ML20091K928

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Electrical,Instrumentation & Control Design Aspects of Proposed License Amend Rev 1 for Single Loop Operation of Pilgrim Nuclear Power Station,Unit 1, Technical Evaluation Rept
ML20091K928
Person / Time
Site: 05000000, Pilgrim
Issue date: 12/14/1983
From: Donich T
LAWRENCE LIVERMORE NATIONAL LABORATORY
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17139C189 List:
References
CON-FIN-A-0250, CON-FIN-A-250, FOIA-84-105 UCID-19724, NUDOCS 8406070246
Download: ML20091K928 (9)
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TECHNICAL EVALUATION REPORT ON THE ELECTRICAL, INSTRUMENTATION, AND CONTROL DESIGN ASPECTS OF THE PROPOSED LICENSE AMENDMENT REVISION 1 FOR SINGLE-LOOP OPERATION OF THE PILGRIM NUCLEAR POWER STATION, UNIT l' (Docket No. 50-293)

Terry R. Donich December 14, 1983

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e A3STRACT This report documents the technical evaluation of the proposed changes to the plant reactor protection system by the licensee of Pilgrim Nuclear Power Station, Unit 1, to account for' single-loop plant operation.

This evaluation is restricted to only the electrical, instrumentation, and control design aspects of proposed changes to the plant technical specifi-cations for single-loop' operation beyond 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The conclusion of the evaluation is that the Pilgrim Nuclear Power Station, Unit 1, license atendment for single-loop operation has met the review criteria provided anonalous control room indications are corrected or warning-tagged for the duration of single-loop operations and the title or position of the appropriate technical individual to make the independent check of the setpoint adjustment be identified.

FORZb'ORD This report is supplied as part of the Selected Operating Reactor Issues Prog' ram II being conducted for the U. S. Nuclear Regulatory Com=ission, Office of Nuclear Reactor Regulation, Division of Licensing, by Lawrence Livermore Naticnal Laboratory.

The U. S. Nuclear Regulatory Com=ission funded the work under the classification entitled " Selected Operating Reactor Issues Program II, B&R 20 19 10 11 1, FIN No. A-0250.

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TABLE OF CONTENTS Page 1.

INTRODUCTION.

1 2.

EVALUATION AND RECOM1SNDATIONS 2

3.

CONCLUSIONS 3

REFERENCES.

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t TECHNICAL. EVALUATION REPORT ON THE ELECTRICAL,

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  • INSTRUMENTATION, AND CONTROL DESIGN ASPECTS OF THE PROPOSED LICENSE AMENDMENT REVISION 1

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FOR SINGLE-LOOP OPERATION OF THE PILGRIM NUCLEAR POWER STATION, UNIT 1 (Docket No. 50-293)

Terry R. Donich Lawrence Livermore National Laboratory 1.

INTRODUCTION By letter to the U. S. Nuclear Regulatory Commission (URC) dated May 12,1981 [Ref.1], the Boston Edison Power Company submitted information to support its proposed license acendeent to operate the Pilgri: Nuclear Power Station, Unit 1 (PNPS-1) with one recirculation loop out of service (i.e., single-loop operation). This request supercedes all other sub=ittals.

This infor=ation included the licensee's analysis of significant events, which were based on a review of accidents and abnormal operational transients

. assoc a ei t d with power operations in the single-loop mode provided by General Electric Company Nuclear Energy Division (GE-NED), the nuclear steam supply system designer.

Conservative assumptions were employed, as discussed in the GE-NED report NED0-24268 dated June, 1980 [Ref. 2] to ensure that the generic analyses for boiling water reactors (BWR 3 and/or 4) were applicable to the PNPS-1.

In response to an NRC request, the licensee provided supplemental information in a letter dated April 11, 1983 [Ref. 3] and a conference call on September 27,1983 [Ref. 4].

A letter to NRC documenting the conference call was dated October 25, 1983 [Ref. 5].

The purpose of this report is to document the evaluation of the electrical, instrumentation, and control (EI&C) design aspects of the proposed license amendment change to the PNPS-1 technical specifications. The con-sideration of proper plant variables, computer models, and the licensee's conclusions on core performance and clad temperature are outside the scope of this evaluation.

This review was conducted using 10CFR50, Appendix A, " General Design Criteria for Nuclear Power Plants" (G.D.C. 20 through 24) [Ref. 6] and IEEE Std 279-1971 [Ref. 7] with the following guidance from the NRC staff for the applicaton of Section 4.15, Multiple Set Points,- of the IEEE Standard:

Manual switching to the.more restrictive setpoint for the APRMs in.

the reactor protection system is acceptable for BWRs if sufficient administrative controls exist to assure that the more restrictive setpoints are in effect when required by the plant technical specifications..

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2 The NRC has defined sufficient adminstrative controls as:

1.

There is to be an independent check of the gain or setpoint adjustment.

2.

The check is to be within the next shift.

3.

Checks are by appropriate technical individuals (e.g., shif t supervisor or S.R.O. ).

The adjustments to the reactor protection system for single-loop operation (i.e., scram trip setpoint adjustments or APRM gain adjustments) =ust be within and therefore satisfy the functional requirements of the reactor protection system.

2.

EVALUATION AND RECOMMENDATIONS The current PNPS-1 Technical Specfications do not per=it single-loop plant operation at redu6ed power for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The licensee's proposed technical specification changes would allow the reactor to operate at reduced power, not greater than 50%, with one recirculation loop inoperable for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if certain changes are cade to the reactor protection syste=s.

These changes are to the Average Pcwer Range Monitor (APRM) scra=

trip setpoint and the Rod Block Monitor (RBM) rod-block setpoint or the ARPM gain.

A different flow pattern is established in the vessel during single recirculation lcop operation as compared to the normal two-loop operation

[Ref. 2}.

In single-loop operation, there is backflow through the jet pu=ps in the idle loop.

The jet pump core flow =easurement system is calibrated only when both loops are in operation and all jet pucps are in forward flow.

The total core flow is the sum of the ceasured jet pump ficws.

In single-loop operation, the. measured flow in the back-flowing jet pucps must be subtracted f rom the flow-through ~ the other jet pumps.

Also, the jet pu=p flow coefficient is different for reverse flow than for forward flow in the jet _ pumps.

Because of the different flow rate and flow path during single-rr. circulation-loop operation, the APRM SCRAM trip settings, which are flow-biased according to the equation in the proposed technical specifications, require resetting to protect the reactor from overpower. The rod-block set-point equation is flow-biased in the same way and with the same flow signal as,the APRM'setpoint,'and must also be modified to provide adequate core

. protection for a postulated rod withdrawal error. This change is accomplished by adjusting the trip setpoints. '

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'The manual adjustment of the. trip setpoints to acccacodate single-loop ~ operation is the only change imposed upon the PNPS-1 reactor c

protection system (RPS). This.=odification subtracts the term 0.65W from

. the trip setpoints-to compensate for backflow through the jet pu=gs in the idle loop.

This change is similar to one which is routinely made to adjust for peaking factors in excess of design (Ref. 4].

The licensee stated that sufficient range exists in the settings to make the necessary changes to the

.RPS for single-loop operation (Ref. 3]. This change will not cause the RPS to violate General Design Criteria 20 to 24 of 10CTR50, Appendix A.

The licensee provided in a lett'er dated October 25, 1983 (Ref. 5]

the draf t procedures which includes the administrative controls to be used

. to assure that the trip setpoint adjustments are performed corrpetly.

The multiple scram trip setpoints will'be used to adjust the reactor protection systen for single-loop operation. These adjustments for starting single-loop operation will be performed by a technician.

A second person will independently review the settings as an administrative control. The NRC definition for sufficient administrative controls defines the second person as a person "such as a shif t supervisor or senior reactor operator." We recommend that the licensee change the procedure to include the position or title of the percon who will independently review the settings.

3.

CONCLUSIONS Based on our review of the information and documents provided by the licensee in Ref.~ 1, we conclude that.the more conservative reactor protection system (RPS) setpoint trips for the APRM and RBM will satisfy the functional requirecents for single-recirculation-loop operation.

The manual adjustment of the trip setpoints to accom=odate single-loop operation is the only change imposed upon the Pilgrim Nuclear Power Station reactor protection system (RPS) instrumentation.

This change will not cause the RPS instrumentation' system to violate 10CFR50, Appendix A, General, Design Criteria 20 through 24 (Ref. 6] or IEEE 279-1971 (Ref. 7] with the exception of the IEEE Standard as discussed be..ow.

Because of the backflow through the jet pu=ps during single-recirculation-loop operation, indications in the ' control room of individual jetpump flow and total summed core flow will be misleading.

We recommend L tl at those, anomalous control ~ room indications be corrected or warning tagged

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. for the duration of the single recirculation-loop operation, as required by Section 4~.~20 of IEEE Std 279-1971 (Ref. 7].

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The administrative controls to be used by the licensee to assure the trip'setpoint adjustments are performed correctly meet the NRC criteria

~for, sufficient administrative controls except that the appropriate pcsition or title of the individual to make the independent check of the setpoint adjustments should be defined.

We -recommend that the NRC accept, upon successful implementation of the above recommended action, the proposed licensee amendment for single-recirculation-loop operation at Pilgrim Nuclear Power Station, Unit 1.

REFERENCES J

1.

Boston Edison Company letter (J. Edward Howard) to NRC (Thomas Ippolf to),

" Revised Request for Technical Specification Changes Concerning Single l

Loop' Operations," dated May 12, 1981.

2.

General Electric Company, Nuclear Power Systems Division, " Pilgrim Nuclear Power Station Single-Loop Operation," NEDO 24268, June 1980.

3.-

3cston Edison Co=pany letter (William D. Harrington) to NRC (Deninic 3.

Vassallo), " Single-Locp Opcration for Pilgrim "uclear Power Station.

Response to Questions," dated April 11, 1983.

4 Telephone conf erence call NRC (Jack Donohew); BECO (Marie Lenhart, Paul Smith, John Abaltin); LLNL (Terry Donich), September 27, 1983.

5.

Boston Electric Company letter (William D. Harrington) to NRC Operating Reactors Branch (Dominic B. Vacallo, Chief), " Single Loop Operation "

dated October 25, 1983.

6.

Code of Federal Regulations, Title 10, Part 50, Appendix A, " General Design Criteria for Nuclear Power Plants," 1981.

7.

IEEE Std 279-1971, " Criteria for Protection Systems for Nuclear Power Generating Stations," dated 1971.

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v DISCLAl\\fER o

This document was prepared as an acuunt of work sponsored by an agency of the United States Gaiernment.

Neither the United States Gosernment nor the Unisersity of California nor any cf their employees, makes any warranty, espress or Implied, or assumes any legal liability or responsibility for the accurach com-pleteness, or usefulneu of any inforenation, apparatus, product, or process disclosed, or represents (i.at its use would not infringe priiste!} owned rights. Reference herein to any specitic commercial products, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or fatoring by the United i.tates Government or the Uni *ersity (f California.

The views and opinians of authors expreued herein do not necessarily state or reflect those of the United States Government 6s* eof, and shall not be used for advertising or product endorsement purposes.

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