ML13312A566

From kanterella
Revision as of 11:27, 4 November 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Response to NRC Question 222.34, Nonproprietary Version, June 1980
ML13312A566
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/30/1980
From:
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML13308B759 List:
References
CEN-127(S)-NP, NUDOCS 8008220229
Download: ML13312A566 (13)


Text

SAN ONOFRE UNITS 2 AND 3 DOCKETS 50-361 AND 50-362 CEN-127(S) - NP RESPONSE TO NRC QUESTION 222.34 NON-PROPRIETARY VERSION JUNE, 1980 COMBUSTION ENGINEERING, INC.

NUCLEAR POWER SYSTEMS POWER SYSTEMS GROUP WINDSOR, CONNECTICUT 06095 8c08220

LEGAL NOTICE This response was prepared as an account of work sponsored by Conibustion Engineering, Inc. Neither Combustion Engineering nor any person action on its behalf:

a. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this response, or that the use of any information, apparatus, method or process dis closed in this response may.not infringe privately owned rights; or
b. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this response.

CRITERIA FOR PROPRIETARY INFORMATION Information contained in this report which is delimited by means of surrounding brackets is proprietary to Combustion Engineering, Inc. Code numbers 1-6 have been placed in the vicinity of such brackets to classify this proprietary information. The following list identifies the classification criteria associated with these code numbers.

Code Criteria 1 The information reveals privileged cost or price information, commercial strategies, production capabilities, or budget levels of Combustion Engineering, Inc., its customers or suppliers.

2. The information reveals data or material concerning Combustion Engineering or customer funded research or development plans or programs of substantial present or potential competitive advantage to Combustion Engineering, Inc.

3 The use of the'information by a competitor would substantially decrease his expenditures, in time or resources, in designing, producing or marketing a similar product.

4 The information consists of test data or other similar data concerning a process, method or component, the application of which results in a substantial competitive advantage to Combustion Engineering, Inc.

5 The information reveals special aspects of a process, method, component or the like, the exclusive use of which results in a substantial competitive advantage to Combustion Engineering, Inc.

6 The information contains ideas for which patent protection is likely to be sought..

Question 222.34 The results of the submitted answer to the staff questions (Amendment 16 September 1979) are surprising. Therefore, we would like to verify some of the results by performing in-house audit calculations. To expedite our audit calculations, provide the input data (actual input used in the CESEC and TORC codes) for the following cases:

Steam line break with offsite power from full power.

Steam line break without offsite power from full power.

Steam line break without offsite power from hot zero power.

Worst feedline break case.

Response is a description of input data to the CESEC code, which was used in the steam line break analysis. Attachment 2 describes additional input data required for the CESEC-ATWS code, which was used in the feedwater line break analysis. The following information is provided for each input:

1. The input variable vector location;
2. The alphanumeric designation of the input variable;
3. The engineering units of the input variable, and
4. A brief description of the input variable.

Attachments 3 through 6 provide the numerical CESEC (or CESEC-ATWS) input data for the full power steam line breaks with and without offsite power available, the hot zero power steam line break without offsite power available, and the worst feedwater line break, respectively.

Input vector locations defined in Attachments 1 and 2 for which no numerical values are given in one or more of the Attachments 3 through 6 assume the value zero. Data on lines identified with an asterisk (*)

do not affect the results of the particular transient. They are provided either as suggested time step or edit control options, or because CESEC requires a non-zero value for certain input variables for its initializa tion calculations even though they are not used in the transient calculations. The format of the input data as read by CESEC is (AlO,4X, Il, 15,6F10. 0). is a complete numerical CESEC input listing for the full power steam line break with offsite power available, failure of one high pressure safety injection (HPSI) pump, and stuck control element assembly (CEA). Attachments 4 and 5 list, for the full power steam line break without offsite power available and for the hot zero power steam line break without offsite power available (both with failure of one HPSI pump and stuck CEA), respectively, those input variables whose values differ from the values specified in Attachment 3.

As discussed in paragraph 15.2.3.1.3.1 of the FSAR, the feedwater line break was analyzed using the CESEC-ATWS code, with modifications for incorporating the Henry-Fauske correlation into the feedwater line break model, for controlling rampdown of the effective steam generator heat

-2 transfer area, and for automatically changing the disposition of systems affected by the loss of offsite power. A complete CESEC-ATWS input listing for the worst case feedwater line break (0.2ft 2 break, instan taneous rampdown of heat transfer area, failure of one auxiliary .

feedwater pump, stuck CEA, loss of offsite power) is given in Attachment 6.

A description of the input data to the TORC code is given in Appendix B of CENPD-161. The numerical TOPC input listing for the full power steam line breaks.-is given in Attachment 7. Card 2 of card group 11, the input location for transient operation conditions, contains values for nominal full power conditions. Transient values for these variables are obtained from CESEC output.

ATTACHMENT 1 Description of CESEC Inputs (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

  • C ATTACHMENT 2 Description of CESEC-ATWS Inputs Not Listed in Attachment 1 (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

ATTACHM1ENT 3 CESEC Input Listing for the Full Power Steam Line Break Inside Containment With Offsite Power Available, Failure of One High Pressure Safety Injection Pump, and Stuck Control Element Assembly (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

ATTACHMENT 4 CESEC Input Listing for the Full Power Steam Line Break Inside Containment Without Offsite Power Available, Failure of One High Pressure Safety Injection Pump, and Stuck Control Element Assembly (only that data which is different from the data in Attachment 3 is listed)

(The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

ATTACHMENT 5 CESEC Input Listing for the Hot Zero Power Steam Line Break Outside Containment Without Offsite Power Available,Control Failure of One High Pressure Safety Injection Pump, and Stuck Element Assembly in Attachment 3 is (only that data which is different from the data listed)

(The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

ATTACHMENT 6 CESEC-ATWS Input Listing for the Worst Case Feedwater Line Break ith Loss of Offsite Power, Failure of One Auxiliary Feedwater Pump, and Stuck Control Element Assemblv (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

ATTACHMENT 7 TORC Input Listing for Full Power Steam Line Break (The material contained in the attachment is proprietary in its entirety and is therefore not included in the non-proprietary version.)

PAPRIETARY INFORMA11N NOTICE THE ATTACHED DOCUMENT CONTAINS "PROPRI ETARY INFORMATION" AND SHOULD BE HANDLED AS NRC "OFFICIAL USE ONLY" INFORMATION. IT SHOULD NOT BE DISCUSSED OR MADE AVAILABLE TO ANY PERSON NOT REQUIRING SUCH INFORMA TION IN THE CONDUCT OF OFFICIAL BUSINESS AND SHOULD BE STORED, TRANSFERRED, AND DISPOSED OF BY EACH RECIPIENT IN A MANNER WHICH WILL ASSURE THAT ITS CONTENTS ARE NOT MADE AVAILABLE TO-UNAUTHORIZED PERSONS.

COPY NO.

DOCKET NO.

CONTROL NO.

REPORT NO.

REC'D W/LTR DTD.

NRC Form 190 (4-78)

PROPRIETARY INFORMATION