ML20090A754

Forwards Questions Re GE single-loop Operation Rept, NEDO-24258

ML20090A754
Person / Time
Site:	05000000, Cooper
Issue date:	09/30/1980
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
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References
FOIA-84-105 TAC-42418, NUDOCS 8010230484
Download: ML20090A754 (2)

Text

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,,g UNITED STATES NUCLEAR REGULATORY COMMISSION g

3 g WASHINGTON. D. C. 20555

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st? 3 0 1880 Docket No.: 50-298 MEMORANDUM FOR:

1. M. Novak, Assistant Director for Operating Reactors, DL FROM:

L. S. Rubenstein, Assistant Director for Core and Containment Systems, DSI

SUBJECT:

DSI QUESTIONS ON G.E. COCPER NUCLEAR STATION SINGLE-LOOP OPERATION Plant Name:

Cooper Nuclear Station Docket Number:

50-298 Licensing Stage:

OR Responsible Branch:

ORB-2 and Project Manager:

V. Rooney 1

Description of Review:

First Round Questions Requested Completion Date:

September 30, 1980 Review Status:

Request for Additional Information

, Enclosed are questions from the Themal-Hydraulics Section of the Core Performance Branch on the General Electric Single-Loop Operation Report NED0-24258.

g L. S. Rubenstein, Assistant Director for Core and Containment Systems Division of Systems Integration

Enclosure:

As stated cc:

D. Ross L. phillips D. Eisenhut M Roonay P. Check S. Diab T. Speis T. Huang T. Ippolito S. Gupta W. Johnston pH

Contact:

S. Gupta X-27091 f* gey L4t3 yA

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3' 492-1

'492.0 CORE PERFORMANCE BRANCH, THERMAL-HYDRAULICS SECTION 492.1 Specify expected minimum and maximum operating core power / flow condition as percentage of Rated Core Power / Flow for Single-Loop Operation.

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'492.2 At the specified minimum and maximum operating Core Power / Flow Condition for Single-Loop Operation, provide the following:

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(1) Safety Limit MCPR values, (2)

Fuel Loading Error MCPR analysis results,

'(3) Local Rod Withdrawal Error (with limiting instrument failure)

Transient Sumary, and P

l (4) Core Wide Transients Analysis and Operating Limit MCPR results for all the fuel' types in the core for the following transients 4

per NEDE-24011-P-A-1: Flow decrease, Cold Water Injection, and Pressurization.

492.3 Section 2.0, a 6% Core Flow Measurement Uncertainty has been established for single-loop operation (compared to 2.5% for two-loop operation).

The total core flow uncertainty value of 2.5% corresponds to 11.2%

standard deviation in each individual jet pump for two-loop operation.

Nhat is the corresponding standard deviation for each individual jet 4

pump for single-loop operation.

492.4 How long will the reactor operate under the single-loop operation, 3

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MAY j 9 1981 MEMORAtlDUM FOR:

T. Ippolito, Chief, ORB #2, DL FROM:

T. P. Speis. Chief, Reactor Systems Branch, DSI

SUBJECT:

REQUEST FOR A MEETING WITH BWR LICENSEES ON SINGLE LOOP OPERATION (SLO)

The Reactor Systems Branch is currently reviewing, by request from the Division of Licensing, several BWR licensee (Duane Arnold, Cooper and Peach Bottom) requests for modifications to their plant technical' specifications that will permit single loop operation (SLO).

In order to make a decision whether SLO is still a safe means of reactor operation, the Reactor Systems Branch and Core Performance Branch requests a meeting to discuss the September 26, 1979 Browns Ferry single loop operation (SLO) " experience".

This experience involved unexplained core vibrations which occurred at 597, power during the single loop mode of operation.

The meeting agenda should cover the following subjects:

N 1.

Discuss in detail the Browns Ferry SLO experience (this discussion will 2 S '(

include their evaluation of the causes of the oscillations); and, N

2.

Provide generic justification for power operation of BWRs (licensees 277 maximum desired power) in the single loop mode in the wake of this

,g experience.

ML The possible reoccurrence of a BF 1 SLO type of experience has raised the NRC's g

concern that safety limits could be violated and/or the exhibited instabilities lead to further complications.

The presentation would be structured to 311 address:

1.

core stability; 2.

core flow symmetry; 3.

pump cavitations; 4.

jet pumps and other vessel internals; and, 5.

safety limits.

It is expected that the information presented at this meeting will allow the staff to decide if single loop operation in BWRs is a safe and prudent means of reactor operation.

CONTACT: Tom Loomis X29403

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MAY t 9 1981 We greatly appreciate your assistance in this matter.

If any questions arise, or if additional information is needed, please contact To Loomis (29403) of

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my staff is coordinating this issue.

j A% r Themis P. Speis. Chief Reactor Systems Branch Division of Systems Integration cc:

R.'Mattson T. Novak P. Check S. Sun D. Clark B. Siegel M. Fairtile K. Eccleston L. Phillips I

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