech Specs, the progressive surveillance requirement was incorporated into the technical specification to ostensibly detect any other unforeseen drive problems.
The possibility of this being a temporary requirement may be inferred from the provision for review of all surveillance requirements after the first operating cycle.
Operability of the scram discharge volume vent and drain valves is necessary for maintaining a reservoir to contain the water l
exhausted from all control rod drives during:a scram.
I Amendment No. 88
-112-a 1--
[
o UNITED STATES
'g NUCLEAR REGULATORY COMMISSION n
,E 3
WASMNGTON. D. C. 20555 S
f PHILADELPHIA ELECTRIC COMPANY g
,j 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. 88 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated October 14, 1980, as supplemented October 7,1981, 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 conformity with the application, the provisions of the Act, and the rules and 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; 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 I
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 Licensi No. OPR-5G is hereby amended to read as follows:
l Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, are hereby incorporated in the license.
PECo shall operate the facility in accordance i
with the Technical Specifications.
2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0ft11SSION l
oh
'F. Stolz, Chief Op ating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: f4 arch 1,1983
ATTACHMENT TO LICENSE AMENDMENT NO. 88 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 Insert 42 42 73 73 74a (new page) 83 83*
92 92 100 100 112 112
- 0verleaf page provided for document comp 14teness.
D
/
e e
I e
e
-,,._._.e
TABLE 4.1.1 (conted) l l
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS I
l i
i Group (2)
Functional Test Minimum Frequency (3)
High Water Iavel In Scram A
Trip Channel and Alarm Every I month.
Discharge Tank i
Turbine condenser Low Vacuum (6)
B2 Trip channel and Alarm (4)
Every 1 month (1).
Main Steam Line High Radiation B1 Trip Channel and Alarm (4)
Once/ week.
i Main Steam Line Isolation A
Trip channel arid Alarm Every 1 month (1).
}
Valve Closure I
Turbine Control valve A
Trip Channel and Alarm Every 1 month.
1 EllC Oil Pressure i
Turbine First Stage Pressure A
Trip Channel and Alarm Every 3 months (1).
Permissive i
I Turbine Stop Valve Closure A
Trip Channel and Alarm Every 1 month (1).
- Reactor Pressure Permissive (6)
D2 Trip Channel and Alarm (4)
Every 3 months.
- R: actor Pressure Fermissive A
Trip Channel and Alam Every 3 months.
l.
- Deleted when modifications auttiorized by hnendment No. 67 are completed.
i
- Effective when modifications authorized by Amendment No.67 are completed.
i Amendment No. 67 88 4
I
f.
i 1
E m
i
{
1stST5UMENTAT10N Til4T INITI ATES CCNTHOL ROD BLOCMS
?ABLE 3.2.C Miniema tso.
' Instrument trip Level Setting taumber of Instrument Action
,=
of operable Instrument Channels Provideal u
channels rer by Design Trip system
=
2 APRM Upscale (Flow 5 (0. 66H 8 4 2-0. 66&W) x 6 Inst. Channels (1) i w
niased) i 7
__tgE__
MFLPD (2) m*
l.
Mode) 2 AFNM Upscale (Startup
$12%
6 Inst. Channels (1) i 2
APRM Eownscale
%2.5 indicated on 6 Inst. Channels (1) scale 1
1 (7) liod Elock Monitor l
$ (0.66We 41 -0.6 6aW) x 2 Inst. Channels (1)
(Flow Biased)
__F, RE__
MFLPD (2) t 1 (7)
Nod Block Monitor
>2.5 indicated on 2 Inst. Channels (1)
Downscale scale l
3 IRM ccwnscale (3) 2 2.5 indicated on 8 Inst. Channels (1) scale 3
IRM Cetector not in (8) 8 Inst. Channels (1)
Startup Position 3
'IRM Upscale
$108 indicated on 8 InJt. Channels (1) scale 2 (5)
SRM Uetector not in (4) 4 Inst. Channels (1)
Startup Position j
2 (5) (6)
SkN Upscale
$105 counts /sec.
4 Inst. Channela (1)
{
l Scnam Discharge Volume 1.25 gallons 1 Inst. Channel
'-(9) l High Level
~
' 1
PBAPS NOTES FOR TABLE 3.2.C (Cont.)
9.
If the number of operable channels is less than required by the minimum operable channels per trip function requirement, place the inoperable channel in the tripped condition within one hour.
This note is applicable in the "Run" mode, "Startup" mode and
" Refuel" mode if m.,re than one control rod is withdrawn.
i Amendment No. 88
-74a-
N l
re TABI.r2 4. 2.C, 2o
]
MINIMUM TEST AND CALIBRATION FREQUCNCY FOR CONTROL ROD BIDCKS ACTUATION Instrument Functional Instrument Instrument Channel Test Calibration Check 1)
APRM - Downscale (1) (3)
Once/3 months once/ day 2)
APRM - Upscale (1) (3)
Once/3 months Once/ day i
)
3)
IRM - Upscale (2) (3)
Startup or Control Shutdown (2) 4)
IRM - Downscale (2) (3)
Startup or Control Shutdown (2) l 5)
RBM - Upscale (1) (3)
Once/6 months once/ day 6)
RBM - Downscale (1) (3)
Once/6 months Once/ day i
7)
SRM - Upscale (2) (3)
Startup or Control Shutdown (2) l 8)
SRM - Detector Not in Startup Position (2) (3)
Startup or Control Shutdown (2) l 9)
IRM - Detector Not in Startup Position (2) (3)
Startup or Control Shutdown (2) j
- 10) Scran! Discharge Volume - High Level Quarterly Once/ Operating Cycle NA l
Logic System Functional Test (4) (6)
Frequency 3
2=
(1)
System Logic Check Once/6 months 3
0 t
i
I 1
5 TABLE 4.2.D 5
g MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS 1
J Instrument Channels Instrument Functional Calibration Instrument Test Check (2) 1)
Refuel Area Exhaust Monitors - Upscale (1)
Once/3 months Once/ day 1
2)
Reactor Building Area Exhaust Monitors (1)
Once/3 months Once/ day
- Upscale m
3)
Off-Gas Radiation Monitors (1)
Once/3 months Once/ day 7,
I M
ce M
i i
e Logic System Functional Test (4) (6)
Frequency l
1)
Reactor Building Isolation Once/6 months 1
2)
Standby Gas Treatment System Actuation Once/6 months l
3)
Steam Jet Air Ejector Off-Gas Line Isolation Once/6 months l
./
The APRM rod block function is flow biased and prevents a significant reduction in MCPR, especially during operation at reduced flow.
The APRM provides gross core protect ~ ion; 1.e.,
limits the gross core power increase from withdrawal 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 protection.
The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level.
A downscale indication on an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough.
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.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
High water level in the seram discharge volume may he indicative of excessive scram valve leakage, or plugging or closing of the discharge volume drain valve, and could jeopardize the abilit,y of all rods to fully insert on a scram signal.
For effective emergency core cooling for small pipe bretks, the 11P CI system must function since reactor pressure does not i
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 HPCl in the event the HPCI does not operate.
The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation.
The trip settings given in the specification are adequate to assure the above criteria are met.
The specification preserves the effectiveness of the system during periods of, maintenance, testing, or calibration, and also minimizes t h'e risk of inadvertent operation; i.e.,
only one instrument channel out of service.
Two air ejector off gas monitors are provided and when their trip point is reached, cause an isolation of the air ejector off cas line.
Isolation is initiated when both instruments reach their high trip point or one has an upscale l
Amendment No. 75, M, 77,88.
t PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity Limitations 4.3.A Reactivity Limitations (Cont'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 not the cause of an immovable control rod.
b.
The control rod directional b.
The scram discharge volume control valves for inoper-drain and vent valves shall' able centrol rods shall be be verified open at least disarmed electrically and once per month. These the control rods shall be valves may be closed in such positions that intermittently for testing.
Specification 3.3.A.1 is met.
c.
Control rods with scram times c.
At least once every 3 greater than those permitted months verify that the 4
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
" reset of the closure signal.
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 be' fore 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 withdriwal.)
e.
Control rods with inoperable accumulators or those whose i
position cannot be positively determined shall be considered inoperable.
Amendment No. 88 3oo.
PBAPS 3.3 & 4.3 BASES (Cont'd) identified as ths resistance to drive motion by an internal control 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 stepwice release into reactor coolant of 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) 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 conditions.
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 new drive a.nd 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 surveillance reports in various operating plants.
These include 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 the successful performance of the modified drive has been submitted to the NRC with a letter from Commonwealth Edison Company to the Commission dated November 6, 1972 with the subject of the letter being Froposed Changes to Quad-Ciclas 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 time of the writing of the Dresden 3 Tech Specs, the progressive surveillance requirement was incorporated into the technical specification to ostensibly detect any other unforeseen drive problems.
The possibility of this being a temporary requirement i
may be inferred from the provision for review of all surveillance requirements after the first operating cycle.
Operability of the scram discharge volume vent a'nd drain valves is necessary for maintaining a reservoir to contain the water exhausted from all control rod drives during.a scram.
I Amendment No. H,"88
-11'2-
___,.---.v
'