ML20212J439
| ML20212J439 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/27/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2NRC-7-034, 2NRC-7-34, GL-85-06, GL-85-6, ND1NSM:2560, TAC-62943, NUDOCS 8703090027 | |
| Download: ML20212J439 (32) | |
Text
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M Telephone (4n) asa-sooo nuctear oroup Februe.ry 27, 1987 hnSppingport, PA 15077-0004 2NRC-7-034 U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 and Unit No. 2 Docket No. 50-334 and 50-412, License No. DPR-66 10CFR50.62, ATWS Rule Implementation Gentlemen:
On June 26,
- 1984, the final rule on reduction of risk from anticipated transients without scram (ATWS) was published in the Federal Register (49FR26036) as 10CFR50.62.
By letters dated June 26,
- 1985, September 30,
- 1985, September 17, 1986 and November 10,
- 1986, Duquesne Light Company provided a
proposed schedule for implementation which called for submitting the design information required by 50.62(c)(6) in February 1987.
Our plans are to implement a
system to initiate auxiliary feedwater and turbine trip on low main feedwater flow consistent with the Westinghouse Owner's Group (WOG)
Topical Report WCAP-10858, "AMSAC Generic Design Package".
This report has been reviewed and approved for referencing by a safety evaluation provided to the WOG on July 7, 1986.
Attached is the plant specific design information required by 50.62(c)(6) for Beaver Valley Power Station, Unit Nos. 1 and 2 ATWS mitigation system actuation circuitry (AMSAC).
This information addresses the NRC safety evaluation on the WOG AMSAC generic design package and the Quality Assurance guidance for ATWS equipment (Generic Letter 85-06).
For Unit 1,
installation of AMSAC is scheduled for the sixth refueling outage which is planned to begin in November 1987.
For Unit 2,
AMSAC is scheduled to be installed during the first refueling
- outage, however, if startup is delayed, installation will be done no later than July 1989.
If you have any questions on this subject, please contact my office.
Very truly yours, g
0703090027 B70227
~
PDR ADOCK 05000334
/
P PDR J. D. Sieber Vice President, Nuclear
l Beaver Valley Power Station, Unit No. 1 and Unit No. 2 Docket Nos. 50-334 and 50-412, License No. DPR-66 10CFR50.62, ATWS Rule Implementation Page 2 cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Ad.ninistrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 340 Addressee only Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Washington, DC 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 Mr. J. Beall, Sr. Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Ms. A. Asars, Resident Inspector U.
S. Nuclear Regulatory Commission Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 INPO Records Center 1100 circle 75 Parkway Suite 1500 Atlanta, GA 30339
= _...
A M S A'C DESIGN REPORT; Beaver. Valley Power 1 Station, Unit Nos. 1 and 2 Docket Nos. 50-334 and 50-412 1.
BACKGROUND on June.26, 1984,-the NRC published the final rule (10 CFR 50.62) on. Anticipated Transients,Without. Scram (ATWS) _in-the Federal Register.
(49 FR 26036).
A correction to the rule was issued on July 6,. 1984. (49 FR 27736) and the rule reporting requirements revised on November.6,-
1986 (51 FR 40303).
The ATWS rule requirements for Westinghouse plants are:
[50.62(c)(1)]
Installation of a
non-safety. grade
- system, diverse from the reactor, trip
- system, that automatically initiates auxiliary feedwater and Turbine Trip under ATWS conditions.
[50.62(c)(6)]
Submission of information sufficient to demonstrate the adequacy of the system.
[50.62(d)]
Submission of a proposed schedule for meeting'the requirements after issuance of QA guidance for the system.
The QA guidance for the ATWS Mitigating System Actuation Circuitry. (AMSAC). was issued on April 16, 1985 as Generic Letter 85-06.
Beaver Valley 1 provided a schedule by letter dated June 26, 1985 -with a revision provided by letter dated September 17, 1986.
Beaver Valley 2
provided a
schedule by letters dated September 30, 1985-and November 10, 1986.
l The Westinghouse Owner's Group (WOG) has developed a generic design package that provides three options for meeting the ATWS rule.
This package (WCAP-10858, "AMSAC Generic Design Package")
j.
was submitted.to the NRC for review on July 25, 1985.
On July 7, 1986 the NRC issued a
Safety ' Evaluation (SE) to the WOG that allows
-plants to reference WCAP-10858 provided each plant provides specific information on 14 items identified in the SE as plant specific.
f 2.
CONCEPTUAL DESIGN A Westinghouse report, WCAP-8330, summarizes the results of ATWS events at a Westinghouse pressurized water reactors.
This report identifies only two ATWS events for which the 3200 psig service level of the RCS may be exceeded.
These transients are:
p complete loss of normal feedwater without scram.
[
a.
j b.
loss of electrical load without scram.
I The loss of electrical load transient is not applicable to Beaver i
Valley because it applies only to plants where the loss of main condenser vacuum causes the loss of the steam-driven main feedwater pumps where as Beaver Valley 1 and 2 has motor-driven main feedwater pumps.
Therefore, the transient the AMSAC is being designed for is the loss of normal feedwater.
2
. _. ~,. _ _ _ _ _., _ _. _ _ -, _, _ _ _ _. _ _. _ _ _, _ _ _ _
~AMSAC Design R3 port BVPS Unit No. 1 and 2 Prgs 2 To address' this transient, we are developing a plant specific design based on the conceptual design: presented in Section 4 of WCAP-10858 (Logic 2:
AMSAC Actuation on Low Main Feedwater Flow).
This. system will actuate a turbine trip and initiate auxiliary feedwater upon sensing the main feedwater flow below a low flow setpoint.
The design is such that the system will; sense conditions indicative of an ATWS when a loss of heat sink has occurred but will not actuate until after a reactor protection signal-should have been generated.
Functional logic diagrams are provided in Figures 1 (Unit 1) and 2 (Unit 2).
Main feedwater flow will be sensed by. three (one per loop) existing protection system transmitters that are located between the main feedwater header and the feedwater regulation valves.
The feedwater flow signal provided to the AMSAC cabinet will be a non-protection system signal derived from the output of an-existing signal isolator within the protection loop.
The. turbine impulse chmnber pressure will be sensed by two existing protection system transmitters and will be provided to the AMSAC cabinet as a non-protection system signal derived from the output of an existing signal isolator.
Actuation of AMSAC will occur on any two of the three main feedwater flow signals below a specific setpoint.
However, to allow for recovery from the loss of only one main feedwater pump and to permit the reactor protection system to respond first, the AMSAC signal will be delayed for a specific time.
To prevent spurious actuations during startups, the turbine impulse chamber pressure will block actuation signals when one of the.two pressure signals are below a setpoint.
In the event of a turbine trip the block of AMSAC will be delayed for a time to allow the system to respond if required.
The setpoint for AMSAC actuation is 25% feedwater flow with a 25 second time delay.
The setpoint for AMSAC block is 40% turbine load with a 120 second time delay.
The AMSAC signal will be provided to a set of oatput isolation relays that will start the auxiliary feedwater pumps and trip the turbine.
To accomplish
- this, contacts from the output relays will be paralleled or installed in series with the reactor protection system contact that performs the same functions.
The three main feedwater flow transmitters are powered from one instrument power supply.
To avoid a spurious AMSAC actuation if the instrument power supply fails a circuit is being added that will block actuation if all three flow signals into AMSAC are lost.
RMSAC Design Report BVPS Unit No. 1 and 2 Page 3 3.
RESPONSE TO SE ON WCAP-10858 a.
(Diversity)
Existing instrument
- sensors, power supplies and isolators are being used for the inputs to AMSAC (3 Feedwater Flow signals and 2 Turbine Impulse Chamber Pressure signals).
The existing final actuation devices (i.e. circuit breakers or solenoid valves) are being used for actuation.
To accomplish
- this, the contact outputs from AMSAC will be series or parallel connected with the reactor protection system contacts in the final actuation device circuit.
(see Figure 3 to 16)
The AMSAC hardware will be of a
different design and manufacturer (Foxboro) than the existing Reactor Protection System (Westinghouse).
Foxboro will use their SPEC 200 and SPEC 200 MICRO equipment which uses microprocessors to perform the logic function.
This is a different design from the existing Westinghouse 7100 (Unit 1) and 7300 (Unit 2) series process equipment and solid state protection system, b.
(Logic Power Supplies)
The AMSAC logic cabinet supply will be from a non-Class 1E instrument power supply which is battery backed.
This power source is independent from the power supplies for the existing Reactor Trip System and is capable of performing during a
For higher reliability, dual power supplies will be used in the AMSAC equipment and will be diode auctioneered.
Therefore, in the event of a failure of one power
- supply, the other power supply will take over.
c.
(Safety-Related Interface)
The implementation of AMSAC does not violate any safety criteria applicable to the Reactor Protection System.
The isolation device is the interface that separates the AMSAC equipment from the Safety-Related systems.
The implementation of the interface will be such that the existing protection system will continue to meet all applicable safety criteria.
The existing isolators (Inputs) are a
qualified device.
(See Section 3.1)
The output isolators (relays) are to be qualified to IEEE 323-1974 and 344-1975.
Physical separation is specified per IEEE 384-1981 for cables routed inside the cabinet and for outside the cabinet
(
the cable separation is per existing BVPS 1 and 2 separation criteria documents and as summarized in the Unit 1 UFSAR Section 8.5 and Unit 2 FSAR Section 8.3.
d.
(Quality Assurance)
See SECTION 4
-AMSAC De2ign Report BVPS Unit No. 1 cnd 2
, PCg3 4 e.
(Maintenance Bypass)
An integral test panel will be used to perform routine surveillance and troubleshooting.
A test / maintenance bypass switch is used to block actuation during testing or maintenance.
Continuous annunciation shall be provided in the control room when the switch is in the bypass position.
The test panel shall be designed so that the cabinet doors cannot be I
closed with the switch in the bypass condition.
Maintenance at power is accomplished by modular replacement of failed components.
Contact closures are provided for annunciation when a
module is removed or power is removed from the system.
This annunciation will be in the control room.
f.
(Operating Bypass)
Operating bypass of AMSAC is accomplished by the C-20 permissive.
This signal is derived from two existing turbine impulse chamber pressure transmitters (one from each impulse chamber) in the reactor protection system.
The signals are isolated by existing isolators and routed to the AMSAC cabinet as non-safety grade signals.
When the pressure signal on both channels exceeds the setpoint (2 out of 2), AMSAC is immediately armed.
When the pressure signal on either of the channels decreases below the setpoint (1
out of 2), AMSAC will be disarmed only if the signal remains below the setpoint for a predetermined set time.
The setpoint for the C-20 permissive is 40% turbine load with a
time delay of 120 seconds on disarming.
The basis for this value is currently being assembled by the WOG.
When this task is completed, we will provide additional information on the bases for the C-20 setpoint.
Since all three feedwater flow transmitters are powered from the same instrument power
- supply, cpurious actuation on failure of this supply will be prevented by blocking AMSAC if all three flow signals are lost.
The AMSAC logic will monitor the feedwater flow signals entering the cabinet for levels indicative of instrument loop failure and only on all three loops indicating a failure vill AMSAC be blocked.
A control room annunciator provides indication when AMSAC is bypassed by the C-20 permissive.
The annunciator layout shall be reviewed for consistency with other annunciators related to the feeduater and turbine systems to assure that Human Factors are considered.
,LAMSAC'De2ign Rsport-LVPS Unit-No.'1 and 2 P;gD 5-For additional information on diversity and independence, see Sections 3.a, 3.1 and 3.j.
g.
(Means for Bypassing)
The means 'for bypassing the AMSAC. equipment shall be accomplished with a
permanently installed Human Factored
. bypass switch on the test panel.
The test panel is designed so that the cabinet doors cannot be closed with the switch in the bypass position.
The bypass switch does not involve lifting
- leads, pulling
_ fuses, tripping breakers or-physically blocking relays. (Also see Section 3.e and 3.f)
-h.
(Manual Initiation)
Manual-initiation of _the turbine trip can be accomplished from the benchboard in the Control Room via either of two pushbuttons-as shown.in Figure 3 and 10 (Logic Diagram).and-Figure 4
and 11 (Elementary Diagram).
The turbine can also be manually tripped via a
trip-lever on the turbine standard.
The manual initiation of the' two motor driven auxiliary
'feedwater pumps (Unit 1:
FW-P-3A and FW-P-3B,-
Unit 2:
2FWE*P23A and 2FWE*P23B) can be accomplished from the benchboard in the Control Room or the shutdown panel by control switches as shown in Figure 5 and 12 (Logic Diagram) and Figures 6, 7, 13 and 14 (Elementary Diagrams).
The-manual initiation of the.one steam driven auxiliary.
feedwater _ pump (Unit 1:
FW-P-2, Unit 2: 2FWE*P22) can be accomplished from the benchboard in the Control Room or the Shutdown Panel by control switches as shown in Figure 8 and 15 (Logic. Diagram) and Figure 9 and 16 (Elementary Diagram).
All. of the above methods are diverse from the existing solid state protection system.
i.
(Electrical Independence from Existing Reactor Protection System)
The inputs to AMSAC (main feedwater flow and turbine impulse chamber pressure) will be taken from existing safety-related circuits isolated by existing isolators.
Cable routing from the isolators to the AMSAC cabinet will be per existing Beaver Valley 1 and 2 criteria for non-safety cables.
Under conditions where the maximum credible faults are postulated to be imposed on the non-safety circuits in the AMSAC equipment, the existing Class 1E isolators (Unit 1:
Westinghouse 7100
- series, model 131-110, Unit 2:
Westinghouse 7300 series) shall not cause safety-related circuits to fail.
AMSAC Dedign R; port BVPS Unit No. 1 cnd 2 Pcg3 6 The maximum worst case conditions are the application of a short
- circuit, open circuit, or the application of 120 VAC on
.the isolated output portion of the instrumentation circuit (i.e., the AMSAC circuitry).
For. the 7100 series isolators, the NRC has previously accepted Westinghouse WCAP-7509-L (Proprietary) and WCAP-7824 (Non-proprietary) per Atomic Energy Commission Letter dated June 6, 1973 from D. B. Vassallo to Mr. Romano Salvatori of Westinghouse.
For the 7300 series isolators, Westinghouse WCAP-8892-A, which provides justification that the objectives of IEEE 279-1971 and Regulatory Guide 1.75 have been satisfied, has been accepted by the NRC.
The power to these isolators is from the existing protection system power supplies which is Class lE.
The output isolators (relays) are to be qualified to IEEE 323-1974 and 344-1975.
j.
(Physical Separation From Existing Reactor Protection System)
The AMSAC equipment shall be physically separated from the existing Reactor Protection System equipment in that each system shall be located in separate cabinets.
The interconnecting cable routing between the systems shall be separated according to the existing separation criteria applied to the protection system and channel separation criteria shall not be violated.
k.
(Environmental Qualifications)
The equipment used for AMSAC shall be designed such that it will be operational in the anticipated r yerational environment.
1.
(Testability at Power)
The AMSAC equipment shall be functionally tested by the manufacturer prior to its shipment to Beaver Valley.
In
- addition, after installation but prior to being put into operation, the system shall be functionally tested.
Periodic testing of the system will be performed based on manufacturer and engineering recommendations with testing of the output through the final actuation device performed during plant shutdowns.
rAMSAC-Design R3 port
- BVPS Unit No. 1 and 2
, PIgni7.
Testing at power-is accomplished through'an intergrated, test panel which. includes a
bypass switch.that blocks 'the actuation signal.and provides continuous annunciation in'tne control room.
Testing-is performed. by first placing the bypass switch in the bypass mcde.
Test switches for each of the inputs are switched individually and in combination to. allow: insertion of analog test signals.
Actuation of bistables.and logic.is observed on test panel lights...When testing is complete, a mechanical interlock prevents closing the test panel or i
cabinet doors with the test Hor bypass' switches in the*
test / bypass mode.
m.
(Completion of Mitigative Action)
JS Once AMSAC
.is initiated, the steam driven auxiliary feedwater
- pump, the two motor driven auxiliary feedwater
- pumps, and the turbine all require deliberate operator action to reset..
The two motor -driven auxiliary feedwater pumps are started by. closing of their 4KV circuit breaker.
Once closed,-the:
breaker can only be opened by motor protection trips or a manual trip.
(See Figures 6, 7, 13 and 14)
The steam driven auxiliary feedwater pump-is started by de-energizing a ' solenoid valve and shall continue operating until manually reset.
(See Figure 9 and 16).
The turbine 'is tripped by draining the-hydraulic oil from the control system.
A turbine " latch" push button on the EHC control panel in the Control Room must be depressed to latch the turbine control valves, n.
(Technical Specifications)
In a letter dated February 10, 1986, the WOG has submitted a position that Technical Specifications for AMSAC are unnecessary.
Beaver Valley concurs in this position and believes that the normal plant administrative controls are sufficient to maintain AMSAC operable.
The Quality Assurance guidance for AMSAC (Generic Letter 85-06) has guidelines for Testing and Maintenance to maintain the system operable.
Item V of the guidance requires procedures based on vendor guidance and Item XI requires periodic testing.
i l
See Section 3.1 for periodic testing.
(
{
L j.
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n
.AMSAC5Decign Rsport s
-BVPS Unit No.l1 and 2 x
y Ptg3 8 7,
4.'. RESPONSE TO GENERIC LETTER 85-06, OUALITY ASSURANCE t
The AMSAC equipment will be manufactured under a. quality I
assurance programc in full compliance with 10 CFR 50, App. B.
2 This meets-the requirements of NRC Generic Letter 85-06..
I.
Provided'below'isa'descriptiononhowBeaverValleywill/addre'ss the ; Quality Assurance requirements for installation and operation of the-AMSAC-equipment.
For the portions of AMSACithat,hrb safety-related (i.e.,'
Isolators and Cabinet) the-existing QA program will be invoked.
k s
a.
Organization
];
For the non-safety-related portions,. normal line management will be' used to ensure activities affecting AMSAC have been correctly performed.
b.
Program N
s-Existir.g plant procedures and practices shall describe the quality controls applied to the AMSAC equipment.
c.
Design Control The existing procedures for Safety-Related work shall be invoked including verification 'of design specifications, test specifications, installation specifications, logic
- diagrams, and drawings.
These procedures meet the requirements of 10 CFR 50 Appendix B.
d.
Procurement Document Control Procurement document control shall be the same as that used for safety-related work which meets the requirements of 10 CFR 50 Appendix B.
e.
Instructions, Procedures, and Drawings For the design of AMSAC; the instructions, procedures, and drawings shall be by the same system as that used for Safety-Related work which meets the requirements of 10.CFR 50 Appendix B.
For operation of AM9AC, activities such as testing will be performed by written instructions.
Maintenance activities will be performed under our Maintenance Work 2equest system that provides maintenance personnel with written instructions, cautionary
- notes, etc.
where it is deemed necessary.
/r AMSAC De31gn'R2 port:
N/.
BVPS-Unit No.'l cnd.2 PIga. 9 f.
Document Control Changes tx) Engineering documents and their issuance shall be by the same method as zhat used for Safety-Related-work.
g.
Control of Purchased Items and Services Duquesne'. Light Company Vendor Surveillance is scheduled to inspect the equipment to the; attributes listed in-the procurement specification before the equipment.is shipped.
The engineer may, at his option, also inspect the equipment and observe testing of the equipment before it is shipped.
A receipt
. inspection shall also -be. conducted' in the
}o
-storeroom when the equipment arrives to determine that the L'
shipment was not damaged or improperly handled during transit.
- Also, a
receiving inspection is conducted by DLC-QC of the equipment received at the storeroom in which' i
the items are inspected for compliance with the procurement specification and procurement documentation -requirements.
The. receiving inspection is a more detailed and/or technical examination of physical attributes
.and supporting.
documentation of received items and normally follows receipt inspection.
All the above inspections shall be performed'in accordance with our existing' program for safety related work.
i Spare and replacement parts shall be purchased to -the applicable requirements of the original procurement
~
specification.
h.
Identification and Control of Purchased Items The equipment shall be identified and controlled in accordance' with existing storeroom procedures which are used for safety-related work.
The procurement specification specifically identifies the AMSAC equipment with a unique
" Tag Number".
The procurement specification states.the requirements of shipping,. receiving, handling, and storage to be in accordance with ANSI N45.2.2, Level B and NRC Regulatory Guide 1.38.
The vendor has agreed that the i
storage of the equipment as outlined above is satisfactory.
In
- addition, the receiving,
- handling, and any-special storage requirements as stated in the procurement specification shall be forwarded to the jobsite with each shipment to which they are applicable.
Also, all crates or boxes shall have external identification marking, including t
Job Order No.,
Purchase Order No.,
Item No., Engineer's name, and Purchaser's Project No.
... _. _. __.. _.. _ _.,. _... ~. _. _.. _.. _ _..__ _ _._, _.-... _ _ _._.. _ _
AMSAC De'31gn R; port-BVPS Unit No. 1 cnd 2 P g2 10 1.
Control of Special Processes All welding of the AMSAC cabinet as stated in the procurement specification shall be done in accordance.with Steel ANSI /AWS Dl.1-84, the structural welding Code Chapters 1 thru 6.
The visual inspection criteria is listed in the procurement specification.
j.
Inspections Duquesne Light Company Vendor Surveillance Group for QC (independent of the line organization) shall do all inspections at the vendors shop per hold points listed in the procurement specification.
The line organization shall be responsible for determining inspection requirements and ensuring that sufficient inspections are performed during installation and operation.
k.
Testing The AMSAC equipment shall be functionally tected at the vendors shop prior to shipment.
Once the equipment is installed and before operational acceptance the equipment shall be thoroughly tested per a test specification issued by the engineer and a test procedure issued by testing.
The above specification and procedure shall establish acceptance criteria based upon the system design and vendor recommendations.
Periodic
- testing, at frequencies recommended by the vendor, will be performed by written procedures that incorporate vendor and engineering recommendations.
1.
Control of Measuring and Test Equipment Existing plant procedures shall be used for the control, calibration, and adjustment of test equipment at specified intervals.
m.
Handling, Storage and Shipping l
See Section 4.h n.
Inspections, Tests and Operating Status Periodic tests shall be performed to verify that AMSAC is operable.
Existing plant procedures and/or practices shall be utilized to indicate the status of AMSAC testing and operability.
c
'AMSAC-.Deaign-R; port
~ BVPS Unit No. 1 cnd 2 Ptga 11-o..
Nonconforme.nces Existing plant practices shall be used to control materials,
-parts or components which do not conform to requirements.
p.
Corrective Action System Existing plant practices _shall be used to assure that conditions adverse to qualify are promptly identified and corrected, q.
Records Current plant procedures require-changes to the plant or procedures, tests or experiments to be reviewed per the requirements of 10 _CFR 50.39 and the records of these-activities be maintained per 50.59(b).
The. information to verify the requirements of the table that accompanied the ATWS rule shall be maintained under the current method of maintaining design documentation.
r.
Audits Management reviews and approves all design documents such as
- drawings, logic
- diagrams, procurement specifications, installation specifications,. test specifications, etc.-
In the course of this _ review, management assures that all documents ' meet the latest approved procedural requirements.
If engineering procedures are not being
- followed, the document is revised before any management approval.
Along with'the management reviews, the above documents shall be independently verified in accordance with ANSI N45.2.ll.
Any changes required as a result of the verification process shall be documented in a revision to the document before it is issued.
In addition, procedures used for testing and maintenance are also reviewed by management prior to being issued or revised.
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