ML20127B922

Forwards PNL-5201, Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Grand Gulf Nuclear Station, Unit 1

ML20127B922
Person / Time
Site:	Grand Gulf, 05000000
Issue date:	07/20/1984
From:	Dingee D Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:	Berlinger C Office of Nuclear Reactor Regulation
Shared Package
ML19263A614	List: 05000000/LER-1984-002, :Since 840107,several Instances of Reactor Protection Sys Bus Breaker Trips Resulted in Loss of Shutdown Cooling.Trip on 840119 Caused by Failure of Circuit Board 05000000/LER-1984-010, :on 840210,reactor Protection Sys Motor Generator Set Output Breaker B Tripped While Transferring Power from Alternate Supply.Caused by Voltage Transient. Design Change Being Considered AECM-84-0133, Advises NRC of Completion of Operator Recertification Program,Per 831118 Commitment.Deficiencies in Training That Remain Open Will Be Closed in Near Future.One Licensed Reactor Operator Undergoing Remedial Training AECM-84-0204, Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored AECM-84-0226, Responds to 840323 Confirmation of Action Ltr Re Verifying Removal of Certain Individuals from Licensed Duties.Util Has Evaluated Licensed Operators to Determine If Deficiency Identified Applicable to Other Operators.Related Info Encl AECM-84-0239, Provides Info Re Plant Discrepancy Repts to Assure That Any safety-related Hardware or Procedural Deficencies Properly Dispositioned,Per 831205 Confirmatory Action Ltr.Procedural Revs Instituted.Related Info Encl ML20126D262 ML20126D273 ML20126D322 ML20126D343 ML20126D352 ML20126D357 ML20126D360 ML20126D363 ML20126D376 ML20126D380 ML20126D392 ML20127A505 ML20127B023 ML20127B328 ML20127B331 ML20127B336 ML20127B341 ML20127B347 ML20127B352 ML20127B358 ML20127B363 ML20127B365 ML20127B370 ML20127B373 ML20127B377 ML20127B381 ML20127B384 ML20127B389 ML20127B408 ML20127B440 ML20127B520 ML20127B524 ML20127B530 ML20127B533 ML20127B542 ML20127B803 ML20127B808 ML20127B888 ML20127B893 ML20127B922 ML20127B927
References
CON-FIN-B-2963, FOIA-84-459 NUDOCS 8408090370
Download: ML20127B922 (1)

Text

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July 20, 1984

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375-2514

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Mr. Carl Berlinger

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Division of Licensing

-i Of f ice of Nuclear Reac tor Regulation U. S. Nuc lear Regul atory Conv11 ss ion

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Washington, D.C.

20555

Dear Mr. Berlinger:

SUBJECT-TDI DIESEL ENGINE PROJECT (FIN B2963)--TRANSMITTAL OF

" REVIEW AND EVALUATION OF TRANSAMERICA DELAVAL INC.

DIESEL ENGINE RELI ABILITY AND OPERABILITY GRAND GULF NUCLE AR STATION, UNIT 1", DATED JULY 20, 1984, PNL-5201 L

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Enclosed for your use are 10 copies of the subject PNL report and two addi tional copies for the NRC publ ic documen t reading room.

ne are sending two copies direc tly to DOE 's Tecnnical Information Center.

Other copies tlso have been distributed as noted on the last page of the report.

m Because of the,hort time available to prepare this report to meet NRC schedules, the report was prepared on-site at the NRC offices.

Accordingly, NRC review and concurrence was concomitant with the preparation.

we plan to have PNL-consul tant Adam Henriksen and mysel f available at NPC on July 31 to respond to questions that the Commissioners may Please advise us of any changes raise.

the schedule that may occur.

in Sincerely, 7

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a-fGf m f Sk David A. Dingee PNL Diesel Engine 0/R Project

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MAR 8 1984 i

MB40RANDUM FORi"R.'J.'Mattson,'tems Integration, NRR Director-

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L. S. Rubenstein, Assistant Directo i

for Core and Plant Systems, DSI I

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FROM:

C. H. Berlinger, Chief Core Perfomance Branch, DSI

SUBJECT:

RE-REVIEW OF GRAND GULF TECHNICAL SPECIFICATIONS

Reference:

1.

Memorandum from R. J. Mattson to R. Houston, et al, dated February 27, 1984,

Subject:

Re-Review of Grand Gulf Technic'il Specifications.

The Core Pe'r'fomance Branch has completed the re-review of Grand Gulf

~l Technical Specifications as requested by Reference 1.

Enclosed is a list of specifications reviewed.

Those specifications listed for which j

no comments are enclosed are acceptable as is.

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. 4. H. Berlinger, hief i

I Core Perfomance Branch, DSI l

Enclosure:

As stated cc:

L. Rubenstein D. Eisenhut T. Novak R. Capra D. Brinkman C. Thomas i

Contact:

S. Sun, CPB:DSI X-29499 3

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ENCLOSURE 1 l

Technical Specifications Re-Review l

By The Core Perfomance Branch for Grand Gulf Unit 1 1.

Definitions:

l 1.2 Average Planar Exposure 1.3 Average Planar Linear Heat Generation Rate 1.7 Core Alteration 1.8 Critical Power Ratio 1.14 Fraction of Limiting Power Density 1.15 Fraction'of Rated Themal Power 1.20 Limiting Control Rod Pattern 1.21 Linear Heat Generation Rate 1.23 Maximum Fraction of Limiting ?ower Density 1.24 Minimum Critical Power Ratio 1.28 Physics Tests 1.33 Rated Themal Power 1.36 Rod Density 1.38 Shu tdown* Margin 1.42 Themal Power II.

Safety Limits i

2.1.1 Themal Power, Low Pressure or Low Flow 2.1.2 Themal Power, High Pressure and High Flow 2.2.1 Reactor Protection System Instrumentation Setpoints (IRM and APRM only)

III. Limiting Conditions for Operation and Surveillance Requirments 3/4.1.1 Shutdom Pargin 3/4.1.2 Reactivity Anomalics 3/4.1.3.1 Control Rod Operability i

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3/4.1.3.2 Control Rod May.imum Scram Insertion Times 3/4.1.3.3 Control Rod Scram Accumulators 3/4.1.3.4 Control Rod Drive Coupling 3/4.1. 3. 5 Control Rod Position Indication 3/4.1.3.6 Control Rod Drive Housing Support 3/4.1.4.1 Control Rod Withdrawal 3/4.1.4.2 Rod Pattern Control System 3 /4.1. 5 Standby Liquid Control System 3/4.2.2 APRM Setpoints 3/4.2.3 Minimum Critical Power Ratio 3 / 4. 2.'4' Linear Heat G,eneration Rate 3/4.3.1 Reactor Protection System Instrumentation (IRM and APRM only) 3/4.3.6 Control Rod Block Instrumentation l

3/4.3.7.6 Source Range Monitors 3/4.3.7.7 Traversing In-Core Probe System 3/4.3.7.10 Loose-Part Detection System 3/4.4.1.1 Recirculation System 3/4.4.1.2 Jet Pumps 3/4.9.1 Reactor Mode Switch 3/4.9.2 Instrucentation 1

3/4.9.3 Control Rod Position l

l 3/4.9.10.1 Single Control Rod Removal 3/4.9.10.2 Multiple Control Rod Removal 3/4.10.2 Rod Pattern Control System l

3/4.10.3 Shutdown Margin Demonstrations

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3-Ccrnment s 3/4.4 3.4.1.1 This Technical Specification, which provides limiting conditions (hours) for operation in natural circulation and with only one recirculation loop, is not sufficiently prescriptive to protect against the potential for thennal hydraulic instability. ' GE recently presented the staff with stability test data which denonstrated the occurrence of limit cycle neutron flux oscillations at natural circulation and several percents above the rated 4

rod line.

The oscilla'tions were observable on the APRM's and were supressed with control rod insertion.

It was predicted that limit cycle oscillations would occur at the operating condition tested, however; the characteristics of the observed oscillations were different than those previously observed at other stability tests.

Namely, the test data showed that some LPRMs oscillated out of phase with the APRM signal and at an amplitude as great as six times the core average.

GE is preparing a SIL for release soon to alert their plants of these new data and to reconmend actions to avoid and control abnonnal neutron flux oscillation.

The applicant is required to change this specification to

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properly protect against the potential for thermal hydraulic instability.

l, 3/4.2.3 t

3.2.3 No reference is given in the BASES for Figures 3.2.3-1 and 3.2.3-2.

These curves are taken fron NEDO-24011, Revision 4 (January 1982) but no reference to this appears in the FSAR,

.