ML20198F749
| ML20198F749 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 01/16/1978 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1155 NUDOCS 8605290075 | |
| Download: ML20198F749 (7) | |
Text
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4 Distribution Docket Filet NRR Reading RSB Reading JAN 1 g gg Newberry Chron Sc-%c s,b MEMORANDUM FOR:
- 0. D. Parr, Chief Light Water Reactor Br. #3, DPM FROM:
Thomas M. Novak, Chief, Reactor Systems Branch, DSS
SUBJECT:
SUPPLEMENTAL TESTIMONY ON WPPSS 1/4 ECCS The attached affadavit and testimony on WPPSS 1/4 ECCS by Scott Newberry of the Reactor Systems Branch is forwarded as requested. The ECCS performance evaluation for the WNP 1, 4 is in compliance with 10 CFR 50.46 and Appendix K and therefore is acceptable.
e Thomas M. Novak, Chief Reactor Systems Branch Division of Systems Safety
Enclosures:
As Stated cc:
S. Hanauer R. Mattson D. Ross.
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T. Novak G. Mazetis S. Israel T. Greene S. Newberry
Contact:
S. Newberry, NRR x27341 8605290075 780116 I
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NRC FORM 318 (9 76) NRCM 0240
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UrlITED STATES OF AfiERICA flVCLEAR REGULATORY C0f1l11SSIO!!
BEFORE Tile AT0:11C SAFE 1Y Af!D LICEriSillG BOARD In the flatter of
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WASHIflGT0fl PUBLIC POWER Docket flos. STil 50-460 SUPPLY SYSTEf4
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AFFIDAVIT OF SCOTT flEWBERRY I, Scott flewberry, having been duly sworn, state that:
'I am employed as a reactor engineer for the Reactor Systems Branch, Division of Systems Safety in the Office of fluclear Reactor Regulation with the U.S. fluclear Regulatory Commission. A copy of my professional qualifications
, is attached to this affidavit.
I am the author of the attached document entitled "flRC Staff Supplemental Testimony of Scott flewberry on WPPSS 1/4 Emergency Core Cooling System Performance," and believe it to be accurate to the best of my knowledge and belief..
,p Scott F. flewberry tiubscribed and sworn to before ma this 13th day of January, 1978.
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NotaryQub.Lic My Ccmnission Expires July 1,1978 1_
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W Professional Qualifications Scott F. !!cwherry Reactor Systems Branch Division of Systems Safety U.S. ?!uclear Regulatory Comission fly name is Scott. F. flewherry.
I am employed as'a Reactor Engineer, Reactor Systems Branch, Division of Systems Safety, U.S. fluclear Regulatory Conmission,11ashington, D.C.
The Reactor Systems Branch is responsible for evaluating the capability of reactor safety systems needed for safe shtitdown during normal and accident conditions, including the performance of emergency core cooling systems.
I attended the United States flaval Academy, Annapolis, Maryland, and received a B.S. degree in 1970.
I am currently attending the Graduate School of Engineering at the Catholic University of America. Washington, D.C.
as a part-time student.
From 1970 to 1971 I attended the flavy fluclear Power Training Program which consisted of training at the fluclear Power Training School, Bainbridge, flaryland, and the 53G submarine reactor prototype in llest flilton, flew York.
From 1972 until 1974 I worked as a qualified Engineering Officer of the Watch abbard the USS Daniel Boone SSBil 629 (BLUC), a nuclear fleet ballistic missile submarine. fly primary assignment was to serve as the ship's Main Propulsion Assistant and Radiological Controls Officer during this period.
I was responsible for the ship's reactor coolant system and steam system propulsion machinery and the control of all radioactive material on board.
In 19741 qualified as fluclear Engineering Officer in the flaval Reactors Program.
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Frto 1974 to 1976 I served as Ucapons Officer, U5S flathan llele SSP.fi 623 (GO' D).
During c:ost of t his period I was involved in the ship's pre-critical and power range testing program durii.9 the nucleat refueling overhaul as a Comand Outy Of ficer, in Deceniber 1976, { started working for the Reactor Systems Branch, Division of Systems $afety, U.S. l'uclear pegulatory Comnission as a reactor engineer.
I have revicwed several construction permit, and prelininary design approval applications in the-reactor systems areas including the perfonnance evaluation of cmcrgency con e cooling systems.
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!!RC STAFF SUPPLEMEilTAL TESTIM 0ilY
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Or SCGIT f1EWCERRY Oil WPPSS 1/4 ElCRGEfiCY CORE C00LIflG SYSTEM PERFORMMCE The staff reported its evaluation of emergency core cooling system (ECCS) performance for WPPSS fluclear Projects (Wr;P) 1 and 4 in reference 1. -We concluded in this_ testimony that the ECCS performance for Ut4P-1, 4 was fri compliance with 10 CFR 50 and Appendix K.
Since the issuance of reference 1, additional analyses were requested to address recent ECC5 analysis changes made by Babcock & Wilcox and to compare the difference in the Wi1P rower level and reactor coolant pump flow parameters to the generic analysis in DAW-10102 (reference 2).
The staff received by reference additional calculations fro;n the applicart (references 3, 4) to show that BAW-10102 adequately defines the " worst-case" situations and maintains sufficient margins to the limits specified in 10 CFR 50.46.
The applicant also sub'nitted calculaticns to confirn that
' the generic analysis in BAW-10102 bounds W:!P-1, 4 (references 5,6)..The input parameters for these calculations were revised to model a core power level of 3600 f1Wt and a reactor coolant pump flow rate of 103,500 gallons per minute which are appropriate for W!4P-1, 4 The minimum centain-ment backpressure calculation was chosen to conservatively bound the kiiP-1, 4 plant-specific calculation previously reported and justified in Appendix A to BAW-10102.
The computer models were' modified to be censistent with the most recent evaluation model determined to be acceptabic by the staff.
The following model changes were included in this ar,alysis:
(1)a 0.25 psi pe'nalty in the cold leg pressure drop due to high pressur.e injection during reflooding as required by reference 7, (2) THETA revised post-CHF heat transfer logic as approved in reference 8, and (3) CRAFT 2 revisions as approved in reference 9.
The peak cladding temperature at the core mid-plane for this analysis is 2064 F wh'ch is 62 F below the value reported 0
in BAW-10102 and well below the 2200 F limit required by 10 CFR 50.46.
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2 The maximum local oxidation was calculated to be 4.27 ' which is below the value reported in BAW-10102 and the 17 limit specified in 10 CFR 50.46, This calculatinn also concludes that the whole-core nietal-water reaction will be less than 1% and that the core geometry remains amenable to cooling such that long-term cooling can be established.
These additi'onal analyses f.herefore show that the conclusions of the previous testimony (reference 1) describing ECCS performance remain applicable, and that i
compliance with the acceptance criteria of 10 CFR 50, Appendix K, has been demonstrated.
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References 1.
Supplemental Testimony of T.11. Cox in flWMP1, 4 Proceeding, at TR page 714.
2.
BAW-10102 ECCS Evaluation of B&W's 205 FS flSS Revisicn 2, December 1975.
3.
Large Break ECCS Evaluation of B&W 205 FS flSS Using the August 1977 ECCS Evaluation flodel (BAW-10104, Rev. 3), September 30, 1977.
4.
Letter from D. L. Renberger (WPPSS) to 0. D. Parr dHRC),- WPPS fiticlear Projects 1 and 4 ECCS Evaluation Model, January 5,'1978.
5.
Letter from D. L. Renberger (WPPSS) to 0. D. Parr (NRC), WPPS fluclear Projects 1 and 4 ECCS Evaluation 14odel, January 10, 1978.
6.
Letter from James A. Taylor (B&W) to S. A. Varga (fiRC), BAW-10102 ECCS Analysis of P,&W's.205 FS flSS at 3GC0 liW and 103,500 gpm RCS flow, January 10, 1978.
7.
Letter from A. Schwencer'(flRC) to I. E. Suhrke (B&W), January 8,1976.
8.
Letter from S. A. Varga (ffRC) to K. E. Suhrke (B&W), February 18, 1977.
9.
Letter from S. A. Varga (flRC) to K.J E. Suhrke (BaW), flay 13, 1977.
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