ML18142B214

LER 1978-005-00 for R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical

ML18142B214
Person / Time
Site:	Ginna
Issue date:	05/02/1978
From:	White L Rochester Gas & Electric Corp
To:	Grier B NRC/IE, NRC Region 1
References
LER 1978-005-00
Download: ML18142B214 (8)

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'N5 ROCHESTER GAS AND ELECTRIC CORPORATIOH ~ 89 EAST AVENUE, ROCHESTER, H.Y. I4649 CD C"7 TESEPHDNE Pf/

LEON O. WHITE. JR VICE PRESIDENT RRE L CODE T I S@46 2780 I eH

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May 2, 1978 C/7 XX~ CO~

n~~o y g Mr. Boyce H Grier, Director

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C7 U. S. Nuclear Regulatory Commission C/l Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

LER 78-005/01T-O, unplanned reactivity insertion of more than 0. 5%+K/K while subcritical R. E Ginna Nuclear Power Plant, Unit No. 1

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Docket No. 50-244

Dear Mr. Grier:

In accordance with Technical Specifications, Article 6. 9.2.a(4),

if subcritical, an unplanned reactivity insertion of more than 0. 5%+K/K, the attached report of Reportable Occurrence 78-005, 14-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

Very truly yours, L. D. White, Jr.

Attachment cc; Dr. Ernst Volgenau (40)

Mr. William G. McDonald (3) p'l/

78/240052

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-244 REC: GRIER B H ORG: WHITE L D DOCDATE: 05/02/78 NRC ROCHESTER GAS 5 ELEC DATE RCVD: 05/05/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i FORWARDING LICENSEE EVENT REPT (RO 50-244/78-005/0iT-'0) Ohl 04/i9/78 CONCERNING UNLICENSED OPERATOR OPENED THE WRONG DI RESIN OUTLET VALVE AND THEN OPENED THE CORRECT VALVE PRIOR TO CLOSING THE FIRST ONE... W/ATT.

PLANT NAME: RE GINNA UNIT i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +~++++++++++>+>+>+ f/'++++++++++++++++

INCIDENT REPORTS

<DISTR1BUTION CODE A002 FOR ACTION: BR CHIEF ZIEMA ++W/4 ENCL INTERNAL: G FILE+~W/ENC NRC PDR++W/ENCL AL4A2 MIPC++W/3 ENCL SCHROEDER/IPPOLI T04+W/ENCL HOUSTON4+W/ENCL NOVAK/CHECK++W/ENCL EEB++W/ENCL KN I GHT++W/ENCL BUTLER4+W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EI SENHUT++W/ENCL BAER+4W/ENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL, KREGER/J. COLLINS4+W/ENCL ROSA+4W/ENCL K SEYFRIT/IE+>W/ENCL EXTERNAL: LPDR S ROCHESTER NY+4W/ENCL TI C++W/ENCL NSIC~~W/ENCL ACRS CAT B++W/16 ENCL COPIES NOT SUBMITTED PEP."

REGULATORY GUIDE 10.1 I

DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78i240052 SIZE: iP+iP+iP /

THE END

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NtiC Fi>RIVI 36/ U. S. NUCLEAR REGULATORY COMMISSION I (7".77 I P 78-005/01T-0 LICENSEE EVENT REPORT (CAR 1180)

CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 toOi} N Y 7 8 9 R E LICENSEE CODE G 1Q70 14 15 0 0 0 0 LICENSE NUMBER 0 0 0 0Q44 25 26 1 1 1 LICENSE TYPE 30 Q4~Qs 57 CAT 58 CON'T

~o ~LQ6 0 5 0 0 0 2 4 4Q70 4 1 9 7 8QBO 74 75 5 0 2 7 8 80 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 10 During resin removal from the A deborating DI operator erroneously opened both A and B deborating DI resin outlets thereb creatin ath for reactor makeu water to the reactor coolant system which was in refueling mode. Before error was corrected, primary loop boron concentration decreased from 2 140 ppm to 2072 ppm. This resulted in an un-planned reactivity insertion of more than 0 ~ 5%~K/K (T. S . 6.9 ~2 .a (4)); however the primary loop boron was not reduced below the 2000 ppm required for refueling mode operation 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OS ~PC Q>> A QI2 ~BQ73 V A L V E X Q74 ~DQls ~X Qls 7 8 9 10 11 12 )3 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q

LERIRO

'4' ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

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23 SHUTDOWN

~00 24 REPORT NO.

9 26

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~01 28 ATI'ACHMENT CODE 29 NPRDR TYPE

~T 30

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PRIME COMP, 3I

~0 NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 022 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~II Qs~GQis ~ZQtp ~ZQ77 O O O 0 Y Qss ~NQ74 Z Qs Z 9 9 9 Qs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 p Unlicensed operator opened the wrong resin outlet valve and then opened the correct valve prior to closing the first one. Operator instructed to follow procedure. Procedure change instituted to increase clarity.

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~14 7 8 9 80 CZ38 9 II FACILITY STATUS Qps ~all 4 POWER 0 Qss OTHER STATUS ~

~3P METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 0 erator observation 10 12 i3 44 45 46 80 ACTIVITY CONTENT 6

RELEASED OF RELEASE

~Z Q33 ~ZQ34 AMOUNT OF ACTIVITYQS NA I.OCATION OF RELEASE NA Q

7 8 9 10 44 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 Qpr ~Z Qss NA 7 8 9 11 12 13 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 43 9 Z Q42 7 8 9 10 80 O

ISSUED PUBLICITY DESCRIPTION ~ NA NRC USE ONLY 8 9 10 68 69 80 o NAME OF PREPARER Carl H. Peck PHQNEI 716 546 2700 ext. 291-205

Attachment to LER 78-005/01T-0 Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket 050-0244 During performance of Procedure S-4. 5. 9, an auxiliary operator was in the process of removing resin from the "A" deborating demineralizer to the "B" spent resin storage tank. The procedure was written so that it could be used to sluice resins from either "A" or "B" demineralizers. The operator opened the "B" demineralizer resin outlet valve, then, realizing his error, he opened the "A" demineralizer outlet without reclosing the "B" outlet. This created a path for reactor makeup water to the reactor coolant system, which was in the refueling mode. After realizing the second error, the operator reclosed the "B" outlet.

The Shift Foreman stopped the sluicing procedure and obtained a primary system boron analysis which indicated a boron concentration decrease from 2140 ppm B to 2072 ppm B. This corresponded to an unplanned reactivity insertion of more than 0. 5% QK/K (T.S. 6. 9. 2.a(4)); however, the primary loop boron was not reduced below the 2000 ppm B required for refueling mode operation.

The operator checked the procedure and the proper flow path before continuing with the procedure. The operator was orally instructed on the importance of following procedures rigorously. The Operations Engineer directed all Shift Foremen to impress the same upon their personnel. Because of the confusion stemming from the dual-use procedure that procedure was deleted and replaced by separate procedures, one for each deborating demineralizer.

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NRC F Og M 366 I7-77)

PP'ONTROL BLOCK:

f LlCENSEE EVENT REPORT Qi U. S. NUCLEAR REGULATORY COMMISSION (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)

(CAR 1176)

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~001 1N Y R E G 1 Q 0 - 0 0 0 0 0 0 0 Qs 4 1 1 1 1 Qs 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 7 8 9 LICENSEE CODE CON'T

~01 """ ~LQB 0 5 0 0 0 2 4 4 7 0 3 0 4 7 8 74 B

75 0 3 3 1 REPORT DATE 7 8 80 QB DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During routine round operator found "A" Diesel Generator (DG) pre-lube pum off. Fur-

~03 ther investigation showed its motor control center (M CC) 1 H de-energized as MCC 1 C supply breaker to 1H was tripped . Although loss of pre-lube pump does not affect capa 6 bility of DG to start, availability of "A" DG fuel transfer pump was affected (T.S 6 9 ~ ~ ~

6 2 b (2) ) A" DG was still capable of auto-start with at least 3 hr. fuel in day tank . "B" CZ30 7 DG was also available for auto-start and pre-start check was initiated to place it in operation; however, corrective action was completed and MCC 1H was re-energized before start completed. 80 7 8 9 COMP SYSTEM CAUSE CAUSE VALVE CODE CODE SUBCODE COMPONENT CODE SIJBCODE SUBCODE

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~EO>>

9 10 11 E 0>> ~AO>>

12 13 C K T B R K 18 074 ~AQTE 19

~ZQTR 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LERiRO REPQRT ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

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23 SHUTDOWN 24 REPORT NO.

~00 4 26 QH 27

~03 28 ATTACHMENT CODE 29 NPRDC TYPE UL 30 PRIME COMP.

LJ 3'I Uo NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~S(>>)~ZOTR ~ZOER L~JQ>> O O O O ~WORE LVJQ4 ~WQs W 1 3 O Qs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 0 poor electrical connection caused thermal device tri . Cable was cut back 3 in. and new connection made to breaker. This is an isolated case as ti htness of connection s verified during annual maintenance to preclude such events. Control Room annuncia-3 tion of inoperable status of MCC 1H and MCC 1 will be art of the ro osed "Diesel 4 Generator Inoperative" annunciators discussed in our November 16, 1977 letter.

80 7 8 9 FACILITY METHOD OF POWER OTHER STATUS Q30 DISCOVERY DISCOVERY DESCRIPTION Q32

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7 8 STATUS

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13 NA 44

~BQ31 45 46 0 erator ins ection round 80 ACTIVITY CONTENT RELEASED OF REI.EASE AMOUNTOF ACTIVITY NA LOCATION OF RELEASE Q 6 ~Z Q33 ~ZQ34 NA 10 44 45 80 7 8 9 11 PERSONNEL EXPOSURES DESCRIPTION Q39 NUMBER TYPE

~00 0 &zOER 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES 12 80 7 8 9 11 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION Z Q42 NA 80 7 8 9 10 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q NA

~20 ~NQ44 68 69 80 E, 7 8 9 10 J. C. Noon PHDNE1 6/546-2700,ext

.291-215 NAME OF PREPARER