ML20052F666

Technical Evaluation of Monitoring of Electric Power to Reactor Protection Sys for Cooper Nuclear Station.

ML20052F666
Person / Time
Site:	Cooper
Issue date:	03/02/1982
From:	Selan J LAWRENCE LIVERMORE NATIONAL LABORATORY
To:	NRC
Shared Package
ML20052F664	List: ML20052F666
References
CON-FIN-A-0250, CON-FIN-A-250 TAC-08938, TAC-8938, UCID-19128, NUDOCS 8205130353
Download: ML20052F666 (7)

Text

{{#Wiki_filter:1 1 Enclosure 2 i 4 1 i UCID- 19128 j I I-1 1 - t l 5 TECHNICAL EVALUATION OF THE MONITORING OF f ELECTRIC POUER TO Tile REACTOR PROTECTION SYSTDI FOR THE COOPER NUCLEAR STATION ,

                                      -                                        James C. Selan SELECTED ISSUES PROGRAM (Docket No. 50-293) t I

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  .i March 2, 1982                                                    -

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Tius is an informal report intended prunarily for internal or limited esternal distnbution.

• The opinions and conctunons stated are those of the author and may or may not be those '

f of the Laboratory. { 3 This work was supported by the United States % clear Regulcry Commission under l ' s Memoraajum of Understandtng with the United States Department of Energy. F 1, h 0FFICIAL RECORD COPY 8205130353 820505 PDR ADOCK 05000290 1 P PDR

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DISCLAl\lER T his document was prepared as an accour.t of work 5ponsored by an agency of the t~nicad States f;osernment. Neuher the Leited States Goiernment not any ageng therecf. nur any of their employees, makes any aarranry. espre,wd or implied, or avumes any legal liabihty or responsibility for the accaracy. templeteness, or uwfalness of ans information apparatue, prodact. or procen diwfused, or represents that its use would nos nfringe prisards owned rights. Reference herein to any specifk commcrcial product, proccu. or sersice by trade name, tradem. irk manufae. turer, or otherwise, does not neceuarily constitute or imply its endurwment. recommendation or fasormg h,* the I nitra - States Goiernment or any agency thereof. The siews and opinions of authors esprewed herein do not necenarily state or redect thow of the United States Gosernment or any agency thereof, I I i sian adie frm: N aticca! Techmal Diiarmation erswe t A Deparrm at of f .mmert e 4:4 5 P.), R +s 41 R oJ J - ymgt~e'd. \ 4 : !al . if j) per c ps siistalk he G!4

ABSTRACT 3 a

  .      .                 This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Cooper Nuclear Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnornal voltage
 -{            and frequency conditions which could be supplied from the power supplies j            and will meet certain requirements set forth by the Nuclear Regulatory Commission.

{ I j The proposed design modifications with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources. l i i i i FOREWORD This report is supplied as part of the Selected Electrical, instrumentation, and Control Systems issues Program being conducted for the U. S. Nuclear Regulatory Commission, Office of Nuclear Reactor

     ,          Regulation, Division of Licensing, by Lawrence Livermore National Laboratory.
    .)

I I The U. S. Nuclear Regulatory Commission funded the work under the I authorization entitled " Electrical, Instrumentation and Control System Support," B6R 20 19 04 031, FIN-A0250. l 1 k - _ -

TABLE OF CONTENTS 3

1, Page e

                                                                               .  .  .  .  . 1

1. INTRODUCTION . . . . . . . . . .

                                                                               .  .  .  .  . 2
           .          2. DESIGN DESCRIPTION   .   .     .      . .  .  .  .
                                                                            .  .  .  .  .  . 3 j                  3. EVALUATION   .    .  .   .     .      . .  .  .
                                                                                   .  .  .  . 4

4. CONCLUSION . . . . . . . . . . .

     '                                                           .  .  .  .  .  .  .  .  .  . 5 REFERENCES     .   .   .  .    .     .

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                                                             -iii-I i

II TECHNICAL EVALUATION OF THE

l MONITORING OF ELECTRIC POWER

) .

j TO THE REACTOR PROTECTION SYSTEM AT THE COOPER NUCLEAR STATION

 'i (Docket No. 50-298)
           ~

James C. Selan Lawrence Livermore National Laboratory, Nevada !l t

1. INTRODUCTION i,

1 During the operating license review for Hatch 2, the Nuclear j Regulatory Commission (NRC) staff raised a concern about the capability

   ?                       of the Class lE reactor protection system (RPS) to operate after suffering l

sustained, abnormal voltage or frequency conditions from a non-Class lE ' power supply. Abnormal voltage or frequency conditions could be produced j as a result of one of the following causes: combinations of undetected, j random single failures of the power supply components, or multiple failures

    ;                      of the power supply components caused by external phenomena such as a seismic event.

The concern for the RPS power supply integrity is generic to all General Electric (GE) boiling water reactors (BWR) MARK 3's, MARK 4's, and MARK 5's and all BWR FUJUC 6's that have not elected to use the solid state RPS design. The staff therefore pursued a generic resolution. Accordingly, - GE proposed a revised design, in conceptual form, for resolution of this concern [Ref. 1). The proposed modification e-ansists of the addition of two Class lE " protective packages" in series between each RPS motor generator (M-G) set and it's respective RPS bus, and the addition of two similar packages in series in the alternate power source circuit to the RPS buses. j Each protective package would include a breaker and associated overvoltage, i undervoltage and underfrequency relaying. Each protective package would meet the testability requirements for Class 1E equipment. With the protective packages installed, any abnormal output type failure (undetectable random or seismically caused) in either of the two RPS

; ,a M-G sets (or the alternate supply) would result in a trip of either one or l     .

both of the two Class lE protective packages. This' tripping would interrupt the power to the effected RPS channel, thus producing a scram signal on that channel, while retaining full scram capability by means of the other channel.

       }

Li Thus, fully redundant Class lE protection is provided, bringing the overall i' 1 I

3. EVALUATION d

  'I
  'i

• j The NRC stated several requirements that the licensee must meet in

           -           their design modification to monitor the power to the RPS. A statement of these requirements followed by an evaluation of the licensee's submittals is as follows:
           ~

i (1) "The components of the RPS shall not be exposed to unaccept-able electric power of any sustained abnormal quality that could damage the RPS." The monitoring module will detect overvoltage, undervoltage, l and underfrequency conditions with the following setpoints. The chosen setpoints are within the ratings of the RPS jj components and thus ensures their protection from sustained jj abnormal-power: Nominal voltage 120 volts, 60 Hz nominal Setpoint Time Delay Condition Overvoltage < 132 Volts

• t
• Undervoltage > 108 Volts Underfrequency ), 57 Hz I
• The licensee states that the actual time delays selected (with respect to their voltage and frequency setpoints) uill fall within the range of .1 seconds to 3.0 seconds which is available from the GE design. Upon installation and testing, the final time delays selected will be verified by CE to

      }                                    ensure that the RPS components will be protected with the chosen.setpoints from sustained abnormal power (Ref. 11].

(2) " Disconnecting the RPS from the abnormal power source shall 'g be automatic." i; l The monitoring module will automatically disconnect the RPS buses from the abnormal power supply after the set time delay l}^ I should the parameters setpoints be exceeded. (3) "The power monitoring system shall meet the requirements'of

       }                                    LEEE 279-1971, CDC-2 and CDC-21."

The monitoring packages meet the Class 1E requirements of IEEE 279, the single failure criteria of CDC-21, and the

         > a                                seismic qualifications of CDC-2.

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1 REFERENCES-4

1. General Electric Company letter, MFN 408-78 (C. C. Sherwood) to NRC (R. S. Boyd), dated October 31, 1978.

2. General Design Criteria-2_ (GDC-2), " Design Bases for Protection Against Natural Phenomena," of Appendix A, "Ceneral Design Criteria for Nuclear Power Plants," in the Code of Federal Regulations, Title 10, Part 50 (10 CFR 50).

3. General Design Criteria-21 (CDC-21), " Protection System Reliability and Testability," of Appendix A, " General Design Criteria for Nuclear Power Plants," in the Code of Federal Regulations, Title 10, Part 50 (10-CFR 50).

4. IEEE Std. 279-1971, " Criteria for Protection Systems for Nuclear Powe" Cenerating Stations."

       \                                                                                            .

'! 5. NUREC-75/087, " Standard Review Plan for the Review of' Safety Analysis il!.; Reports for Nuclear Power Plants." f' 6. NRC memorandum from Faust Rosa to J. Stolz, T. Ippolito, and C. Lainas,- l dated February 19, 1979.

7. NRC Ictter to Operating BWR's, dated September 24, 1980.

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8. NPPD letter (Jay M. Pilant) to NRC (Thomas A. Ippolito), dated

!-{ December 2,1980. i i, 9. NPPD Ictter (J. M. Pilant) to NRC (Thomas A. Ippolito), dated i May 15, 1981. - I

10. NPPD letter (Jay M. Pilant)~to NRC (Thomas A. Ippolito), dated September 29, 1981.

11. Telecon, Jef f Weaver ('NPPD), Iqbal Ahmed and Byron Siegel (NRC), and James Selan (LLNL) - dated February 17, 1982.

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