ML20214Q222

Errata & Addenda to LOCA Analysis Rept for Pilgrim Nuclear Power Station

ML20214Q222
Person / Time
Site:	Pilgrim
Issue date:	10/31/1986
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20214Q102	List: BECO-87-081, Application to Amend License DPR-35,consisting of Proposed Change 87-03,ensuring Safe Operation of Reload 7 Core Design During Cycle 8.Supporting Matl Encl.Fee Paid ML20214Q111 ML20214Q147 ML20214Q182 ML20214Q200 ML20214Q222
References
77NED148, NEDO-21696-ERR, NEDO-21696-ERR-05, NEDO-21696-ERR-5, NUDOCS 8706040291
Download: ML20214Q222 (3)

Text

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~ REGION 2 APPLICABLE TO:

NEDO-21696 ERRATA And ADDENDA

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T. I. E. NO.

77NED148 j

SHEET LOSS-OF-COOLANT ACCIDENT TIT u N O.

ANALYSIS REPORT FOR PILGRIM DATE October 1986 Nt?CTTAR PCMER STATION NOTE: Correct allcopin of the applicable ISSUE DATE AUGUST 1977 publicarion a specified below.

REFERENCES INSTRUCTIONS pfago ap*H (CORRECTIONS AND ADDITIONS)

NE) 1.

Page 3-1 Replace with.new page 3-1 2.

Page 7-1 Replace with new page 7-1 (Change bars in right-hand margin indicate areas where~ report has been revised.)

8706040291 870522 PAGE 1 np 1 PDR ADOCK 05000293 P

PDR

NEDO-21696

'i 3.

INPUT TO ANALYSIS A list of the significant plant input parameters to the LOCA analysis is presented in Table 1.

Table 1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOIANT ACCIDENT ANALYSIS

• l Plant Parameters:

Core Thermal Power 2037 MWt, which corresponds to 102% of rated core power Vessel Steam Output 8.14 x 106 lbm/h, which corre-sponds to 102% of rated core power Vessel Steam Dome Pressure 1050 psia Recirculation Line Break 4.34 ft2 (DBA)'

Area for Large. Breaks - Suction Number of Drilled Bundles 428 Fuel Parameters:

Peak Technical Initial Specification Design Minimum Linear Heat Axial Critical Fuel Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft)

Factor Ratio **

l A.

8DB219L 8x8 13.4 1.5 1.24 B.

8DB219H 8x8 13.4 1.5 1.24 C.

8DB262 8x8 13.4 1.5 1.24 D.

P8DRB265L 8x8 13.4 1.5 1.24 E.

P8DRB282 8x8 13.4 1.5 1.24 F.

P8DRB265H 8x8 13.4 1.5 1.24 G.

BP8DRB300 8x8 13.4 1.5 1.24

• Bundle type BP8DRB300 was analyzed with input parameters described in l

Reference 13.

• • To account for the 2% uncertainty in bundle power required by Appendix K, the SCAT calculation is performed with an MCPR of 1.22 (i.e., 1.24 divided by 1.02) for a bundle with an initial MCPR of 1.24.

I 3-1

NED0-21696 i

7.

REFERENCES j

1.

Letter, Dennis L. Ziemann (NRC) to G. Carl Andognini (BECO), "Re: Pilgrim Station Unit No.

1," dated March 11, 1977.

2.

Letter, Darrell G. Eisenhut (NRC) to E.D. Fuller (GE), Documentation of the i

Reanalysis Results for the Loss-of-Coolant Accident (LOCA) of Lead and Non-Lead Plants." June 30, 1977.

3.

General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10CRF50 Appendix K, NEDO-20566 (Draft), submitted August 1974, and General Electric Refill Reflood Calculation (Supplement to SAFE Code Description) transmitted to the USAEC by letter, G.L. Gyorey (GE) to Victor Stello, Jr. (NRC), dated December 20, 1974.

4.

" Safety Evaluation for General Electric ECCS Evaluation Model Modifications,"

letter from K. R. Go11er (NRC) to G. G. Sherwood (GE), dated April 12, 1977.

5.

Letter, A. J. Levine (GE) to D. F. Ross (NRC) dated January 27, 1977,

" General Electric (GE) Loss of Coolant Accident (LOCA) Analysis Model Revisions - Core Heatup Code-CHASTE 05."

6.

Letter, A. J. Levine (GE) to D. B. Vassallo (NRC), dated March 14, 1977,

" Request for Approval for Use of Loss of Coolant Accident (LOCA) Evaluations Model Code REFLOOD05."

4 7.

" Supplemental Information for Plant Modification to Eliminate Significant In-Core Vibrations," Supplement 1, NEDE-21156-1, September 1976.

8.

" Supplemental Information for Plant Modification to Eliminate Significant In-Core Vibrations," Supplement 2, NEDE-21156-2, January 1977.

}

9.

Letter,R. Engel (GE) to V. Stello (NRC), " Answers to NRC Questions on l

NEDE-21156-2," January 24, 1977.

10. Letter, G. L. Gyorey (GE) to V. Stello, Jr., dated May 12,1975, " Compliance with Acceptance Criteria for 10CFR50.46."

11. Letter, Lee Liu (IEL&P) to Edson G. Case (NRC), Letter No. IE-77-1453, dated July 29, 1977.

12. Letter, Thomas J. Galligan, Jr., (BECO) to Director, Division of Reactor Licensing (NRC), dated July 9,1975, "10CFR50 Appendix K and Proposed Technical Specifications For Pilgrim Nuclear Power Station, Unit 1."

13. " Pilgrim Nuclear Power Station Loss-of-Coolant Accident (LOCA) Analysis Update," NEDO-30767, September 1984.

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