ML20040C334
| ML20040C334 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/07/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 8201270542 | |
| Download: ML20040C334 (24) | |
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CATAWBA Mr. William 0. Parker Vice President - Steam Production Duke Power Company P.O. Box 33189 Charlotte, North Carolina 28242 cc: William L. Porter, Esq.
North Carolina Electric Membership Duke Power Company Corp.
P.O. Box 33189 3333 North Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 Raleigh, North Carolina 27611 J. Michael McGarry, Ill, Esq.
Debevoise & Liberman Saluda River Electric Cooperative, 1200 Seventeenth Street, N.W.
Inc.
Washington, D. C.
20036 207 Sherwood Drive Laurens, South Carolina 29360 North Carolina MPA-1 P.O. Box 95162 James W. Burch, Director Raleigh, North Carolina 27625 Nuclear Advisory Counsel 2600 Bull Street Mr. R. S. Howard Columbia, South Carolina 29201 Power Systems Division Westinghouse Electric Corp.
Mr. Peter K. VanDoorn P.O. Box 355 Route 2, Box 179N Pittsburgh, Pennsylvania 15230 York, South Carolina 29745 Mr. J. C. Plunkett, J r.
NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28208 Richard P. Wilson, Esq.
Assistant Attorney General S.C. Attorney General's Of fice P.O. Box 11549 Cclumbia, South Carolina 29211 Walton J. McLeod, J r., Esq.
General Counsel South Carolina State Board of Health J. Marion Sims Building 2600 Bull Street Columbia, South Carolina 29201
o Ef! CLOSURE 1 s
4 REQUEST FOR ADDITI0tlAL IflFOR"ATI0tt CATAWBA STATI0fl UtlITS 1 t. 2 IllITIAL TEST PROGRA!i 640.01 State that copies of approved test procedures will be available for (14.2.3.2) examination by fiRC regional personnel approximately 60 days prior to the scheduled perfor nance of preoperational tests, and not less than 60 days prior to scheduled fuel loading date for startup tests.
(NRC possession of the procedures should not impede the revision, review, or refinement of the procedures.)
640.02 The initial test program should verify the capability of (14.2.12) the offsite power system to serve as a source of power to the emergency buses.
Tests should demonstrate the capability of each starting transformer to supply power (as the alternate supply) to its unit's emergency buses while carrying its maximum load of plant auxiliaries and the other unit's emergency buses (as preferred supply).
Tests should also demonstrate the transfer capabilities of the unit's emergency bus feeders upon loss of one source of offsite power.
These tests should be performed as early in the test program as the j
availability of necessary components allows.
Provide des-criptions of the tests that will demonstrate these capabilities.
640.03 Provide test descriptions that will verify that the emergency (14.2.12) ventilation systems are capable of maintaining all Engineered Safety Feature equipment within their design temperature range with the equipment operating in a manner that will produce the maximum heat load in the compartment.
If it is not practical to produce maximum heat loads in a compartment, describe the methods that will be used to verify design heat removal capacity of the emergency ventilation systems.
640.04 Modify Table 14.2.12-1, page 12, to include the commitment to (14.2.12-1) demonstrate at least five consecutive successful cold, quick auxiliary feedwater pump starts.
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640.05 Modify Table 14.2.12-1, page 21, to include the following:
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(14.2.12-1) a) Verify that individual cell limits are not exceeded during the design discharge test.
b) Verify that each battery charger is capable of floating the battery on the bus while supplying the largest combined demands of the various steady-state loads under all plant operating conditions, not just for normal bus 0.C. loads.
c) Verify that each battery charger is capable of recharging the completely discharged battery within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of thE Various steady-state loads.
640.06 Because Catawba Nuclear Station is a multi-unit facility, (14.2) describe the power supplies for the units to ensure independence during power distribution testing.
The descriptions should address both normal and emergency A.C. and D. C. power distri-bution systems.
Provide assurance that cross-ties will not exist which could cause less emergency bus pcwer to one unit, due to testing of the other unit.
640.07 Modify Table 14.2.12-1, page 28, to include the description (14.2.12-1) of test procedures which will serve a) To demonstrate the capability of the combustible gas control system to operate in response to post-LOCA requirements.
b) To demonstrate that post-LOCA hydrogen monitors function j
properly.
I c) To demonstrate the operability of the vacuum breakers.
640.08 Verify that sources of water for long-term core cooling are (14.2) tested to demonstrate adequate NPSH and the absence of vortexing over the range of basin levels from maximum to the minimum calculated 30 days following LOCA.
- 640.09 Provide a description of the testing that demonstrates the (14.2.12) capacities of the cressurizer, main steam reliefs, and turbine bypass valves.
It has been noted in other startups that the capabilities of these values sometimes exceed the values assumed in the accident analyses for inadvertent opening or failure of these valves.
640.10 Verify that open and reclosure set points for all safety (14.2.12) and relief valves are checked at temperature.
640.11 Verify that the communication system is preoperationally (14.2) tested, especially if it is relied on by the emergency plan.
640.12 Verify that tests of sampling systems are adequate to verify (14.2) flow paths, holdup times, and procedures.
640.13 Our review of licensee event reports has disclosed that many (14.2) events have occurred because of dirt, condensed moisture, or other foreign objects inside instruments and electrical components (e.g., relays, switches, breakers).
Describe any tests or inspections that will be performed or any administrative controls that will be implemented during your initial test program to prevent component failures such as these at your facili ty.
640.14 Table 14.2.7-1 (page 5), Compliance With Regulatory Guides.
(14.
7.1)
Exception to Regulatory Guide 1.79 Rev.1 Section C.1.b.(2) is not justified.
Vendor testing of individual ccmponents cannot adequately predict system behavior.
Add additional tests or modify existing test abstracts in Table 14.2.12-1 to ensure compliance
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with Regulatory Cuide 1.79 Rev.1 Regulatory Position C.l.b.(2).
640.15 Provide a preoperational test description to test containment (14.2.12-1) penetration coolers.
On those penetrations where coolers are not used, provide a startup test description that will demonstrate that concrete temperatures surrounding hot penetrations do not exceed design limits.
600.16 Certain terminology used in the individual test descriptions (1.2.12) does not clearly indicate the source of the acceptance criteria to be used in determining test adequacy.
An acceptable format for providing acceptance criteria for test results includes any of the following:
Referencing technical specifications (Chapter 16)
Referencing accident analysis (Chapter 15)
Referencing other specific sections of the FSAR Referencing vendor technical manuals Providing specific quantitative bounds (only if the information cannot be provided in any of the above ways).
Modify the individual test description abstracts presented below to provide adequate acceptance criteria for all items in the respective test summaries or, if applicable, add a paragraph to Subsection 14.2.12 that provides an acceptable description to each of the following unclear terms found in the identified tables.
a)
Acceptable, sufficient, expected rcnge, within limits, limits, verified, demonstrated, accomplished, predicted value, design prediction Table 14.2.12-1 Table 14.2.12-2 pages 2 pages 15 (three) 20 (two) 20 38 29 3
30 6
b)
Cerived from Table 14.2.12-1, page 33 c)
Acceptable stability / values; stable condition; unacceotable Table 14.2.12-2 pages 17 (two) 19 31 d)
In compliance with, verified to function correctly as speci-fied in, described in, designated in, in accordance wit'i; test documents / procedures / documentation, specification, specified configuration.
. d) continued Table 14.2.12-1 pages 3 pages 22 5 (two) 23 7 (two) 24 (two) 8 (two) 27 9
30 10 31 11 (two) 32 12 (two) 33 14 34 15 16a 17 Table 14.2.12-2 pages 2 page 16 7
e)
Respond / function as designated / described, function properly, satisfactory performance, perform adequately, respond / actuate properly, accurately Table 14.2.12-1 pages 5 14 18 19 (two) 16a 33 21 (two) 31 34 13 24 Table 14.2.12-2 pages 3 21 5
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f)
Design engineering, design specifications / requirements /
values / criteria / prediction / standards Table 14.2.12-1 pages 16a (two) 15 l
36 38 L
f) continued Table 14.2.12-2 pages 7 pages 15 8
22 12 29 640.17 In renards.to your Exception Taken to Regulatory (14.2)
Guide 1.68 Rev 2 App. A 5.t; testing of inputs, output, and correct operation of hardware and software necessary to ensure compliance with provisions of the station operating license do need to be verified by providing a test abstract for testing the process computer input, output, and correct operation of hardware and software (safety-related).
640.18 Specify the status of containment prior to fuel loading.
( 14.2.10.1 )
640.19 State that the emergency boron addition system or other (14.2.10.1 ) negative reactivity insertion system will be operable prior to fuel loading.
640.20 Specify the status of protection systems such as interlocks, (14.2.10.1 ) mode switch, and radiation equipment prior to fuel loading.
640.21 Commit to maintaining a display indicating the stat 6s of the
( 14 c2.10.1) core and fuel pool.
640.22 Include setting high-flux scram trips at their lowest value in (14.2.10.2) the initial criticality procedure.
640.23 Include the setting of high-flux scram trips to a value no (14.2.12.2) greater than 20% beyond the power of the next test level during power ascension tests.
640.24 A review of each test level, including extrapolation of DNBR (14.2.12.2) and maximum linear heat rate values to the high-flux trip setpoint for the next power level, along with required approvals prior to ascension to the test level, must be included.
. = _.
l 640.25 State that both neutron and gamma radiation surveys are included 1
( 14.2.12.2 ) in your radiation shielding survey.
Comit to identifying high (page 20) radiation areas per 10 CFR Part 20.
640.26 Expand your unit load steady state test to include measuring
( 14.2.12.2 ) and evaluating the following steady-state core performance (Page 19) parameters:
1.
Flux distributions 2.
Local surface heat flux 3.
Linear heat rate 4.
Departure from nucleate boiling ratio 5.
Maximum average planar linear heat generation rate 6.
Minimum critical power ratio 7.
Quadrant power tilt 640.27 Change your acceptance criteria for the controlling of xenon
( 14.2.12.2) transients to account for expected changes throughout core
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(Page 24) life.
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640.28 Demonstrate the ability to shut down and maintain the reactor
( 14.2.12.2) in a hot standby condition, with a minimum crew from outside J
(Page 32) the control room.
The potential capability for placing the reactor in cold shutdown must also be demonstrated.
640.29 Your Rod Cluster Control Assembly Drop Time Test does not include
( 14.2.12.2 ) retesting for drop times outside the two-sigma limit.
Comi t to retesting each RCCA outside this limit at 1 cast three times.
640.30 Modify your RCCA drop time test acceptance criteria to include
( 14.2.12.2) both hot zero power and cold temperature conditions, with both j
flow and no-flow conditions in the reactor coolant system in order to bound conditions under which scram might be required.
640.31 Include demonstration of proper operating of dashpots (deceler-l
( 14.2.12.2) ating devices) to prevent mechanical damage during RCCA drop l
time testing.
l 640.32 Reactor coolant system flow test must be expanded to include
( 14.2.12.2) the following:
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Establish that vibration levels are acceptable.
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b)
Determine that differential pressure across the fully loaded core and major reactor coolant systen components i
are as predicted for all allowable combinations of pump operation.
c)
Show that piping reactions to transients are as predicted.
640.33 Commit to performing pseudo-rod-ejection test at less than 5%
3
( 14.2.12.2) power.
640.34 In addition to items required by Reg Guide 1.68 Rev. 2 that you
( 14.2.12.2) have omitted, some of your tests are not conducted at sufficient or appropriate power levels. Modify Figure 14.2.11-1 to show the following:
Power Level Pseudo Rod
<5%, >10%
Ejection Process and
<5%, 25% - 10G%
Effluent Monitoring Neutron and
<5%
Gar:ma Radiation i
Survey I
Station Blackout
>10%
Natural Circulation
- 5%
j Test Unit Load Steady
<5%
State Test i
Loss of Control
>10%
j Room Test Feed Water 50%
i Temperature Variation i
Also include at appropriate power levels any test previously I
noted as omitted.
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1 640.35 Preoperational Flow-Induced Vibration Testing of Reactor Internals (3.9.2.4)
(page 3.9-33).
The justification for lack of instrumented tests is insufficient.
Incorporate modifications which will ensure compliance with Regulatory Guide 1.20 Regulatory Position C.3.2.2.
640.36 Cleaning and Contamination Protection Procedures (page 5.2-11).
(5.2.3.4.1)
Preassembly componer.t cleaning does not guarantee system requirements.
Include provisions for after-assembly system cleaning.
Refer to Regulatory Guide 1.37.
1 640.37 Typical System (page 12.3-8).
Modify the current Compliance (12.3.3.4)
Status as presented in Tables 12.3.3-1,
-2,
-3, and -4 to ensure conformity to Regulatory Guide 1.52 Revision 2.
Particularly, a)
Position on Paragraph C.2.d should be altered to include recording of pressure drops and flow rates.
b)
Position on Paragraph C.2.h should be altered to include compliance to IEEE Standard 279 for the design of the instrumentation and equipment controls, c)
Position on Paragraph C.3.c should be altered to include compliance to Revision 2 of Regulatory Guide 1.52.
640.38 Table 14.2.7-1 (page 36) Regulatery Guides.
Include statement (14.2.7.1) of degree of compliance to Regulatory Guide 1.95.
640.39 NRC Regulatory Guides (page 8.1-6).
Justification for exception 2 (8.1.5.2) to Regulatory Guide 1.128 is insufficient.
Include modifications which will guarantee hydrogen concentration limits are maintained in conformance to Regulatory Guide 1.123.
640.40 Evaluation of Compliance with NRC Branch Technical Position RSS 5-1 (App. 5A) on Design Requirements of the Residual Heat Removal System (page SA-1).
Include the following changes to ensure conformance to Regulatory Guide 1.139, a) Modify the appropriate statements which include " loss of offsite power" to "only onsite or only offsite power".
b)
Include statement of assurance that the RHR System is protected frca accidental overpressuri:ation when it is not isolated from the RCS.
640.41 fiodify testino conducted in conformance with Regulatory (14.2)
Guide 1.41 to incoroorate the following:
a)
Provide assurance that all sources of power supply to vital buses are capable of carrying full accident loads.
If some portions of the power supplies carnot be full-load tested, provide justification.
b)
Verify that buses not under test are monitored to verify absence of voltage.
i 640.42 We could not conclude from our review of the preoperational l
(14.2.12.1) test phase description, test abstracts provided in l
Table 14.2.12-1, pp. 1-38, that comprehensive testing is scheduled for several systems and components.
There fore,
i clarify or expand the description of the preoperational l
test phase to address the follnwing:
a)
Page 1, Preoperational Testing of Redundant On-Site Electric Power Systems to Verify Proper Load Group Assignments.
Include in Table 14.2.12-1 test abstract (s) that will ensure conformance to Regulatory Guide 1.41.
i As a minimum a suitable test should assure that each redundant on-site power source and its load group can i
function without any dependence upon any other redundant load group or portion thereof.
b)
Page 2, Reactor Coolant System Thermal Expansion and Constraint.
Expand the abstract te substantiate analytically or by additional measurement the tacit assumption that removal of piping insulation does not misrepresent true pipe expansion and interference.
c)
Page 4, Piping Thermal Expansion.
Table 3.9.2-3 does not exist.
Cite the approcriate table.
The second acceptance criteria is not a comolete sentence.
Complete this sentence to reflect its desired meeting.
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d)
Page 6, Chemical and Volume Control.
The exception to Regulatory Guide 1.68 A.l.b.2, loss of power response has been noted.
State which test (s) include demonstration of the pneumatically and solenoid actuated components to fail safe on loss of power.
e)
Page 7, Rod Control.
Expand the test abstract to include failure response to loss of power.
f)
Page 9, Reactor Protection.
Modify the response time testing to:
1.
Account for process-to-sensor hardware (e.g.,
instrument lines, hydraulic snubbers, sensing lines) delay times; 2.
Provide assurance that the response time of each primary sensor is acceptable; 3.
Account for output of the sensor-to-engineered safety features actuation delay time; 4.
Provide assurance that the total engineered safety features actuation system response time (the sum of the above three time delays) is conservative with respect to the accident analysis assumptions.
Note:
Item 2 can be accomplished by measuring the response time of each sensor during the pre-operational test, stating that the response time of each sensor will be measured by the manufacturer within two years prior to fuel loading, or describing the manufacturer's certification process in sufficient detail for us to conclude that tne sensor response times are in accordance with design.
9)
Page 13, Component Cooling Water System.
Speci fy which test procedure includes the automatic starting of the component cooling water pump.
Modify the 9
committed test to reflect inclusion of the automatic starting of the component cooling water pump.
h) Use of plant specific abbreviations.
For clarity use of plant specific abbreviatier.s is appropriate only af ter definition in the abstract text, e.g., "fluclear Service Water System (RN)".
Modify the following pages of Table 14.2.12-1 to include text definition of plant specific abbreviations:
Topic Abbreviation Pace 15
. Fire Protection System LP (incorre t) 16 Nuclear Service Water System RN and SNSWP 24 Containment Air Vx (incorrect)
In addition, correct the misnomers "LP" and Vx" on pp. 15 and 24.
i)
Page 15, Fire Protection.
Expand the test to include testing of manual and automatic operation of fire detection and alarm systems.
j)
Page 17, Loss of Instrument Air.
Ensure by modification of existing test abstracts, or providing additional abstracts conformance with Regulatory Guide 1.80 Regu-latory Fosition C.1-7.
k)
Page 18, Control Rocm Ventilation.
Expand the test to include demonstration of the duct leak tightness.
1)
Pace 19, Diesel Building Ventilation.
1.
The te?.perature extremes of the test method and acceptance criteria are incompatible.
Modify the temperature extremes of the test method to agree with those of the Acceptance Criteria.
2.
Include in the test abstract description of how the testing of the temperature extremes will be achieved, e.g.:
a)
Emoloy use of chillers and heaters.
b) Data extrapolation c) Other, describe fully.
m)
Page 20, Emergency Diesel Generator 1.
Specify the portions of the Emergency Diesel Generator, Functional Test which will be performed concurrently with the Engineered Safeguards Functional Test.
2.
Modify the test description to include the follcwing:
a.
Include in the test purpose a stipulation for providing power to equipment needed to maintain the plant in a safe condition during an extended loss of power.
b.
Expand the test abstract or provide additional abstracts to assure conformance with Regulatory Guide 1.108 Regulatory Positions C.l.b.(2)-(5),
C.2.a.(3)-(6)/(8)-(9), and C.2.b.
c.
Verify that the acceptance criteria are based on valid tests as defined in Regulatory Guide 1.108 Regulatory Positions C.2.e.
n)
Page 22, Diesel Generator Fuel Oil.
Specify the "known acceptable operating level" in the test method or Acceptance Criteria.
o)
Page 23, Initial Integrated I eak Rate and Structural Integrity of Containment Tests.
The penetration local leak rate preoperational test is mentioned here.
However, an abstract for the afore-mentioned test is unavailable.
Expand Table 14.2.12-1 to include an abstract for the local leak rate preopera-tional test in accordance with Regulatory G;ide 1.68 A.l.i.4.
p)
Page 26, Ice Condenser Region.
The ice condenser inventory used as an acceptance criterion does not correspond to the inventory of Table 6.2.1-2.
Modify the acceptance criteria such that the ice cordenser inventory cited corresponds to that of Table 6.2.1-2.
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Page 28, Electric Hydrogen Recombiner.
Expand the test to include demonstration that containment hydrogen
)
monitoring is functional without the operation of the hydrogen recombiner as required in Regulatory Guide 1.68 i
A.l.h.4.
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Page 31, Engineered Safety Features Actuation.
Expand
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the response time testing to:
j 1.
Account for process-to-sensor hardware (e.g.,
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instrument lines, hydraulic snubbers, sensing
]
lines) delay times; 5) 2.
Provide assurance that the response time of each l
primary sensor is acceptable; 3.
Account for output of the sensor-to-engineered 1
safety features actuation delay time; I
j 4.
Provide assurance that the total engineered safety j
features actuation system response time (the sum l
of the above three time delays) is conservative with respect to the accident analysis assumptions, j
Note:
Item 2 can be accomplished by measuring the 5
response time of each sensor during the pre-i cperational test, stating that the response r
time of each sensor will be measured by the j
manufacturer within two years prior to fuel j
loading, or describing the manufacturer's j
certification process in sufficient detail for us to conclude that the sensor response j
times are in accordance with design.
1 s)
Page 32, Safety Injection System.
Modify the test I
abstract to include verification of the adequacy of the electrical power supply under maximum startup loading conditions.
l t)
Page 33, Containment Spray System. Modify the test abstract to ensure that the air and water tests use i
a common header. The intent is to verify that paths for the air-ficw test of containment ~soray nozzles 1
l overlap the water-flow test paths of the pumos to i
demonstrate that there is no blockage in the flow path.
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. u) Page 34, Spent Fuel Coolina 1.
Expand the test to include testing of the antisiphon device.
2.
The Acceptance Criteria are incomplete.
Expand the Acceptance Criteria such that all items being tested are addressed.
v)
Page 35, Fuel Handling Area Ventilation.
The Acceptance Criteria are incomplete.
Expand the criteria to include criterion (a) for temperature control.
w) Piping System Vibration Acceptance Criterion B(a) is incomplete. !!odify this criterion to clarify its meaning.
(page 38) 640.43
( Table 14.2.7.1 )
a)
Exception to A.l.i Exception applies only to Subsection 20.
Modify header to read A.l. i.20.
b)
Exception to A.l.p Subsection 1.p does not exist.
Cite the appropriate subsection.
Modify the exception to state whether or not the bench test will be performed by the vendor; assure that the appropriate documentation is available, c) Exception to A.4.2 A.4.2 does not exist.
Cite the appropriate subsection.
d) Exception to A.5.m i
Modify justification such that comparison between measured and predicted reactor coolant flows is clear.
6J0.24 Provide a test description or modify the appropriate subsection
( 14. 2.12 ' "? )
that addresses the NUP.EG-0737 requirement I.G.1, training during icw power testing.
640.45 Review of the preoperational test phase description disclosed (14.2.12.1) that the operability of several of the systems and ccmponents listed in Regulatory Guide 1.68 (Revision 2), Appendix A, may not be demonstrated by the preoperational test phase as described in Table 14.2.12-1.
Expand Table 14.2.12-1 to address the following items:
1.a.3 Reactor Internals Vibration Test 1.d.1 Turbine Bypass Valves 1.d.2 Steam Line Atmospheric Dump Valves 1.d.3 Relief Valves 1.d.4 Safety Valves 1.e.3 Main Steam Isolation Valves 1.e.4 Steam Generator Pressure Relief and Safety Valves 1.e.5 Steam Extraction System 1.e.6 Turbine Stop, Control, Bypass, and Intercept Valves 1.e.10 Feedwater Heater and Drain System 1.e.12 Main Condenser Auxiliaries Used for Maintaining Condenser Vacuum 1.g.1 Normal A.C. Power Distribution System 1.g.2 Emergency A.C. Power Distribution System 1.g.4 D.C. System 1.h.6 Ice Condenser Containment Air Return Fans 1.h.8 ECCS Tanks and Othcr ECCS Water Sources 1.h.9 Containment Pecirculation Fans 1.i.2 Containment Isolation Valves 1.i.8 Primary and Secondary Containment Isolation Initiation Logic 1.i.9 Containment Purge Systems 1.i.10 Containment and Containment Annulus Vacuum-Breaker Tests 1.i.21 Containment Penetration Cooling Systems 1.j.3 Secondary System Steam Pressure Control System 1.j.S Reactor Coolant System Leak Detection Systems 1.j.6 Loose Parts Monitoring System 1.j.9 Pressure Control Systems 1.j.10 Seismic Instrumentation 1.j.ll Traversing Incore Probe System 1.j.12 Failed Fuel Detection System 1.j.13 Incore and Excore Neutron Instrumentation 1.j.16 Hotwell Level Control System 1.j.17 Feedwater Heater Temperature, Level, and Bypass Control Systems 1.j.19 Instrumentation and Controls for Shutdown Outside the Control Room 1.j.20 External and Internal Flooding Conditions 1.j.22 Accident Tracing Instrumentation 1.j.25 Process Computers 1.k.2 Personnel Monitors and Radiation Survey Instruments 1.k.3 Laboratory Equipment
- 1. E.1 Liquid Radioactive Waste Handling Systems i. t.2 Gaseous Radioactive Waste Handling Systems
- 1. t. 3 Solid Maste Handling Systems
- 1. E. 5 Condenser Offgas System 1.t.6 Ventilation System Isolation Features 1.z.7 Liquid Radwaste Effluent System 1.t.8 Plant Sampling System 1.m.2 Refueling Equipment 1.m.3 Leak Tests and Operability of Sectionalized Devices and Bellows 1.m.4 Dynamic and Static Load Testing i
1.m.5 Fuel Transfer Devices 1.n.5 Reactor Coolant and Secondary Sampling Systems 1.n.6 Chemistry Control Systems:
Reactor Coolant and Secondary Coolant Systems 1.n.8 Seal Water Systems 1.n.9 Vent and Drain Systems for Contaminated or Potentially Contaminated Systems 1.n.10 Reactor Coolant System Purification and Cleanup 1.n.12 Soron Recovery System 1.n.13 Communication Systems
~ i 1
i 1.n.14.a Heating, Cooling, and Ventilation of Space Housing Engineered Safety Features 1.n.14.b.
Heating, Cooling, and Ventilation of Primary Containment 1.n.14.c Heating, Cooling, and Ventilation of Battery Rooms 1.n.14.e Heating, Cooling, and Ventilation of Auxiliary Buildings
]
1.n.16 Cooling and Heating Systems for the Refueling Water Storage Tank 1.n.18 Heat Tracing and Freeze Protection Systems 1.o.1 Dynamic and Static Load Test 1.o.2 Reactor Component Protective Devices and Interlocks 1.o.3 Equipment Safety Devices i
640.46 A review of the data summaries for PWR licensee event reports I
( 14 9'12) concerning selected instrumentation and control (I&C) components
)
was recently conducted.
This review indicated that a major cause of equipment failure was setpoint drift.
Provide an explanation which describes how the test program at Catawba I
will be conducted to minimize the potential for excessive setpoint drift for safety-related equipment instrumentation i
and control systems.
1 f
640.47 Your test descri'ptions are not sufficiently detailed to ascertain (14.2.12) if the voltage levels at the safety-related buses are opti-mized (for the full load and minimum load conditicns that are l
expected throughout the anticipated range of voltage variations l
of the offsite power source) by appropriate adjustment of the i
j voltage tap settings of the intervening transformers.
Demonstrate j
that the adequacy of the design in this regard is verified by j
actual measurement and by correlation of measured values with
{
analytical results.
Provide a description of the method used for making this verification.
i 1
1 l
t i
l
640.48 (14.2.12.2 )
Review of the startup test phase description revealed that the operability of some systems and components listed in Regulatory Guide 1.68 (Revision 2), Appendix A, may not be demonstrated by the startup test phase as described in Table 14.2.12-2.
Expand Table 14.2.12-2 to address the following items, and at the appropriate test level.
2.
d.
Final reactor coolant system leak rate test.
g.
Final calibration of source-range neutron flux measuring instrumen-
~
tation.
Verification of associated alarms and protective functions.
4.
f.
Radiation surveys h.
Chemical and radiochemistry tests i.
Control rod sequencers and block functions j.
Primary containment ventilation k.
Steam driven engineered safety features 1.
Main steam and branch line isolation valves n.
Control room computer system o.
At temperature control rod scram time testing p.
Pressurizer and main steam relief valves q.
Residual heat removal systems r.
Reactor coolant purification and cleanup systems s.
Reactor vessel internals vibrations u.
Principal plant control systems 5.
f.
Single high worth rod predictions h.
. lod scram time check i.
fleutron flux instrumentation sensitivity j.
Rod runback and partial scram k.
ECCS high-pressure coolant injection systems 1.
Residual or decay heat removal systems n.
n
_~
I I.
n.
Reactor coolant system loose parts monitoring I
o.
Reactor coolant leak detection systems p.
Vibration monitoring j-q.
Failed fuel detection systems r.
Printouts or CRT dispir.ys
'l s.
Principal plant control systems
)
t.
Relief, dump and bypass valves u.
Isolation valves 1
v.
Main steam and feedwater systems w.
Shielding and penetration cooling systems x.
Auxiliary systems
]
y.
Instrumentation systems a.a.
Chemical and radioachemical control systems Gaseous and liquid radioactive waste processing j
c.c.
i e.e.
Primary containment and inerting and purge systems
- f. f.
Ventilation and air conditioning systems g.g.
ATWS equipment h.h.
Design load swing j.j.
Dynamic response to coincident turbine-generator and offsite power losses m.m.
Automatic main steam isolation valves closure o.o.
Vibration and expansions measurement 640.49 Regulatory Guides (page 49), Exceptions to Regulatory Guide 1.140.
(1.8)
Regulatory Positions C.3.1 and C.5 are not justified.
Include discussion to ensure compliance with these positions'.
640.50 Verify operability of the solid and liquid radwaste systems 2,
(14.2) by testing with representative chemical waste streams.
The acceptance criterion for the solid radwaste system should require that there be no free liquid in the solidification sample.
i ERRATA Page Section/ Table Item 1
Table 14.2.12-1 (a) Ti+1e of page 8, " Function" should be
" Functional".
(b) Title of page 10, " System" should be
" Systems".
(c) Title of page 14, " Removal Functional" should be " Removal System Functional".
(d) Title of page 22, " System Test" should be " System Functional Test".
(e) Title of page 23, " Leak Test" should be
" Leak Rate Test".
( f) Title of page 29, " Function" should be
" Functional".
(g) Title of page 35, " Fuel Pool" should be
" Fuel Handling Area".
3
" Abstract" misspelled 4
(TM) " components and" should be " components are".
9 (TM) " selective basis" should be " selective basis,"
17 (P) "penumatic should be " pneumatic" and
" test begins" should be " testing begins".
26 (AC) " temperatures is <20F" should be
" temperature is <20F".
32 "Astract" should be " Abstract".
(TM) injection of small" should be " injection of a small" 35 (TM) "erroc" should be " error" (AC) "Each train" snould be "Each train,".
1 Table 14.2.12-2 Title of page 26, " Ejected Rod" should be
" Rod Ejection". '
ADDITIONAL-tRRATA Pgs. 14-iii and 14-iv Each item must be identified by a page number in the List of Tables and List of Figures.
14.2.5, pg. 14.2-6,,
Replace "could consist" with " consists".
2nd para., 2nd sentence 14.2.5, pg. 14.2-7, Clarify what is meant by "only if a discrepancy 1st para.
exist..." (i.e., discrepancy between what and what).
14.2.5, pg. 14.2-7, Replace "may consist" with " consists".
2nd para.
Table 14.2.7-1, page 2a The number "14.2.7-1" should follow the word
" Table" in the title.
Table 14.2.7 ', page 6, The word " air" is used twice together; delete second exception taken one " air".
Table 14.2.12-1, page 6, Insert the word " water" after "mckeup".
Purpose Table 14.2.12-1, page 9, Insert the word "the" after " timing".
Test Method, 5th line Table 14.2.12-1, page 11, Insert the word "for" after " sink".
Purpose, 3rd line Table 14.2.12-1, page 33, Replace the word "may" with "shall".
Test Method, 2nd para.,
3ra line Appendix SA pace SA-4 Change "aprallel" to " parallel" paqe 5A-9 Change "there" to "these" l