ML20127B922

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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:
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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Mr. Carl Berlinger Division of Licensing -i Of f ice of Nuclear Reac tor Regulation U. S. Nuc lear Regul atory Conv11 ss ion

[ 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

[

- 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 -

raise. Please advise us of any changes in the schedule that may occur.

Sincerely, ,

7 /

a-fGf m f Sk David A. Dingee

_ PNL Diesel Engine 0/R Project

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' I UNITED STATES

!he j9,'n NUCLEAR REGULATORY COMMISSION d . 'A

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WASHING TON. D. C. 20555

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MAR 8 1984 i

! Director- -

j MB40RANDUM '

FORi"R.'J.'Mattson,'tems

'" Difisfon of 'Sys Integration, NRR THRU: L. S. Rubenstein, Assistant Directo d i for Core and Plant Systems, DSI I i '

i 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

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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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I . 4. H. Berlinger, hief 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 i 3 2 .. a n i/11. z pt.

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1 1 6

,- 1 ENCLOSURE 1 l Technical Specifications Re-Review l By The Core Perfomance Branch for Grand Gulf Unit 1

1. Definitions:

1.2 Average Planar Exposure l

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

l 3/4.9.3 Control Rod Position 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

5. c. Fww 5 w . , s.

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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 ,

( 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,

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