ML18051A241

Forwards Safety Evaluation & Technical Evaluation Rept Re TMI Action Item II.E.1.2, Auxiliary Feedwater Sys Automatic Initiation & Flow Indication. Sys Comply W/Nrc long-term Safety Requirements

ML18051A241
Person / Time
Site:	Palisades
Issue date:	12/16/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
Shared Package
ML18051A242	List: ML18051A241
References
TASK-2.E.1.2, TASK-TM LSO5-82-12-036, LSO5-82-12-36, NUDOCS 8212210459
Download: ML18051A241 (19)

Text

. '.

December 16, 1982 DISTRIBUTION Docket Docket No. 50-255 LS05-82-12-036 NRC PDR Local PDR ORB Reading NSIC DCrutchfield HSmith TWambach OELD ELJordan JMTayl or ACRS ( 10)

SEPB f*1r. David J. V ande~J a 11 e Nuclear Licensing Administrator Consumers PovJer Company 1945 West Parnall Road Jackson 9 Michigan 49201

SUBJECT:

AUXILIARY FEED\\*JATER SYSTEM AUTOMATIC INITIATION AND FLmJ INDICATION (TMI ACTION PLJ.i.N ITEH II.E.1.2)

.Palisades Plant The NRC staff nas completed the revietv of the auxiliary feedwater system automatic initiation and flow indication for Palisades.

Enclosed are the staff's Safety Evaluation and a Technical Evalu-ation Report prepared by our contractor~ the Franklin Research Center.

Ue conclude that the Palisades auxHiary feedwater automatic initiation and flmJ indication systems comply with the NRC staff's long-term safety grade requirements.

Sincerely, S

~~1 Original signed by t:::"""""'

Thomas V. Wambach for/

Dennis M. Crutchfield~ Chief

"'(** *. r b /0 'f)

Operating Reactors Branch #5

~~ ~ ~ ~

Division of Licensing Enc 1 osures:.

l. Safety Evaluation

2. Technical Evaluation cc w/enclosures:

See next pa9e OFFICE~ ~&-p9.~.~****.Q.~.if.P~*........................................................................

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DATE~ ll..:.. !.l.~!.~.~---*11../~/If?/~~---**........................................................................

NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960

Mr. David J. VandeWalle cc M. I. Miller, Esquire Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201

~ James G. Keppler, Regional Administrator Nuclear Regulatory ColTlllission, Region III 799 Roosevelt Road Glen Ellyn, Illinois: 60137 Township Supervisor

• Covert Townshi Route 1, Box 10 Van Buren County, Michigan. 49043 Office of the Governor (2)

~oom l - Capitol Building Lansing, Michigan 48913 Palisades Plant ATTN:

Mr. Robert Montross Plant Manager Covert, Michigan 49043 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:

Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 Resident Inspector c/o U. S. NRC Pali sades Pl ant Route 2, P. O. Box 155 Covert, Michigan 49043 December 16, 1982

. -~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 SAFETY EVALUATION PALISADES - AUXILIARY FEEDWATER AUTOMATIC INITIATION AND FLOW INDICATION TMI ACTION PLAN ITEM II.E.

1.2 INTRODUCTION

AND

SUMMARY

To improve the reliability of Auxiliary Feedwater Systems (AFWS) at pressurized water reactor (PWR) facilities, the staff is requiring licensees to upgrade the system where necessary to ensure safety grade automatic initiation and flow indication. The criteria for

• this upgrading are contained in NUREG-0737 (Clarifications of TMI

• Action Plan Requirements),Section II.E.1.2.

The evaluation of the Palisades AFWS design was performed for the NRC by Franklin Research Center {FRC) as part of a technical assistance contract program.

The results of the FRC evaluation are reported in the attached Technital Evaluation Report (TER-C5257-298).

Based on our review.of the FRC TER and a subsequent submittal from --_:-:

the licensee, we conclude that AFWS automatic initiation and flow indication designs ~re acceptable.

EVALUATION The attached TER provides a techncial evaluation of the electrical, instrumentation, and control design aspects of the Palisades AFWS.

with regard to automatic initiation and flow indication. The TER notes that upon a loss of offsite power, the motor-driven AFW pumps are not _automatically sequenced onto the diesel generator. -This does not meet the requirements of Position 6 of NUREG-07~7, Item II.E.1.2. The license~ has subsequently informed us by l~tter dated September 30, 1982 that.it is their intent to provide this automatic sequencing of the motor-driven pumps onto the diesel gener?tors.

The Palisades Technical Specifications currently require periodic testing of the AFWS automatic actuation logic. This requirement was added to the Technical Specifications by Amendment 67 dated October 8, 1981.

The present Palisades Technical Specifications are consistent with the two auxiliary feedwater pumps that are part of the AFWS.

The licensee has proposed a*dding a third pump to the system and the review was based on this three pump AFW system.

As.such, section 3.5 (Steam and Feedwater Systems) of the Palisades Technical

Specifications will need to be revised at a time appropriate to the installation and operation of the third pump to reflect the upgraded auxiliary feedwater system.

The environmental qualification of safety related systems including AFWS circuits and components is being reviewed by the Environmental Qualification Branch as part of their review of licensee responses to "Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipment in Operating Reactors, 11 issued to the licensee in NRR letter dated March 5, 1980.

In order to adequately determine from the control room the performance of the AFWS, steam generator level instrumentati6n is used,'in addition to flow indication. The requirements for this steam generator level instrumentation are specified in Regulatory Guide 1.97 Revision 2 (R.G. 1.97) -

11 Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident 11 ).

CONCLUSIONS Based on our review:of the Franklin Research Center TER, and the licensee's submittaJ dated September 30, 1982, we conclude that the Palisades AFWS automatic initiation and flow indication*system~ when fully complete~ comply with the staff's long-term safety grade requirements and are acceptable.

f-.

TECHNICAL EVALUATION REPORT AUXILIARY F*EEDWATER SYSTEM AUTOl\\1ATIC INITIATION AND FLOW INDICATION-i' CONSUMERS POWER COMPANY l! PALISADES PLANT

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NRC DOCKET NO. 50-255 NRCTACNO. 11732 NRC CONTRACT NO. NRC-03-79-118 Prepared by Franklin Reseatcti.Center

.20th and Race Street Philadelphia, PA _19103 Prepared for Nuclear Regu!ato*ry Commission Washington, D.C. *20555 September 8, 1982 FRC PROJECT C5257 FRC ASSIGNMENT 9 FRCTASK 298 Author: J. E. Kaucher FRC Group Leader: K. Fertner Lead NRC Engineer: R. Kendall M. Wigdor This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owne~ rights.

Pr~ared by:

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Group Lead~r Date: 71 [-/ f 7-r/J(fj/qpf¢.1-i~~. ~

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~Li~ ffianklin Research Cent~r A Division of *The Franklin Institute The Bcnjomin Frenklin Perkwey, Phila.. Pe. 19103 (215) 448-1000

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• TER-C5257-298 CONTENTS

=:.

Section Title 1

3 INTRODUCTION

• 1.1 Purpose of Review 1.2 Generic Issue Background :

1.3 Plant-Specific Background TECHNICAL EVALUATION

• 3.1 General Description of Auxiliary Feedwater System 3.2 Automat1c Initiation.

i 3.2.l Evaluation 3.2.2 Conclusion 3.3 Flow Indication o

3.3.l Evaluation 3.3.2 Conclusion 3.4 Description of Stearn Generator Level Indication 4

CONCLUSIONS 5 '

REFERENCES

~

iii

• .:~~Franklin Research Center Page 1

1 1

2 3

5 5

5 5

a.

8 8

8 9

10

µ_1

~..;_.

TER-C5257-29 8 FOREW'.)RD This Technical Evaluation Report was prepared by Franklin Research. Center under a contract with the U.S. Nuclear Regulatory Commission (Office of Nuclear Reactor Regulation, *oivisio? of Operating Reactors) for technical assistance in support of NRC operating reactor licensing actions. "The technical evaluation was conducted in accordance with criteria established by the NRC.

Mr. J. E. Kaucher contributed to the technical preparation of this report

. through a subcontract with VC:STEC Services, Inc.

'\\..'

~

v

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. _* __ frari,~in Research Cente~.

TER-C5257-298

1. - INTRODUCTION 1.1 PURPOSE OF REVIEW The ~urpose of this review is to provide a technical evaluation of.the emergency feedwater system design to verify that both safety-grade automatic initiation circuitry and flow indication are provided at the Palisades Nuclear Power Plant.

In addition, the steam generator level indication available at the Palisades plant is described to assis.t subsequent NRC staff rev-iew.

• 1.2 GENERIC ISSUE BACKGROUND A post-accident design review by the Nuclear Regulatory Commission (NRC) after the March 28,.1979 incident at Three Mile Island (TMI) Uni.t 2 has established that the auxiliary feedwater (AFW) system should be treated as a safety system in a pressurized water reactor (PWR) plant.

The designs of safety systems in a nucl.ear power plant are i

requl.red to meet general design criteria (GDC) specHieC:. in Appendix A of the 10 CFR Part 50 [l].

The relevant design criteria for the AFW ?YStem design are GDC 13, GDC 20, and GDC 34.

GDC 13 sets forth the requirement for instrumentation to monitor variables and systems {over their anticipated ranges of operation) that can affect reactor safety.

GDC 20 requi.res that a protection system be designed to initiate automatically in order to assure that acceptable fuel design limits are not exceeded as a result of anticipateq operational occurrences.

GDC 34 requires that the safety function of the de:si_gned system, that is, the. residual heat removal by the AFW system, be accomplished even in the case of a single failureo On September 13, 1979, the NRC is~ued a letter [2] to each PWR. licensee that defined a set of requirements specified in NUREG-0578 [3]. It required that the AFW sy".stem have automatic initiation and single failure-p.roof des'ign consistent.with the requirements of GDC.20 and GDC 3~. In addition, auxiliary feed~ater flow indication in the control room should be provided to satisfy the requirements set forth in GDC 13 *

~::::-... __ ~ ~ Franklin Research Center

• " DMs1on o! The Freni<iin lnsvtute

TER-C5257-298 Du~ing the week of September 24, 1979, seminars were held in four regions of. the country to discuss the short-term requirements.

On October 30, *1979, another letter was issued to each PWR licensee providing additional clarification of the NRC staff short-term requirements without altering their intent [4] *

. Post-'1'¥...I analyses of primary system response to feedwater transients and reliability of installed AFW system~ also established that, in the long term, the AFW system should be upgraded in accordance with safe.ty-grade require-ments~

These long-term requirements were clarified in the letter ~f September S,* 1980 [5].

This letter incorporated in one document, NUREG-0737 [6), all T¥J~related items approved by the commission for implementation at this time.

Section II.E.1.2 of NUREG-0737 clarifies the requiremencs for th~ AFW system autoillatic initiation and flow indication.

1.3.

P~-~T-SPECIFIC BACKGROUND The Consumers Power: Company (CPC), responding to NRC r~quirements in letters dated January 21, 1980 [7] and March 4, 1980 [BJ, provided a description of the AFW system, the modifications required, and the tentative schedule for implementing these modifications at the Palisades plant.

In response to a me~ting with the NRC, CPC supplied additional information in a letter dated ~pril 22, 1980 [9].

In letters d~ted December 19, 1980 [10] and May 29, 1981 [11], CPC submitted updated information reflecting all AFW system modifications.

Finally, in letters dated November 5, 1981 [12] and August 11, 19 82 [l.3], the -Lice:f1see provided system logic diagrams and schematics.

The review of the AFW system at the Palisades plant began on May 20, 1981, based on the criteria described +/-n Section 2 of this reporto

~->:-....;* ___ Franklin Research Center

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TER-C5257-29 8

2.

REVIEW CRITERIA To i~prove the reliability of the AFW sys~ern, the NRC required licensees to up1grade the system, where necessary, to ensure timely automatic initiation I

when required.

The system upgrade was to proceed in two phases. In. the short term, as a minimum, control grade signals and circuits were to be used to auto-matically initiate the APW system.

This control grade system was to meet the following requirements of NuREG-0578, Secti':')n 2.1. 7. a [3]:

Rl.

The design shall provide for the automatic initiation of the auxiliary feedwater system.

2.

The automatic initiation signals and circuits shall be designed so that a single failure will not result in the loss of auxiliary feedwater system function.

3.

Testability of the ini~i~ting signals and circuits shall be a feature of.the design.

4.

The initiating signals and circuits shall be powered from the emergency buses.

S.

Manual capabil~ty to initiate the auxiliary feedwater sys-tem from the control room shall be retained and shall be implemented so t'hat a single failure in the manual circuits will not result in the loss of system function.

6.

The ac motor-driven pumps and valves* in the auxiliary feed-water system shall be included in the automatic actuation (simultaneous and/or sequential) of the loads to the emer-gency bus.es.

7.

The automatic initiating signals and circuits shall be desig~ed so that their failure will not result in the loss of manual capability to initiate the AFW system from the control room."

In the long term, these signais and circuits were to be upgraded in accor-dance with safety-grade*requirements. Specifically, in addition to the abqve require:~-=::~s, the automatic initiation signals and circuits must have imiepen-dent c~annels, use environmentally qualified components, have system bypassed/

inopera~le status features, and conform to control system interaction crite~ia, as stipulated in IEEE Std 279-1971 ll4].

~'

..... ----Franklin Research Center

.&,, D:vis.*on of -:-he Frenl"Jin lnst:tutc-

• --.~ ~.. ~

TER-CS257-298 The capability to ascertain tbe AFW system performance from the control room must also be provided.

In.the short term, steam generator level indica-tion and flow measurement were to be used to assist the operator in maintaining the required steam generator level during AFW system operation.

Thi"s system was to meet t.'1-ie following requirements from NUREG-0578 I Section 2.1.7. b, as clarified by NUREG-0737,Section II.E.1.2:

"l.

Safety-grade indication of auxiliary feedwater flow to each steam generator shall be provided in the control room *

. 2.

The ~uxiliary. feedwater flow instrument channels shall be powered from the emergency buses consistent with satisfying the emergency power diversity requirements of the auxiliary feedwater sy~tern set forth in Auxiliary Systems Branch Technical Position 10-1 of the Standard Review Plan, Section 10.4.9

[l~]."

The NRC staff has determined that, in the long term, the overall flowrate indication system for Combustion Engineering and Westinghouse plants should inciude at least one AFW'flowrate indicator and one wide-range steam generator level indicator for eachjsteam generator, or two flowrate indicators.

The safety-:grade flowrate indication system should be environmentally qualified, powered from a highly r~liable, battery-backed non-class lE power source,

. periodically tested, par~ of the plant's quality assurance program, and capable of display on demand.

The operator relies on steam generator level instrumentation, in addition -

to AFW flow indication, to determine AFW system performance.

The requirements for this' steam generator level instrumentation are specified in Regulatory Guide' 1.97, Reyision 2, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident* [16].

~:::-...... ~ _ -* Franklin Research Center A Divts.on of The Franl<ion l'1s~1u1e

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• TER-CS257-298

3.

'IBCBNICAL EVALUATION 3.1 GENERAt DESCRIPTION OF AUXILIARY FEEDWA~R SYSTEM

'!he auxiliary feedwater.(AFW) system at the Palisades plant supplies water to the secondary side of the steam generators for reactor decay heat removal when normal feedwater sources are unavailable due to loss of offsite power or other malfunctions.

'!he system consists of one steam turbine-driven pump (415 gpm) and two motor-driven pumps (415 gpm and 300 gpm).

One motor-driven AFW pump and the turbine-driven AFW pump are interconnected on the discharge side by a common header which then branches into two lines, one to each steam generator.

'Ihe lines to the steam generators each contain two normally open, motor-operated valves and one normally closed, pneumatically operated flow control valve; either pump can feed one or both steam generators.

T'ne other motor-dri~en AFW pump (P-66c) is pa;t of a separate train that is also capable of feeding either or both steam generators with the same valve arrangement as the dual pump train.

The primary *source of water for the AFW.system is a' 125,000-gallon condensate storage* tank and the backup supply is the primary system makeup storage tank.

An alternate source of water is Lake Michigan, ~upplied via three fire protection system pumps.

'!ne motor-driven AFW pumps are supplied power from the two ac emergency buses.

'!he turbine-driven pump can receive steam from either steam generator.

3.2 AUT01".iATIC IN.ITIATION 3.2.l Evaluation Upon completion of the proposed AFW system modifications, AFW flow to the steam generators will be automaticallY. initiated when preset levels of any of the following parameters are exceeded: *

~

A.

Motor-Driven Pumps

r. - Low steam generator level (2 of 4)

B.

'I\\lrbine-Driven Pump

1.

Low steam generatpr level (2 of 4)

~~'

• _ ~~ Franklin Research Center

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TER-C5257-298

'!be normal valve configuration for the AF'ril system is all AFW pump suction valves open, discharge flow con.trol valves closed, and steam admission valves to the turbine-driven pump closed.

One motor-drive_n AFW pump, one steam adm:i,ssion valve,. and two flow control valves are powered from Division i emergency buses.

'!he* other steam admission valve, the other motor-driven pump, and flow control valves are powered from Division II emergency buses.

'!he flow control valves are designed to fail open and the steam admission valves are designed to fail closed*.

However, because the,flow control valves fail open and the steam admission valves are powered from separate, safety-grade power supplies, there is sufficient de.sign safety margin to assure system valve operation as required.* Automatic isolation of a leaking steam generator is a design feature of the system.

'Ine operation of any AFW pump will.provide the necessary capacity for removing decay heat from the s~eam generators at a rate s~fficient to prevent ovetpressurization of the reactor coolant system and to maintain steam generator levels..

The two motor-driven AFW pumps will be started t:irst, and if flow is not established within a preset time, the turbine-driven pump will automatically start.

A review of initiation logic and wiring diagram~ revealed no credible single malfunction that would prevent proper protective action at the system level when required.

In addition, the Licensee has stated in Reference 10 that the design of the AFW system initiation logic meets IEEE Std 279-1971 in

• that no single component failure will prevent the automatic start signal from being initiat':d*

Initiation signal operating bypasses are provided to allow testing of the steam generator level channels.

~en one of the four. channels is taken out of service for maintenance, the initiation logic is a two out of three

. coincidence.

'!be following AF'W system testing has been proposed by CPC in a technical specification change request dated December 18, 1980 [17):

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_, ~~~ Franklin Research Center

Channel Descrintion

• ~uxiliary Feed Pump Flow Indication Auxiliary Feed Pump Au to Initiation Surve illa-nce Function

a.

Check

b.

Calibrate

a.

Test

b.

Calibrate Freauency M

R M

R TER-C5257-298 Surveillance Method

a. Com?arison ~f channels

b.

Known differential pr.es-sure applied to sensors

a. Internal test signal

b.

Known differential pres-sure appl~ed to sensors

'ITie control circµitry for automati~ initiation of the AF"~ system is designed so that if.the initiating event includes loss of offsite power, the motor-driven AFW pumps will not be started, nor will they be sequenced onto the emergency diesel. 'nlis arrangement does not satisfy the requirements of Posi"tion 6 of NU~G-0737,Section II.E.1.2.

The initiating signals and circuits are powered from safety-grade power supplies.

~ne system is desfgned so that the oper~tor has the capability of overriding the starting of any of ~the AFW pumps from the control room.

Annunciation of this override is provided*i~ the control room.

A single failure in the manual circuit.

will not-result in a loss of system automatic function, end t.~e separation of manual and' automatic initiating circuits ensures that the failure cf the auto-rnatic function will not result in a loss of ~anual capability.

initiation circuits meet single failure criteria.

'!be manual

'lhe electrical i_ndeJ?endence and physical separation of elements of the proposed AFW actu~tion system design comply with the requi=ements* of NUREG-0578

{3] and IEEE Std. 279-1971 {14) *.

The quality of components used in the AFW system has been ass~red by the Licensee because Class 1 safety-grade power supplies will be used and all control-grade equipmen~ will be replaced with safety-grade equipm_ent.

M,equate enviro~mental qualification of all safety-related syste~s, including the AFW system, is being determined separately by the NRC and is net withir: the scope of th is review.

~ ".;.:~* Franl-Jin Research Center

TER-CS257-298 3.2.2 Conclusion Based on.the* evaluation documented in Section 3.2.1, it is concluded that the initiation signals, logic, and associated circuitry of the AFW system at the Palisades plant comply with the long-term, safety-grade requirements of Section 2.1. 7.a of NUREG-0578 and the subsequent clarification issued by the NR: with the following exception:

o Review of the AFW system initiating signals, logic, and associated circuitry for the Palisades plant has shown that if a loss.of offsite power occurs, the motor-driven AFw pumps are not automatically sequenced on the diesel generator.

'.Ibis arrangement does not satisfy the requirements of Position 6 of NUREG-0737,Section II.E.1.2.

3.3 FLOW INDICATION 3.3~1 Evaluation

~ne performance of. the AFW system at the Palisades plant can be assessed by the AFW flowrate indicators, two for each steam generator, located in the control room.

T'ne Licensee has:stat~d that new'safety-grade flow fndication loops, supplied with safety-grade power, have been installed.

'lhe readout devices for these loops are also safety-grade.

T'ne existing AFW flow indication loops are control-grade and are powered from Class 1E power sources.

'Ihe determination of adequate environmental qualification of all safety-related systems, including *the AFW flowrate indication system, is being reviewed separately by the NRC and is-.

not within the scope of this review.

The flow indication system is not used in any control system.

Testing of the* flow indication is provided by actual system functional testing as described in Section 3.2~1.

3.3.2 Conclusion Based on the review documented in the preceding section, it is concluded

-that t.;e flow indication system of the Palisades plant satisfies the long~terrn requirehle!"lt of Section 2.1.*7.b of t.-UR:::G-0578 that at least one hFW flowrate irjicator exists for each steam generator.

In addition, the flow indic?tion e.-ceeds the NIC staff's design requirements in that the instn:rnentation is

• safety-grade and completely redundant.

~-:::-..... ~*- __ Franklin Research Center A t>:.uaor, o' The F ran<d1n lnst1tu1t

TER-C5257-298 3.4 DESCRIPTION OF STEAM GENERATOR LEVEL INDICATION Steam generator level instrumentation at the Palisades plant consists of four narrow-range channels per steam generator.

A separate indicate~ is provided for each channel and each is powered from a separate vital bus.

I Presently, no wide-range indication is provided; however, the Licensee has committed to the addition of wide-range detectors.

'!he steam generator level instrumentation channels are tested-as follows:

Channel Check Functional Test Calibration s

M R

The level instrumentation.channel power supplies are ~s follows:

Channel Vital Bus Type Indication A

Y-10 Indicator

- B Y-20 Indicator c

Y-30 Indicator D

Y-40 Indicator

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TER-C5257-298

~.

CONCLUSIONS Based on the evaluation documented in Section 3.2.1, it is concl~ded that the initiation signals, logic, and associated circuitry of the auxiliary feedwater (AFW) system at the Palisades plant comply with the long-term, safety-grade requirements of Section 2.1.7.a of NUREG-0578 and the subsequent clarification issued by the NRC with the following exception:

o Review of the AFW system initiating signals, logic, and associated circuitry for the Palisades plant has shown that if a loss of offsite power occurs, the motor-driven AFW pumps are not automatically sequenced on the diesel generator.

This arrangement does not satisfy the requirements of Position 6 of NUREG-0737,Section II.E.l.2.

• Auxiliary Feedwater Fiow Indication.

The review of the A-""W flow* indication shows that the f*low indication system sa~isfies the lon<;1-term requirements of at least one AFW flowrate indicator and one wide-rftnge steam generator level indicator for each steam generator and, therefore, is acceptable.

~':::..... ~ _ ~ ~ Franl*din Research Center

TER-C52S7-29 8

5. -

REFERENCES

l.

Code of Federal Regulations, Title 10 Office of the Federal Register, National Archives and Records Service, General Services Administration f

Revised January 1, 1980

2.

NRC

3.

Generic letter to all PWR licensees regarding requirements resulting from Three Mile Island Accident 13-Sep-79

• TMI-2 Lessons Learned Task Force Status Reoort and Short-Term Recommendations" NRC, July 1979 NUREG-0578 4o NRC Generic letter to all PWR licensees clarifying lessons learned short-term

.requirements 30-0ct-79 5 *. NRC Generic letter to a::ll PWR licensees regarding short-te_rm requirement resulting from Three Mile Island accident 05-Sep-80

6.

"Clarification of TMI Action Plan Requirements*

NRC, November 1980 NUREG-0737

7.

R. w. Huston (C?C}

Letter to D. L. Ziemann (NRC}

Consumers Power C6mpany, 21-Jan-BO

8.

D. P. Hoffman (CpC)

Letter to D. L. Ziemann (NRC)

Consumers Power Company, 4-Mar-80

9.

R. W. Huston (CPC)

Letter to D. L. Ziemann (NRC)

Consumers ?ower Company, 22-Apr-80

10.

D. P. *Hoffman (CPC)

Letter to D. M. Crutchfield (NRC)

Consumers Power Company, 19-Dec-80

_../'2--......._ ~--'.J Franklin Research Center

11.

12.

13.

B. D. Johnson (CPC)

Letter to D. M. Crutchfield (NRC)

Consumers Power Company, 29-May-81 B. D. Johnson (CPC)

Letter to D. M. Crutchfield (NRC)

Consumers Power Company, S-Nov-81 B. D. Johnson (CPC)

• Letter to D. M. Crutchfield (NRC)

Consumers Power Company, ll-Aug-82 TER-C5257-298 14 *. "Criteria for Protection Systems for Nuclear Power Generating Stations" Institute of Electrical and Electronics Enginee.rs, Inc., New York, New York IEEE' Std 279-1971

15.

Standard Review Plan, Section 10.4.9, Rev. I NRC, no date HUREG-7 5/087 16!

"Instrumentation* for Light~Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Rev. 2 NRC, *December 19 BO ;

Regulatory Guide 1.:97 (Task RS 917-4)

17.

D. P. Hoffman (CPC)

Letter to D~ M. Crutchfield (NRC)

Consumers Power Company, 18-Dec-80

~-.,......._

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