ML20054E111

Forwards Request for Addl Info Re Initial Test Program Described in FSAR as Result of Review of Util Application for OLs

ML20054E111
Person / Time
Site:	River Bend
Issue date:	04/19/1982
From:	Schwencer A Office of Nuclear Reactor Regulation
To:	William Cahill GULF STATES UTILITIES CO.
References
NUDOCS 8204260148
Download: ML20054E111 (21)

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DISTRIBUTION:

Docket File bcc:

PRC APR I 9 1981 LB#2 File

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$fs(dfItdR$r$fC NRC PD'R RTedesco Local PDR (Docket.Hos;:50-458/459 i ASchwencer ACRS /16)

RPerch mgi co, EHylton J

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.O Mr. William J. Cahill, Jr.

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Senior Vice President Region IV River Bend Nuclear Grcup Resident Inspect &

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%, P Gulf States Utilities Company S&maner--

P. O. Box 2951 Rhtth c,

Beaumont, Texas 77704 diThompson.

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Attn: Mr. J.E. Booker EVo N ec 4

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Dear Mr. Cahill:

JStefano

Subject:

River Bend Station, Units 1 and 2 - Request for Additional Information As a result of our review of your application for operating licenses for River Bend Station, we have need for addltional information related to the initial test program described in Chapter 14 of the Final Safety Analysis Report. Attached are the Procedures and Test Review Branch questions for which a response is needed.

Please contact the NRC project manager for your facility within seven (7) days of receipt of this letter to provide your planned response date.

Sincerely, A Schwencer, Chief Licensing Branch No.

• Division of Licensing

Attachment:

As stated cc: See next page f

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. NRC FORM 318 00/80l NRCM O2.tO OFFICIAL RECORD COPY

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V Mr. William J. Cahill, Jr.

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Senior Vice President River Bend Nuclear Group F

Gul f States Utilities Company

-Post Office Box 2951 l}

Beaumont, Texas 77704 ATTN: Mr. J.E. Booker i

cc: Troy B. Conner, Jr., Esquire Conner and Wetterhahn 1747 P.ennsylvania Avenue, NW Washington, 0.C.

20006 Mr. William J. Reed, Jr.

Director - Nuclear Licensing Gul f' States Utilities Company Post Office Box 2951 Beaumont, TX 77704 Stanley Plettm'an, Esquire Orgain, Bell and Tucker Beaumont Savings Building Beaumont, TX 77701 l-l 9

William J. Guste, Jr., Esquire

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Attorney General State of Louisiana

'l P.O. Box 44005 State Capitol Baton Rouge, LA 70804 1

Richard M. Troy, Jr., Esquire

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Assistant Attorney General in Charge State of Louisiana Department of Justice

?34 Loyola Avenue New Orleans. LA 70112 l

A. Bill Beech I

Resident Inspector il P.O. Box 1051

!4 St. Francisville, LA 70775

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REQUESTS FOR ADDITIONAL INFORMATION l

RIVER BEND STATION, UNITS 1 AND 2 I

INITIAL TEST PROGRAM 4

640.1 Regulatory Guide 1.68 - Rev. 2 (Table 1.8-1).

(1.8)

Address the following:

(14.2.7) 1.

Modify your exceptions to Appendix A, Positions 1.c and 5.g.g, to provide a commitment to include in your test program any design features to prevent j

f or mitigate anticipated transients without scram (AlWS) that may in the future be incorporated into your plant design.

2.

The staff recognizes that there is currently no Loose Parts Monitoring System at the River Bend Station.

Commit to the test requirements of Appendix A, Positions 1.j(6) and 5.n, for such systems that may be installed in the future.

]

3.

Verify that sources of water used for Long-term core i

cooling are tested to demonstrate adequate NPSH and the absence of vortexing over range of basin level from i

maximum to the minimum calculated 30 days following LOCA.

I i

(Clarification of Appendix A, Position 1.h(10).)

640.2 Regulatory Guide 1.68.2-Rev.1 (Table 1.8-1).

The

(.l. 81 exception to Position C.4(c) is not acceptable.

(14.2. 7)

Submit additional technical justification for exclusion of

j establishing a heat transfer path to the ultimate heat sink, or delete the exception and modify the appropriate test abstracts.

640.3 Include a description of the test (s) that will be performed (14.2.12) to ensure conformance to Regulatory Guide 1.95, Protection of Nuclear Power Plant Control Room Operators Against an l

Accidental Chlorine Release.

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c-640.4 The staff was unable to determine that sufficient q.

(14.2.12) preoperational and startup testing of the residual i

heat removal systcm is to be performed such that the operability requirements of Regulatory l

Guide 1.139 (subsection C.5, parts a and b) would be adequately demonstrated.

Modify the preoperational test 14.2.12.1.5, Residual Heat Removal Systemi appro-j priately and provide startup test abstracts which

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satisfy Regulatory Gu.ide 1.139.

640.5 Verify that the completion of the required pre-(14. 2.1. 2 )

perational testing that is required prior to (14. 2. 5 )

(14.2.10.1) fuel l o a d i r.g includes review and approval of test (14.2.12)

. results.

If portions of any preoperational tests are intended to be conducted, or their results app oved, after fuel loading:

(1 ) List each test; (2) state what portions of each test will be delayed until after fuel loading; (3) provide technical justification for delaying these portions; and (4) state when each test will be comple:ed (key to test conditions defined in Chapter 14).

Note that any test that you do nc.t intend to begin prior to fuel loading should be included in your startup test phase instead of the preoperational test phase.

Modify the appropriate sections of Char er 14 acccrdingly.

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i 640.6 Certain terminology used in the individual. test 0

clearly indicate the source j

(14.2.12) description does not t

of the acceptance criteria to be used in deterrnining

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l test adequacy) an acceptaole format for prov id ing d

acceptance criteria for test results includes any l

of the following:

i Referencing technical specifications (Chapter 16),

l Referencing accident analysis ( C h a pt e r.15),

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i Referencing other specific sections of the FSAR

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.f (e.g., 7. 4.1. 2 ),

Referencing vendor technical manualse Providing specific quantitative bounds (only if the information cannot be provided in any of

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the above ways).

Modify the individual test description abstracts

'4j presented below to p r c.v i d e adequate acceptance i

criteria for all items in the r,espective test summaries ore if applicabler add a paragraph to i

Subsection 14.2.12 that provides an acceptable j

i description to each of the following unclear

'l terms found in the identified subsections of Subsection 14.2.12.

(1)

Specified, specified by the manufacturer technical specificationse test specificationse I

test specification limits, within limits of test specificationi stated in test specifi-cations, accordance with test specificationse

!1 consistent with test specifications, tolerances i 1

!1 of the test specifications, criteria of the test specifications, test specification

!S requirementse water quality specificatione l) water chemistry specificationse RPS specifi-fj cations, accordance with vendor specifications

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i 1.1.4.d; 1.2.4.b; 1.3.4.bidierh;

,' l 1.4.4.arbicie; 1.5.4.bec; 1.6.4.arb; 1

'i 1.7.4.arb; 1.8.4.arbic; 1.9.4.aebec;

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1.10.4.aibic; 1.11.4.arcid; 1.12.4. arced; 1.14.4; 1.15.4; 1.16.4.aebid; 1.17.4; 1

1.18.4.a,becid; 1.19.4.a;bec; 1.20.4.a,bec; a

1.22.4.arbierfig; 1.24.4.arbiced; 1. 2 6. 4. a ib ;

.I 1.27.4.aib; 1.28.4.aibicidifigeh; 1.29.4.aibi j

ced; 1.31.4.a,d; 1.32.4; 1.33.4.brere; f

1.34.4.ard; 1.36.4.cidre; 1.38.4.aibiced; 1.41.4.a,b; 1.42.4; 1.43.4.b; 1.44.4.a,b; i

1.45.4.arb; 1.46.4.a,bec; 1.47.4.arcid; 1.48.4.arbicidif; 151. 4. a r b i c ; 1.54.4; 1.62.4; 1.65.4.aib; 3.1.4; 3.10.4; 3.16.4; 3.24.4; 3.33.4 (2)

Correct, correctly, proper, propertyr functions propertyr functions correctly, intended functioni functior, responds ccrrectly 1.3.4.c; 1.4.4.f; 1.5.4.a,b; 1.6.4.arcid; 1.7.4.cid; 1.8.4.c; 1.12.4.c; 1.13.4.a,bec; 1.16.4.cre; 1.19.4.d; 1.21.4.arb,c; 1.36.4.b; 1.47.4.b; 1.48.4.e; 1.49.4.b; 1.60.4.a;

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3.28.4; 3.20.4 4

(3)

Functionally verifiede verified operatiorale performance is verified, verified, operational 1

1 1.1.4.aib; 1.2.4.a; 1.23.4.a,bec; 1.25.4.

arbic; 1.40.4.arbicid; 1.44.4.g; 1.49.4.a; 1.55.4.a; 1.56.4; 1.57.4.arbic; 1.58.4.a,br cid; 1.59.4.b; 1.60.4.a; 1.61.4-(4)

Within limitse within allowable limits, within the prescribede within the designe lower limite limit specified, set point, high t er.p e r a t u r e set pointe license limitationi meets test limits

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(5)

Requirede requirements, all required 1.3.4.a; 1.4.4.d; 1.33.4.a; 1.35.4.a;

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1.43.a; 1.65.4.a; 3.6.4; 3.12.4,

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(6)

Rated 1.8.4.c; 1.22.4.c; 1.39.'4.b; 1.44.4.c; 3.10.4; 3.12.4; 3.16.4; 3.19.4; 3.20.2.4; 3.30.4

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(7)

Adequates adequately, acceptabler sufficiente k

satisfactory, successfully 3

1.4.4.d; 1.5.4.are; 1. 6.4. f ; 1.18. 4. e ;

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~4 1.48.4.g; 3.22.4; 3.27.5.4; 3.28.4 i

4 1

(8)

Predicted valuer calculated valuer calculated displacemente as designed, design points t

i.

1.7.4.c; 1.8.4.c; 3.9.4; 3.14.4; 3.20.3.4; 3.29.4 3l j

(9)

Demonstrated operabler capable of operatinge

.i each demonstratione operation--demonstratede a

ability--demonstrated

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1.44.4.f; 1.55.4.b; 1.60.4.a; 1.64.4.a,b; i

i 3.32.4 (10)

Scram trip setting, trip setting, high pressure 4

scram setting 3

3.21.4 I

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(11)

Precalculated--rates Lii!

3.27.2.4 i

(12)

System related variable to any test input, process 1

1 variable 3.18.4; 3.20.2.4; 3.19.4; 3.23.4 i1 (13) Process diagrams t

3.31.4; 3.32.4 l j i i (14) Capacities 1.31.4.b

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(15) Differe.ntial Pressure i

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-b (16) Maximum reactor pressure 3.22.4

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(17) Assumed value in FSAR 3.20.4.4 (18) Minimum core flow 3.21.4 1

(19) Minimum 1.58.4.c i

(20) Normal 1.36.4.e; 1.39.4. arc; i

(21) Operates as tested 4

1.34.4.b i-(22) Selected 4

1.18.4.e (23) Not significantly greater i

t 3.24.4 t

I 640.7 Identify any of the post-fuel loading tests (14.2.12) described in Section 14.2 which are not essential towards the decorstration of conformance with design requirements for structures, systems, components, and design leatures that meet any I

of the following criteria:

3 l

(1)

Will be relied upon for safe shutdown and i,

cooldown of the reactor under normal plant a

cenditions and for maintaining the reactor i

in a safe cor.ditior for-an extended shutdown period.

(2)

Will be relied upon for safe shutdown and cooldown of the reactor under transient (infrequent or moderately frequent events) conditions and postulated accident conditions, and for maintaining the reactor in a safe con-1 dition for-an' extended shutdown period following such conditions.

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4 (3)

Will be relied upon for establishing con-formance with safety limits or limiting l

conditions for operation that will be included in the facility technical specifications.

(4)

Are classified as engineered safety features or will be relied upor~ to support or assure.

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the operation of engineered safety features within design limits.

(5)

Are assumed to function or for which credit n

is taken in the accident analysis for the facility (as described in the Final Safety

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Analysis Report).

3 (6)

Will be utilized to processi storer control, or limit the release of radioactive materials.

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j 640.8 Review of the preoperational and startup test phase (14.2.12.1) descriptions disclosed tFat the operability of

'lj several of the systems and components l i s 't e d in 1

/

Regulatory Guide 1.68 (Revision 2) Appendix A may not be deconstrat'ed.

Expand your test descriptions to address the following items:

1 i

i (1)

Preoperational Testing

)i

1. a (2) ( g)

Instrumentation used for mon'itoring 1;j system performance or performing permissive and prohibit interlock i

.a t w (1

functions-l1 1.e(12)

Main condenser auxiliaries'for main-

.t.

tj t a taining condenser vacuum 1.g(2)

Emergency A.C.

power distribution system

't 1.h Suppression pool makeup system 1.h(9)

Verify that containment recirculation fan motor current is within' its design

? r velue at conditions representative of j

.a accident c on d i t i'o n s.

Address such issues c j as air density, temperaturer humidityr a

fan speeds and blade angle.

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. Containment design overpressure

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structural tests and vacuum test J

1.i(8)

Primary and secondary containment isolation initiation logic tests 1.i(10)

' Containment and containment annulus vacuum-breaker tests 1.i(11)

Containment supplementary leak collection

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nd exhaust system tests

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Containment air purification and cleanup system tests 1.'i (13 )

Containment inerting system tests 1.i(16)

Containment ventilation system tests 4

i 1.i(17)

Secondary containment system ventilation

j tests 1

l 1.i(21)

Containment penetration cooling system i

tests y

j 1.j(8)

Automatic reactor power control system

1. j (12)

Failed fuel detection system 1.j(18)

Auxiliary startup instrument tests I

(neutron response checks) i

?-

1 1.j(20)

Instrunentation used to detect external

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and internal flooding that could result

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from such sources as fluid system piping 1

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' lI failures 1.j(21)

Reactor mode switch and associated i

functions

.)

1.j(22)

Instrumentatior. that can be used to track the course of postulated accidents such as containment wide-range pressure indi-i cators, r;eactor vessel water level

(

monitors, pressure suppression level t

monitors, high range radiation detection devices, and hum'dity monitors l

9 of 18 4

.)

1.j(24)

Annunciation for reactor control and

.i engineered safety features 3

.1 1.m(3)

Operability and leak tests of section-

- I alizing devices and drains and leak 1

tests of gaskets or bellows in the 5

1 refueling canal and fuel storage pool i.t 1.n(8)

Seal water systems r

1.n(9)

Vent and drain systems for contaminated or potentially contaminated systems and I

areas and drain and pumping systems t

serving essential areas, e.g.,

spaces I

J housing diesel generators, essential electrical equipment and essential j

1

, i, pumps dj

1. n ( 14 ) ( c )

Battery rooms heating, cooling and I

ventilation systems 1

l 1.n(18)

Heat tracing and freeze protection systems

')

(2)

Initial Fuel Loading and Precriticai Tests g

l 2.b control rod decelerating devices 2.c Final functional testing of reactor i

protection system

?.

(4)

Low Power Testing i

4.k Steam-driven engineered safety features i

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l (5)

Power-Ascension Tests

,l 5.w Provide a startup test description that will demonstrate that ccncrete temperatures surrounding hot penetrations do not exceed design limits.

5.h.h Plant dynamic response to load swings.

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10 of 18 ie 1

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640.9 14.2.12.1.1.

Expand the Feedwater System Acceptance (14.2.12.1)

Test to address:

)

(1)

Pump performance requirements including flow

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'1 rates, headi suction heads and overspeed t

11 characteristics.

ll (2)

Proper operation of controls used for manual l

and autcmatic starting and stopping of the

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peep drivers.

(3)

Feedwcter flow rate adjusting valves.

Verify proper response of the valves over the operating range and correct operation of protective features such as thermal overload and under-voltage sensing devices of the valve operatcrs l

]

and a s s c c i a t'e d control circuitry.

640.10 14.2.12.1.5. Expand the Residual Heat Removal System j

(14.2.12.1)

Preoperational Test to provide acceptance. criteria for the following safeguard and operational functions:

LPCIr Suppression pool cooling, shutdown ecolinge steam :ondensing.

l 640.11 14.2.12.1.10. Expand the Reactor Recirculation J

]

(14.2.12.1)

System Preoperational Test to provide acceptance criteria for Test Ob j ectives 1.d and 1.e.

)

640.12 14.2.12.1.11 Expand the Control Rod Drive Hydraulic (14.2.12.1)

System Preoperational Test to ensure that the failure aj mode of ti.: control rod drive system is correct on 1

jh loss of power.

640.13 14.2.12.1.12 Expand the Fuel Handling and Vessel (14.2.12.1)

Servicing Equipment Preoperational Test to ensure that other crane hoistsi and associated lifting and rigging equipmenti are static tested at 125 percent of rated load and are full operational ij 3

tested at 100 percent of ratee loed.

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11 of 18

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1 640.14 14.2.12.1.14 Expand the Feedwater Control System

]

Preoperational Test to include testing which (14.2.12.1)

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verif es the proper response of system components f

(programmers, summers, and signal modifiers).

4

.R Verify operability of sensors and associated i4l instruments which provide input into the feedwater control system.

Verify that the outputs in response i

+

to test signals are stable and accurate.

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i 640.15 14.2.12.1.15 Expand the Leak Detection' System (14.2.12.1)

Preoperational Test to provide acceptance, criteria 1

f or the recorderse alarms, and indicators.

640.16 14.2.12.1.22 Expand the Fuel Rod Cooling and (14.2.12.1)

Cleanup System Preoperational Test to include terting of antisiphon devices, high radiation 4

alarms, and low water level alarms.

Provide

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]

acceptance criteria for containment i's o l a t i on I

valve isolation and operability of remotely

}

centrolled valves.

. 1, 1

640.17 14.2.12.1.24, Expand the Combustible Gas Control 1

i, (14.2.12.1)

System Preoperational Test to provide acceptance i

criteria for the hydrogen monitors.

640.18 14.2.12.1.28 Expand the Control Beilding HVAC (14.2.12.1)

Frecperational Test to include testing of radiation monitors, chlorine monitorsi and smoke detectors which are interlocked with the control room HVAC.

1 640.19, 14.2.12.1.28, 14.2.12.1.34, 14.2.12.1.47 Expand (14.2.12.1) 14.2.12.1.28, Control Building HVACr and 14.2.12.1.34, Standby Gas Treatment System, to include in place DOP testing for HEPA filters'and halogenated hydrocarbon refrigerant testing for 4

the charcoal adsorbers.

Expand 14.2.12.1.47, d

i Fuel Buildine HVAC, to include halogenated hydro-carbon refrigerant testing of the charcoal adsorbers.

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t 12 o f 18 1.

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640.20 Provide test, descriptions that will verify that (14.2.12.1) the emergency ventilation systems are capable of maintaining all ESF equipment within their design

-i temperature' range with the equipment cperating l3{

J in a manner that wiLL produce the maximum heat toad in the compartment.

If it is r.o practical

]n to produce maximum heat loads in a cocpartment, describe the methods that will be used to verify r

design heat removal capability of the e.mergency ventilation systems.

Note that it is not apparent that pc s t -a c c i den t i

design heat loads will be produced in ESF equip-ment rooms during the power ascensicn test phase; l

i l4 therefore, simply assuring that area temperatures J

i i

remain within design limits during this period will probably not demonstrate the design heat removal capability of these systems.

It will be 1

necessary to include measurement of air and cool-I, ing water temperatures and flows anc the extrapo-

)i lations used to verify that the ven iiation systems can remove +he postulated post-accicert heat loads.

6 640.21 14.2.12.33.

Expand the Reactor Plart Ventila-i 1j (14.2.12.1) tion System Preoperational test to crevide accept-ance criteria for those components er' processes i

t I

described in Test Objectives 1.b, 1.c, and 1.e.

1

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640.22 14.2.12.1.35.

Expand the Remote Shutdown System l5 (14.2.12.1)

Preoperational Test to specify'the portions of

,?

the described test which are to be pe r formed with l

other specified tests.

Modify the appropriate abstracts accordingly.

640.23 14.2.12.1.36.

Expand the Standby Diesel Generator

!5 (14.2.12.1)

Preoperational test to include demor.stration of diesel' starting ability with the design minimum starting air available.

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13 of 18 640.24 14.2.12.1.37,.

Modify the Vessel Internals Vibra-

-5 (14.2.12.1) tion Preoperational test as follows:

(1) Expand this test and provide appropriate startup test abstracts to address the per-l formance commitments made in Subsections 3.9.2.48 and 3.9.2.68.

I (2) Clarify the disposition of fuel assemblies during the preoperational test as per Regula-j s

tory Guide 1.20 Section C.2.2.c.

(3) Expand the acceptance criteria to include a) evaluation of vibra *.ional data for con-j sistency with predicted values and b) check of flush cloths for particulate speckling.

640.25 14.2.12.1.39.

Expand the Class 1E 125 V DC (14.2.12.1)

System Preoperational Test to verify that individ-val cell limits are not exceeded during the design discharge test and to demonstrate that the DC loads will function as necessary to assure plant safety at a battery terminal vol age equal to the acceptance criterion that has been established for minimum battery terminal vol: age for the dis-charge load test.

640.26 Testing in conformance with Reguiatory Guide 1.41 (14.2.12.1) must incorporate the following:

(1) Provide assurance that all sources of power supply to vital buses are cacable of carrying full accident loads.

If some. portions of the power supplies cannot be full-load tested, provide justification.

(2) Verify achievement of stable operation during each test.

(3) Verify that testing is condu:ted with only one power source at a ti'me.

(4) Verify that buses not under test are monitored i

to verify absence of voltage.

i 14 of 18 l4 2

640.27 14.2.12.1.45.

Expand the Auxiliary Building 4

l (14.2.12.1) ventilation System Preoperational Test to demon-d strate the system's ability to supply the required air flow to the auxiliary buildings.

640.28 14.2.12.1.46.

Expand the Radwaste Building Ventil-4q (14.2.12.1) ation System Preoperational Test to demonstrate the system's ability to supply air flow to various q

.i areas.

l j

640.29 14.2.12.1.47.

Expand the Fuel Building Ventila-j Preoperational Test to provide accept-(14.2.12.1) tion System

]

differential between ance criteria for the pressure l

the various areas maintained by the fuel build-ing ventilation system and the outside atmosphere.

640.30 14.2.12.1.49.

Expand the Turbine Building Ventil-j (14.2.12.1) ation System Preoperational Test to include veri-fication of air flow.

i 640.31 14.2.12.1.50.

Expand the Instrument and' Service v

(14.2.12.1)

Air System Acceptance Test as f'o l l ow s :

i

'l (1) Expand the test prerequisites to encompass f

those cited in Regulatory Guide 1.80, Pre-operational Testing of Instrument Air Systems.

"1 1

(2) Include testing of all the components and

'l systems referred to in Regulatory Guide 1.80,

]

Section C.2-C.7.

l

4 (3) Identify the systems that are dependent on

)

instrument air and are to be tested and those

.)l that are not going to be tested.

j (4)' Provide the following:

' J f j (a) Sufficiently detailed test abstracts for

! 4 i :

those systems or components, dependent on instrument air, that are to be tested.

a (b) Sufficiently detailed technical justifica-tions for not testing those systems dependent on instrument air.

l

b 15 of 18 3

640.32 14.2.12.1.51.

Expand the 13.8 kV and 4160 V l-(14.2.12.1)

Distribution System Preoperational Test to provide acceptance criteria for test objectives 1.a and1.6.

640.33 14.2.12.1.56.

Expand the Cranes Acceptance test (14.2.12.1) to ensure that static testing is performed at 125 percent of rated load and f ull operational

)

testing at 100 percent of rated load.

't 4,

640.34 14.2.12.1.58.

Expand the Condensate Acceptance j

(14.2.12.1) test to address:

(.) Pump pe'rformance requirements including flow 1'

rates, head, suction head, and overspeed characteristics.

J l

-( 2 ) Proper operation of contrcls used for manual 4

and automatic starting and stopping of the punp drivers.

f~j) 640.35 A number of startup tests fail to quantif.y test-1 (14.2.12.3) ing power levels or use such r.on-specific descrip-1 tions as

...at selected. reactor power levels...",

...near rated conditions...",

"...as high a power i

as necessary...", or

...a moderate power level sufficiently high...".

Include a table of all startuo tests and associated test condition regions V

as identified in Figure 14.2-4, Start-up and J

l Test Condition Flow Map.

1 640.36 14.2.12.3.4.

Expand the full Core Shutdown Margin I

(14.2.12.3) test to cuantify " additional margin for exposure" i s' as used in the Level 1 Acceptance Criteria and J4 i

either provide this margin or state when it-will be available.

j 640.37-14.2.12.3.5.

Expand the Control Rod Drive System 1

{

(14.2.12.3) test Level 1 Acceptance Criteria to require that i,

the maximum scram times of all CRos shall be 1

re-evaluated and shall meet the criteria in t

Line 3 (given that initially any CRD scram time exceeded a Line 1 value).

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16 of 18 lj' ll 640.38 14.2.12.3.,12.

Our review of licensee event reports

,I (14.2.12.3) has disclosed several instances o1 RCIC pump fail-

)

ure to start on demand.

It appears that many of i

these failures could have been avoided if more thorough testing had been conducted during the plant's initial test programs.

In order to dis-cover any problems affecting pump startup and to demonstrate the reliability of your emergency

':j cooling system, state your plans to demonstrate i

at least five consecutive, successful, cold, i

quick pump starts during your initial test pro-gram.

640.39 14.2.12.3.20.

Expand the appropriate Feedwater (14.2!12.3) system tests to address the following items addressed by Regulatory Guide 1.68.1, Section C:

><Il

')

(1) 2.2(a)

Feedwater operability.

l (2) 2.2(b)

Feedwater control system res,ponse in canual mode of control.

Transfer to automatic mode of control.

(3) 2.2(c)

Autcmatic control system stability

,i 4

and response characteristics.

(4) 2.2(d)

Automatic control system stability 5

ano response following plant trans-l i

ients.

??

(5) 2.2(f)

Vibration levels.

1 4

(6) 2.2(g)

Piping covements.

i I

2 (7) 2.2(h)

Margins between system variables

.'I and instrument setpoints.

t (8) 2.2(i)

Operation using condensate storage f

I2 system (9) 2.2(j)

Operation with alternative electric pouer sources.

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640.40 14.2.12.3.24.

Expand the Turbine Trip and Generator 1

(14.2.12.3)

Load Rejection test to et.sure that both trips are conducted at full rated power, or provide technical justification that shows how the test

]

purpose can be met without accomplishing both full power! trips.

A sufficient technical justification would be if the turbine trip is initiated directly by all i

remote-manual openings or automatic trips of the i

generator main breaker, i.e.,

a direct electrical signal, not a secondary effect such as turbine overspeed.

The method used for opening the main generator breakers (by simulating an automatic or manual trip) should be selected such that the y

turbine-generator will be subjected to the maxi-i l

mum credible overspeed condition.

f

]

640.41 14.2.12.3.15.

Expand the Shutdown from 0.utside i

]

(14.2.12.3) the Main control Room test to address the follow-ing items of R e g~u l a t o r y Guide 1.68.2:

l!

(1)

C.2(b)

Cccmunications i

(2)

C.2(c)

Authority and responsibility of

,3 control room observers l

(3)

C.3 Initial reactor power level at 10-25%

(4)

C.3(b)

Maintenance of hot standby condi-j lj I

tion for 30 minutes.

! l (5)

C.4(d)

Reduction of reactor coolant tempera-lj ture by at least 500F.

I

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640.42 14.2.12.3.28.

Modify the Loss of Turbine-Generator (14.2.12.3) and Offsite Power test to maintain loss of off-1 site power for at least 30 minutes.

640.43 Modify your FSAR to describe tests and training to comply with NUREG-0737 Item I.G.1.

Refer to LRG-II position 1-HFS.

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l The following Regulatory Guides were referenced in the River rj Bend questions.

Regulatory Guide 1.41, "Preoperational Testing of Redundant Onsite Electric Power. Systems to Verify Proper Load Group Assignments".

1 Regulatory Guide 1.68 (Rev'ision 2), " Initial Test Programs l

for Water-Cooled Nuclear Power Plants".

1

]

Regulatory Guide 1.68.1 (Revision 1), "Preoperational and

'i j

Initial Startup Testing of Feedwater and Condensate Systems

')

for Boiling Water Feactor Power Plants".

1 Regulatory Guide 1.68.2 (Revision 1), " Initial Startup Test 1

Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants".

Regulatory Guide 1.80, "Preoperational Testing of Instrument Air Systems".

.j l

.l Regulatory Guide 1.95 (Revision 1), " Protection of Nuclear j

Power Plant Control Room Operators Against an Accidental i

Chlorine Release".

f l

Regulatory Guide 1.139, " Guidance for Residual Heat Removal".

1 1

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.j Errata Page Section Item

.1 14-ii 14.2.12.1.5 "14.2-29" should be "14.2-28" 14.2-2 14.2.1.3

" extend" should be " extends" j

14.2-14 14.2.3.1 "GE design" should be "GE, design" 14.2-44 14.2.12.1.13

" control, circuitry" should be

" control circuitry" d

14.2-106 14.2.12.3.2.4

" radiation" misspelled.

14.2-108 14.2.12.3.4.2.c "a noise" should be "a signal-to-noise" 14.2-145 14.2.12.3.27.2.3 "testated" should be changed to the appropriate power level.

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