ML18113A261

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LER 1976-028-00 for St. Lucie Unit 1, Hydrogen Sampling System Isolation Valves Update Report No. 1
ML18113A261
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 03/04/1977
From: Schmidt A
Florida Power & Light Co
To: Moseley N
NRC/IE, NRC/RGN-II
References
PRN-LI-77-57 LER 1976-028-00
Download: ML18113A261 (8)


Text

NRC FORM 195 U.S. NUCLEAR RFGULATORY COMMISSION DOCKET NUMBER 12.76)

FILE NUMBER NRC DISTRIBUTION FDR PART 60 DOCKET MATERIAL INCIDENT REPORT TO: FROM: DATE OF DOCUMENT DATE RECEIVED Q LETTER QNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED QORIGINAL Q UN C LASS IF I E D QCOPV DESCRIPTION ENCLOSURE PLANT NAME:

NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION BRANCH CHIEF: p) Cm4n~

W 3 CYS FOR ACTION LIC, ASSTo:

W CYS ACRS g CYS~BTNG S 'NT $

'EG INTERNAL D ISTRI BUTION FTLE X&E (2 MIPC SCHROEDER/XPPOLXTO HOUSTON NOVAK/CHECK GRDIES CASE BUTLER HANAUER TEDESCO/MACCARY EISEiVHUT BAER SHAO VOLL1%R/BUNCH KRI?GER/J COLLXNS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: C~C4r TIC:

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o d5 NRC FORM 196 (2.76)

NRC FOQM 195 U Sr NUCLFAR RFGULATORV COMMISSION DOCKET NUMBER (2-76},i 50-335 FILE NUMBER 4RC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO: Mr. Norman g. Moseley FROM: Florida Power & Light Co DATE OF DOCUMENT Miami, Flao 33101 3-4-77 A D Schmidt DATE RECEIVED 3-17-77 KILETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED QORIGINAL ERINC LASS IF IE D Kcor v DEscRIPTIQN Ltr trans the following: Lic>> Event Report 76-28 furn undate report No. 1 involving hydrogen mII~ikkagx sampling system. isolation valves. ', ~ (2P)

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DONOr REMOVE St; Lucie Unit 1:

"ACKNOWLEDGED;

'HL C SAFETY FOR ACTION/INFORMATION ASSIGNED AD:

O C~MANA PROJECT MANAGER~

L C ASST LXC ASST INTERNAL D IST R I BUTION REG FILE SYSTEMS SAFETY PLANT SYSTEMS SXTE SAFE NRC PDR HEINEMAN TEDESCO

~ CCHROEDER OELD GOSSXCK & STAFF ENGINEERING IPPOLXTO ENV 0 MIPC MACARRY ERNST CASE BOSNAK BALLARD HANAUER SIIGJEIL OPERATING REACTORS YOUNGBLOOD HARLESS PAWLICK STELLO SITE TECH PROJECT MANAGEMENT REACTOR SAFE OPERATING TECH GAMIIILL BOYD ROSS EISENHUT STEPP P COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON CHECK BUTt E SITE ANALYSIS MELTZ VOLLIIER HELTEMES AT& I SKOVHOLT SALTZMAN J, COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR NA~TLAB B OOQI ggg NA TIC: V IE 'EG ULR KSON OR 1 NSIC LA PDR ~ ~

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NRC FORM I95 I2.76)

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FLORIOA POPOVER Bt LIGHT'COMPANY March 4, 1977 PRN-LI-77-57 88ylla106 t

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Mr. Norman C. Moseley, Director, Region II ~~CFi<'(0, Office of Inspection and Enforcement U'. S. Nuclear Regulatory Commission -l7-7W 230 Peachtree Street, N. W., Suite 1217 Qt 1'IIIarAII g~0 (jQ Atlanta, Georgia 30303 COJN415gI0I1

Dear Mr. Moseley:

,SPY QQ REPORTABLE OCCURRENCE 335-76-28 ST: LUCIE UNIT 1 DATE OF OCCURRENCE: JUNE 4, 1976 HYDROGEN SAMPLING, SYSTEM lSOLATION VALVES UPDATE REPORT NO. 1 The attached Licensee Event Report is be'ng submitted to update our initial report of June 18, 1976.

Very truly yours, A. D. Schmidt Vice President Power Resources MAS/cpc Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (40)

Director, Of ice of Management Information and Program .Control (3)

O>o~lo$ eQ PEOPLE... SERVING PEOPLE

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CONTROL SLOCK:

UC EN SEE NAME t LICENSEE EVENT REPORT UCEN8E 6

'UM8ER INlTIAL REPORT- JUNE SE PRINT AU. REOUIRED INFORMATION)

LIEN8 E TYP E ~

EVENT TYPE 18, 1976

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0 0 I, 1 I1 1 1 ~01

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7 14 15 25 26 30 31 32

[QD1] CQN'7 7 8 CATEGORY 57 EVENT 0ESCRIPTION 58 REPORT, TYPE 59 REPORT SOURCE

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OOCICET NUMSER 0 0 I 68 69'4 0 I 6 EVENT DATE 0 4 7 I 6, 0 75 REPORT DATE 4 7 7 80 isolation 1

~02 Review of the testine rouosed for Unit 2 h dro en samolin s. stem valves 1 ed 8 9 7 8 9 or r fo t dentical Unit 1 valves Unit 1 F AR 80 WOI4 7 8 9 I Section 3. 1 3 c 1 assif ies these valves as environmenta 1 cateeor 1A. However . it has been ao I

Qg8 7 9 de termined that the Unit 1'alves have not been t e tes ted for the Dro os ed environment 80 6 in accordance vrlth IEEE- 2 1971 because the recuirement to do so was not soecif ied in 7 8 9 PAVE ao SYSTEM CAUSE CCMPONKMT M~4F~

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COMPONENT COOS A L 17 SUPPI A

43 M

44 X I 9 I 9 9 47

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48 CAUSE OESCRIPTION Unit gl dro en sam 1 in system isolat ion valves were not tested for cate or 1A enviror a 9 ao 7

g 8 9 m ta ndi i ns in accordance with IEEE- 2 1 71 because the re 'uirement to do so Q~g +was ot st ci fiFid in the purchase order 7 8 9 80 FAC.'STY METHOD OF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY OESC IPMN 7

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~B ~05 0 NA 44

~d Purchase Order Review 1 0 12 13 45 46 FORM OF ACTWilTY CQATENT RECUSED OF R EL~8 AMOUNT OF MTNflY LCCATION OF RELEASE lzJ LzJ NA NA 7 8 9 10 11 44 PERSONNEL EXPO SURFS NA PERS0iVNEL INJURIES

[iAI LZoO~J NA PROBABLE CON 6EGUENCES NA 7 8 9 ao LOSS OR OAMAGE TO FACIUTY TYP'E OESCMCION NA 7 8 9 10 ao I

P U 8 LIC ITY

~1( 7 NA 7 8 9 En AOOITIGNAL FAcToRs See page 2 for continuation of Event Description.

a C'omnonent Manu facturer C irc 1 e Seal Coroorat on i ao ie 9 9 ao NA IIE: M.. Schoolman PPONE. 05 552- 3779

Reportable Occurrence 335-76-28 Licensee Event Report Update ¹1 Page Two the purchase order. As an interim corrective action, administrative guidelines were written to inform appropriate personnel of the action to be taken if the valves will not operate under post-accident conditions. (An alternate sample source has been developed via the plant purge system if required. ) Operations personnel have been informed that they should actuate the hydrogen recombiners if a containment hydrogen sample cannot be ts3cen. Based on FSAR hydrogen

. generation analysis for the existing plant design, the operator has 45 days to actuate either hydrogen recombiner before the hydrogen concentration reaches 4$ . The replacement hydrogen valves have been purchased from Valcor Engineering in accordance with IEEE-323 (1971) and will be installed during the first scheduled refueling following receipt of the valves. (335-76-28).