ML19317G462
| ML19317G462 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/19/1975 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003160072 | |
| Download: ML19317G462 (5) | |
Text
{{#Wiki_filter:. _. - -. NRC DISTRIBUTIGN FOR PART 60 DOCKET MATERIAL o (TEMPORARY FORM) CONTROL NO: loo 6'/ FILE: FROMF1 rdia P wer corp. DATE OF DOC DATE REC'D LTR TWX RPT OTHEh Drystal River J.T. Rodeers 9-19-75 9-22-75 vvy TO: ORIG CC OTHER SENT AEC POR X'G NFC 1 siEea 2 SENT LOCAL PDR vvv CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO: XXX 3 50-302 DESCRIPTION: ENCLOSURES: Letter furnishing additional infor::aticn concerning the Crystal River Unit # 3 E=ergenc Core Cooling System (ECCS)..... With Attachments 1 thru 4. (3 Copies Enclosure Received) PLANT NAME: Crystal River #3 FOR ACTION /INFORMATION _ ____.__SAS 9-22-75 BUTLER (L) fSCHWENCER (L) ZIEMANN (L) REG AN (E) u 7w .aCIm 0WLsr 3uu W/ Copies W/4 Copies W/ Copies W/ Copies CLARK (L) STOLZ (L) DICKER (E) LEAR (L) W/ Copics W/ Copies W' Copies W/ Copies DO NOT R,,,7mue y n PARR (L) VASSALLO (L) KNIGHTON (E) SPIES W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNGB LOOD (E) LpH W/ Copies W/ Copies W/ Copies W/ Copies INTERNAL )lSTRIBUTION 911EG FILD _ TECH REVIEW DENTON LIC ASST A/T IND. fNRC PDR SCHROEDER GRIMES R. DIGGS (L) BRAITMAN /OGC, ROOM P 5063 MACCARY GAMMILL H. GEARIN (L) SALTZMAN /. GOULBOURNE (t(brR) MELTZ /GOSSICK/STAF F KNIGHT KASTN ER E AASE PAWLICKI BALLARD P. KREUTZER (E) AIAMBUSSO SHAO SPANGLER J. LEE (L) PLANS /BOYD /STELLOM M. RU3'IBR00K(L) MCDONALD MOORE (L5 HOUSTON ENVIRO S. REED (E) CHAPMAN DEYOUNG (L) ,/NOVAK(J) MULLER M. SERVICE (L) DUBE (Ltr) SKOVHOLT (L) /ROSS DICKER S. SHEPPARD (L) /E. COUPE (cre GOLLER (L) (Ltr) IPPOLITO KNIGHTON M. SLATER (E) PETERSON P. CO LLINS <TEDESCO YOUNGBLOOD H. SMITH (L) HARTFIELD (2) DENISE J. COLLINS REGAN S. TEETS (L) KLECKER REG OPR / LAIN AS < PROJECT LDR G. WI LLI AMS (E) EISENHUT / FILE & REGION (2) BENAROYA ~B A:w a__ V. WILSON (L) WIGGINTON HIPC VOLLMER HAM LESS R. INGRAM (L) 'hh 5 M. DUNCAN (E) EXTERN AL DISTRIBUTION /1 - LOCAL PDR ' ~ ~ (:.,-.7 ; lu, /1 - TIC (ABERN ATHY) (1)(2)(10) - NATION AL LABS 1 - POR SAN /LA/NY /1 - NSIC (BUCH AN AN) 1 - W. PENNINGTON, Rin E-201 GT 1 - BROOKH AVEN N AT LAB 1 - ASLB 1 - CONSU LTANTS 1 - G. ULRIKSON ORNL 1 - Newton Anderson N EWM AR K/B LUM E/AG B ABI AN 4-ACRS liOLCi-Ne/SENT t. A. ggg 8003100471 /- ,../ cc i g./
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-nue :" Florida Power-coa'?a"'oa September 19, 1975 gy.o Cy. Mr.'A. Schwencer, Chief gaicdater'll Light Water Reactors Branch 2 ~,g W~7,2, -.c-x" N k(v" Directorate of Licensing '. ]- f Office of" Regulation 'a U.S. Nuclear Regulatory Co m,ission = %
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In Re: Florida o'wei$g67. ped {tenrM
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Crystal River Unit #3 Docket No(g150-3025-* Dwktt We /q7 (, [/ '({rym-;f,,
Dear Mr. Schwencer:
I %yy e This is in response to your letter o July 7, 1973, in which you requested Florida Power Corporation to supply additional information concerning the Crystal River Unit #3 Emergency Core Cooling System (ECCS). Attached are three (3) copies of our response to Items 1 through 4 of Attachment 1 of your July 7 letter in question and answer form. Our response to Item 5 sf Attachment 1 will be submitted to-your staff by October 15, 1975, as previously in-dicated in our letter to you dated August 25, 1975. If you require any additional information or discussion concern-ing the attached responses, please do not hesitate to contact this office. Very truly yours, J. Rodgers Asst. Vice President JTR/iw Enclosures. f.Q00
~ REQUEST FOR ADDITIONAL INFORMATION Item 1. ' Break Spectrue and Partial Loop Operation. The information provided for each plant shall comply-with the provisions of the attached memorandum entitled, " Minimum Requirements for ECCS Break JSpectrum Submittals." Response to Item 1. On May 29, 1975, and July 9, 1975, Babcock 4 Wilcox (NSS supplier for Crystal River Unit 3) submitted to the Commission copies of their non-proprietary topical reports BAW-10104, "B4W's ECCS Evaluation Model," and BAW-10103, "ECCS Analysis of B4W's 177 FA Lowered Loop NSS," respectively. Topical report BAW-10104 describes the generic BSW ECCS Evaluation Model and demonstrates the compliance of this model to Appendix K of 10 CFR 50. Both the large and small break models are included in this report. Topical report BAW-10103 describes the B4W ECCS evaluation for the Oconee class of plants in con-formance to the requirements of 10 CFR 50.46. Section 6.0 of this topical report contains a complete break spectrum analysis that meets the requirements outlined in your memorandum entitled, " Minimum Re-quirements for ECCS Break Spectrum Submittals." Topical reports BAW-10104 and BAW-10103 are applicable to Crystal River Unit 3 and have been incorporated by reference in our license application via of our letter to Mr. A. Giambusso, Director, Division of Reactor Licensing, dated July 24, 197.. The ECCS analysis for the LOCA during partial loop-operation war submitted to the-Commission by Babcock 6 Wilcox on September 11, 1975, as a revision to -topical report BAW-10103. The results of these analyses show that peak cladding temperatures are significantly below the. full loop operation results reported in BAW-10103. Two cases of 3 pump operation were analyzed at the maximum kw/ft LOCA limit for ~ 4' pump operation as established in BAW-10103. The worst case break r.ssumed is identical to that report in BAW-10103. This revision.to topical ~ report BAW-10103 addressing partial loop operation is applicab.!e to Crystal River Unit 3 and will be incorporated by zeference in our license application via of Amendcent No.~47 to the ~ Crystal River Unit 3_ Final Safety Analysis Report.
c, -h ~ s- { 1-Item 2 Potential Boron Precipitation (PWR's only) The.ECCS system in each plant should be evaluated by the applicant (or licensee) to show that significant changes in chemical concentrations will not occur during the long term after a loss-of-coolant accident (LOCA) and these' potential changes have been specifically addressed by appropriate operating procedures. Accord-ingly, the applicant should review the system capabilities and operating procedures to assure that boron precipitation would not compromise long-term core cooling capability following a LOCA. This review should consider all aspects of the specific plant design, including component qualifi-cation in the LOCA environment in addition to a detailed review of operating procedures. 'The applicant should examine the vulnerability of the specific plant design to single failures that.would result in any significant boron precipitation. Response to Item 2. -Boron concentration in the post-LOCA, long term cooling environment has been analyzed for the potential of unacceptably high boric acid concentration in the core region on a generic bases in the Babcock and Wilcox topical report BAW-10103. The CR#3 operating procedures outlined below will preclude any significant changes in chemical concentrations during longterm cooling subsequent to a LOCA. T-he bases for these procedures is Section 10 of the B6W topical report,.BAW-10103, dated June, 1975. The modes of long-term cooling are scoped below and should be instituted 15 minutes after a LOCA. At that time, it is assumed that the BWST is empty and the LPI is'taking suction from the reactor building sump. For this scoping, it is assumed that decay heat string "A" will be used to force flow through the core while string "B" continues to take suction from the reactor building sump. Mode I If'both LPI strings are operable, isolate string "A", then attempt to pull suction on the decay heat drop line through string "A" and into the core. If this is accomplished, string "B" may be shut down to see if only one LPI string is needed. If chis is successful, string "B" may be placed back in operation or be operated periodically to make up for volume contraction. (See attached Figure I.) l l.
.R ~ ITEM 2 - PAGE 2. If Mode I is unsuccessful, maintain . flow in the, reactor through two inj ection paths: (1) two LPI paths from one LPI via the LPI discharge cross-connect-valves; -or (2) one LPI and one HPI path via the LPI-HPI cross-connection, then proceed to Mode II. Mode II Attempt to gravity drain the reactor to the reactor building sump through the decay heat drop line and the "A" string sump suction line. (cee attached Figure II.) Mode III If Mode II is unsuccessful, establish flow into the pressurizer through the auxiliary spray line from string "A". (See attached Figure III.) Mode IV Establish _ flow through the LPI discharge cross-connect line through the "A" string (reverse flow), then through the decay heat line to the reactor. (See attached Figure IV.) The application of these procedures outlined above at CR#3 will preclude significant changes in chemical concentrations during long-term cooling subsequent to a LOCA. The vulnerability of these modes of operation used for the control of chemical concentrations to single failures is analyzed in Section 10 of topical report BAW-10103. This analysis, which concludes that these modes together meet the single failure criteria and will effectively limit the boron concentration ratio, is applicable to Crystal River Unit 3.
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